Sample records for icebreaker arktika reactor
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ERIC Educational Resources Information Center
Peerbhoy, Denise; Bourke, Cathriona
2007-01-01
Objective: To document young people's and teachers' responses to "Icebreaker", a Theatre in Education (TIE) performance exploring themes of sexual health and relationships, in relation to "Healthy Arts"' objectives. Design: Data reported here were part of a wider evaluation of a government funded scheme. Setting: Data was…
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New U.S. icebreaker to advance Arctic Marine Science
NASA Astrophysics Data System (ADS)
Swift, Jim; Clough, Lisa; Berkson, Jonathan; DuPree, George; Falkner, Kelly
The decades-long planning for a U.S. icebreaking vessel dedicated to Arctic marine science reached its goal with the entry into service of the UGCGC Healy, a polar research vessel operated by the U.S. Coast Guard for the U.S. science community. The ship is named for Captain Michael A. Healy, a legendary figure of Alaskan history who served as commanding officer of the U.S. Revenue Cutters Corwin (1884-1885) and Bear (1886-1895).Healy is 128 m long, 25 m wide, displaces 14,900 metric tons, and traverses up to 1.4 m ice at 1.65 m s-1, propelled by two 11.1-MW AC synchronous motors fed from DC diesel electric engines through cycloconverters. Thus, Healy is more powerful and somewhat larger than the German polar research vessel Polarstern or the Canadian icebreaker Louis S. St-Laurent. Healy's power system responds quickly to the load changes common in icebreaking. The ship has a conventional icebreaker bow. The hull provides a sea-kindly ride and more stable work conditions in open water than do the U.S. Coast Guard Polar-class icebreakers. The ship is designed to work in any Arctic season.
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Energizers and Icebreakers for All Ages and Stages.
ERIC Educational Resources Information Center
Foster, Elizabeth Sabrinsky
This book is intended to assist group leaders, teachers, counselors, and peer helpers in the development of relationships and active learning. The first chapter, "Icebreakers," begins with an overview that explains the nature, purpose, and importance of these activities. Icebreakers are used to help group members learn about each other in a…
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Ice-Breaking as a Useful Teaching Policy for Both Genders
ERIC Educational Resources Information Center
Yeganehpour, Parisa
2017-01-01
These days focus of interest in English learning changes to productive skills, in Turkey. This research study assesses the teachers' point of view about using ice-breakers for adult Turkish EFL learners in upper-intermediate level. It also anticipates finding valuable information with applying ice-breaker activities as a useful teaching policy…
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Kulikov, Konstantin N.; Nizamutdinov, Rinat A.; Abramov, Andrey N.
From 1959 up to 1991 nine civil nuclear powered ships were built in Russia: eight ice-breakers and one lash lighter carrier (cargo ship). At the present time three of them were taking out of service: ice-breaker 'Lenin' is decommissioned as a museum and is set for storage in the port of Murmansk, nuclear ice-breakers 'Arktika' and 'Sibir' are berthing. The ice-breakers carrying rad-wastes appear to be a possible source of radiation contamination of Murmansk region and Kola Bay because the ship long-term storage afloat has the negative effect on hull's structures. As the result of this under the auspices ofmore » the Federal Targeted Program 'Nuclear and Radiation Safety of Russia for 2008 and the period until 2015' the conception and projects of decommissioning of nuclear-powered ships are developed by the State corporation Rosatom with the involvement of companies of United Shipbuilding Corporation. In developing the principal provisions of conception of decommissioning and dismantling of icebreakers the technical and economic assessment of dismantling options in ship-repairing enterprises of North-West of Russia was performed. The paper contains description of options, research procedure, analysis of options of decommissioning and dismantling of nuclear ice-breakers, taking into account the principle of optimization of potential radioactive effect to personnel, human population and environment. The report's conclusions contain the recommendations for selection of option for development of nuclear icebreaker decommissioning and dismantling projects. (authors)« less
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Reaching 1 m deep on Mars: the Icebreaker drill.
Zacny, K; Paulsen, G; McKay, C P; Glass, B; Davé, A; Davila, A F; Marinova, M; Mellerowicz, B; Heldmann, J; Stoker, C; Cabrol, N; Hedlund, M; Craft, J
2013-12-01
The future exploration of Mars will require access to the subsurface, along with acquisition of samples for scientific analysis and ground-truthing of water ice and mineral reserves for in situ resource utilization. The Icebreaker drill is an integral part of the Icebreaker mission concept to search for life in ice-rich regions on Mars. Since the mission targets Mars Special Regions as defined by the Committee on Space Research (COSPAR), the drill has to meet the appropriate cleanliness standards as requested by NASA's Planetary Protection Office. In addition, the Icebreaker mission carries life-detection instruments; and in turn, the drill and sample delivery system have to meet stringent contamination requirements to prevent false positives. This paper reports on the development and testing of the Icebreaker drill, a 1 m class rotary-percussive drill and triple redundant sample delivery system. The drill acquires subsurface samples in short, approximately 10 cm bites, which makes the sampling system robust and prevents thawing and phase changes in the target materials. Autonomous drilling, sample acquisition, and sample transfer have been successfully demonstrated in Mars analog environments in the Arctic and the Antarctic Dry Valleys, as well as in a Mars environmental chamber. In all environments, the drill has been shown to perform at the "1-1-100-100" level; that is, it drilled to 1 m depth in approximately 1 hour with less than 100 N weight on bit and approximately 100 W of power. The drilled substrate varied and included pure ice, ice-rich regolith with and without rocks and with and without 2% perchlorate, and whole rocks. The drill is currently at a Technology Readiness Level (TRL) of 5. The next-generation Icebreaker drill weighs 10 kg, which is representative of the flightlike model at TRL 5/6.
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Coast Guard Polar Icebreaker Modernization: Background and Issues for Congress
2014-02-11
Efforts to Identify Arctic Requirements Are Ongoing, but More Communication about Agency Planning Efforts Would Be Beneficial, GAO-10- 870, September...icebreakers also have substantial command, control, and communications capabilities. The flexibility and mobility of polar icebreakers would assist...Fisheries enforcement in Bering Sea to prevent foreign fishing in U.S. waters and overfishing —Capability to conduct search and rescue in Beaufort Sea
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Coast Guard Polar Icebreaker Modernization: Background and Issues for Congress
2013-07-24
but More Communication about Agency Planning Efforts Would Be Beneficial, GAO-10- 870, September 2010, p. 53. Coast Guard Polar Icebreaker...and helicopters. Polar icebreakers also have substantial command, control, and communications capabilities. The flexibility and mobility of polar...Coast Guard —Fisheries enforcement in Bering Sea to prevent foreign fishing in U.S. waters and overfishing —Capability to conduct search and rescue in
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Building Community in the Classroom through Ice-Breakers and Parting Ways
ERIC Educational Resources Information Center
Eggleston, Tami; Smith, Gabie
2004-01-01
Many instructors are concerned with creating a community in the classroom. Although there are numerous published "ice-breakers," many of these techniques are not specific to psychology courses or have been used so much that the students see them as redundant and cliche. Icebreakers are better if they have relevance to a specific class, are…
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Coast Guard Polar Icebreaker Modernization: Background and Issues for Congress
2016-11-10
time between the end of Polar Star’s current intended service life and the entry into service of one or more new heavy polar icebreakers. There are...at least two options for bridging this time period: One would be to further extend the service life of Polar Star and/or repair and extend the...service life of Polar Sea. The other would be to charter (i.e., lease) one or more other icebreakers (perhaps foreign- owned ones), if such ships are
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Open-Water Resistance and Seakeeping Characteristics of Ships with Icebreaking Bows
1991-05-13
of a Knuckled Forefoot on a Typical Icebreaker ...... ................... . 19 3-2. Lines Plan, T-AGS OCEAN (ICE) . * * .... . 23 3-3. Curve of...the ice. As the stem strikes the ice, initial failure of the ice occurs by simple crushing. Then the raked stem of the icebreaker rides up onto the ice...bossings, skegs, rudders, 18 and special stem forefoot shapes were not included in the shapes tested. To ensure that the parent and its variants
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Designing a Maintainable and Sustainable Coast Guard Icebreaker for Arctic and Antarctic Operations
2014-03-21
03-2014 Technical June 2013-August 2013 Designing a Maintainable and Sustainable Coast Guard Icebreaker for Arctic and Antarctic Operations...of Engineering Designing a Maintainable and Sustainable Coast Guard Icebreaker for Arctic and Antarctic Operations Abstract The U.S. Coast Guard is...Pollution (MARPOL) of which Annex V prohibits the discharge of solid waste other than food refuge less than 25mm in diameter into the Antarctic Region [6
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Using Appreciative Intelligence for Ice-Breaking: A New Design
ERIC Educational Resources Information Center
Verma, Neena; Pathak, Anil Anand
2011-01-01
Purpose: The purpose of this paper is to highlight the importance of applying appreciative intelligence and appreciative inquiry concepts to design a possibly new model of ice-breaking, which is strengths-based and very often used in any training in general and team building training in particular. Design/methodology/approach: The design has…
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The Icebreaker Mission to Search for Life on Mars
NASA Technical Reports Server (NTRS)
Stoker, C.; Mckay, C.; Brinckerhoff, W.; Davila, A.; Parro, V.; Quinn, R.
2015-01-01
The search for evidence of life on Mars is the ultimate motivation for its scientific exploration. The results from the Phoenix mission indicate that the high N. latitude ice-rich regolith at low elevations is likely to be a recently habitable place on Mars [Stoker et al., 2010]. The near-surface ice likely provided adequate water activity during periods of high obliquity, 3 to 10 Myr ago. Carbon dioxide and nitrogen are present in the atmosphere, and nitrates may be present in the soil. Together with iron in basaltic rocks and perchlorate in the soil they provide carbon and energy sources, and oxidative power to drive metabolism. Furthermore, the presence of organics is possible, as thermally reactive perchlorate would have prevented their detection by Viking and Phoenix. The Mars Icebreaker Life mission [McKay et al., 2013] focuses on the following science goals: (1) Search for biomolecular evidence of life; (2) Search for organic matter from either exogeneous or endogeneous sources using methods that are not effected by the presence of perchlorate; (3) Characterize oxidative species that produced reactivity of soils seen by Viking; and 4) Assess the habitability of the ice bearing soils. The Icebreaker Life payload (Figure 1) includes a 1-m rotary percussive drill that brings cuttings samples to the surface where they are delivered to three instruments (Fig. 1), the Signs of Life Detector (SOLID) [Parro et al., 2011] for biomolecular analysis, Laser Desorption Mass Spectrometer (LDMS) [??? 2015]) for broad spectrum organic analysis, and Wet Chemistry Laboratory (WCL) [Hecht et al., 2009] for detecting soluble species of nutrients and reactive oxidants. The Icebreaker payload fits on the Phoenix spacecraft and can land at the well-characterized Phoe-nix landing site in 2020 in a Discovery-class mission.
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Kick-Start Your Class: Academic Icebreakers to Engage Students
ERIC Educational Resources Information Center
Johnson, LouAnne
2012-01-01
LouAnne Johnson's newest book is a collection of fun and simple educational icebreaker activities that get students excited and engaged from the very first minute of class. These activities are great to use with students at all levels, and many of the activities include variations and modifications for different groups. Research has shown that the…
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Coast Guard Polar Icebreaker Modernization: Background and Issues for Congress
2013-04-25
Accountability Office, Coast Guard[:]Efforts to Identify Arctic Requirements Are Ongoing, but More Communication about Agency Planning Efforts Would...control, and communications capabilities. The flexibility and mobility of polar icebreakers would assist the Coast Guard in closing future mission...Sea to prevent foreign fishing in U.S. waters and overfishing —Capability to conduct search and rescue in Beaufort Sea for cruise line and natural
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The Icebreaker Life Mission to Mars: A Search for Biomolecular Evidence for Life
NASA Technical Reports Server (NTRS)
Mckay, Christopher P.; Stoker, Carol R.; Glass, Brian J.; Dave, Arwen I.; Davila, Alfonso F.; Heldmann, Jennifer L.; Marinova, Margarita M.; Fairen, Alberto G; Quinn, Richard C; Zacny, Kris A.;
2012-01-01
The search for evidence of life on Mars is the primary motivation for the exploration of that planet. The results from previous missions, and the Phoenix mission in particular, indicate that the ice-cemented ground in the north polar plains is likely to be the most recently habitable place that is currently known on Mars. The near-surface ice likely provided adequate water activity during periods of high obliquity, 5 Myr ago. Carbon dioxide and nitrogen is present in the atmosphere, and nitrates may be present in the soil. Perchlorate in the soil together with iron in basaltic rock provides a possible energy source for life. Furthermore, the presence of organics must once again be considered, as the results of the Viking GCMS are now suspect given the discovery of the thermally reactive perchlorate. Ground-ice may provide a way to preserve organic molecules for extended periods of time, especially organic biomarkers. The Mars Icebreaker Life mission focuses on the following science goals: 1. Search for specific biomolecules that would be conclusive evidence of life. 2. A general search for organic molecules in the ground ice. 3. Determine the processes of ground ice formation and the role of liquid water. 4. Understand the mechanical properties of the Mars polar ice-cemented soil. 5. Assess the recent habitability of the environment with respect to required elements to support life, energy sources, and possible toxic elements. And 6. Compare the elemental composition of the northern plains with mid-latitude sites. The Icebreaker Life payload has been designed around the Phoenix spacecraft and is targeted to a site near the Phoenix landing site. However, the Icebreaker payload could be supported on other Mars landing systems. Preliminary studies of the SpaceX Dragon lander show that it could support the Icebreaker payload for a landing either at the Phoenix site or at mid-latitudes. Duplicate samples could be cached as a target for possible return by a Mars Sample
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The Icebreaker Life Mission to Mars: a search for biomolecular evidence for life.
McKay, Christopher P; Stoker, Carol R; Glass, Brian J; Davé, Arwen I; Davila, Alfonso F; Heldmann, Jennifer L; Marinova, Margarita M; Fairen, Alberto G; Quinn, Richard C; Zacny, Kris A; Paulsen, Gale; Smith, Peter H; Parro, Victor; Andersen, Dale T; Hecht, Michael H; Lacelle, Denis; Pollard, Wayne H
2013-04-01
The search for evidence of life on Mars is the primary motivation for the exploration of that planet. The results from previous missions, and the Phoenix mission in particular, indicate that the ice-cemented ground in the north polar plains is likely to be the most recently habitable place that is currently known on Mars. The near-surface ice likely provided adequate water activity during periods of high obliquity, ≈ 5 Myr ago. Carbon dioxide and nitrogen are present in the atmosphere, and nitrates may be present in the soil. Perchlorate in the soil together with iron in basaltic rock provides a possible energy source for life. Furthermore, the presence of organics must once again be considered, as the results of the Viking GCMS are now suspect given the discovery of the thermally reactive perchlorate. Ground ice may provide a way to preserve organic molecules for extended periods of time, especially organic biomarkers. The Mars Icebreaker Life mission focuses on the following science goals: (1) Search for specific biomolecules that would be conclusive evidence of life. (2) Perform a general search for organic molecules in the ground ice. (3) Determine the processes of ground ice formation and the role of liquid water. (4) Understand the mechanical properties of the martian polar ice-cemented soil. (5) Assess the recent habitability of the environment with respect to required elements to support life, energy sources, and possible toxic elements. (6) Compare the elemental composition of the northern plains with midlatitude sites. The Icebreaker Life payload has been designed around the Phoenix spacecraft and is targeted to a site near the Phoenix landing site. However, the Icebreaker payload could be supported on other Mars landing systems. Preliminary studies of the SpaceX Dragon lander show that it could support the Icebreaker payload for a landing either at the Phoenix site or at midlatitudes. Duplicate samples could be cached as a target for possible return by
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AURORA BOREALIS - Development of a New Research Icebreaker with Drilling Capability
NASA Astrophysics Data System (ADS)
Thiede, J.; Biebow, N.; Egerton, P.; Kunz-Pirrung, M.; Lembke-Jene, L.
2007-12-01
Polar research both on land and in the sea cannot achieve the needed progress without novel and state of the art technologies and infrastructure. In addition, we have the obligation to equip the upcoming young and courageous generation of polar researchers with the most modern and safest research platforms the 21st century can provide. This effort will require major investments, both in terms of generating new tools, as well as maintaining and renovating existing infrastructure. There are many different novel tools under development for polar research, we will concentrate on the presently largest one, the planning for a new type of research icebreaker, the AURORA BOREALIS with an all-season capability of operations in permanently ice-covered waters and with the possibility to carry out deep-sea drilling in ice-covered deep-sea basins. AURORA BOREALIS will be the most advanced Polar Research Vessel in the world with a multi-functional role of drilling in deep ocean basins and supporting climate and environmental research and decision support for stakeholder governments for the next 35 to 40 years. The vessel is planned as a large research icebreaker with 44,000 tons displacement and a length of up to 196 m, with about 50 Megawatt propulsion power. Advanced technological features will include azimuth propulsion systems, extensive instrumental and airborne ice- management support, and the routine operation of Remotely Operated Vehicles (ROV) and Autonomous Underwater Vehicles (AUVs) from two moon-pools. An unique feature of this icebreaker will be the drilling rig that will enable sampling of the ocean floor and sub-sea down to 5000 m water depth and 1000 m penetration at the most inhospitable places on earth. The possibility to flexibly equip the ship with laboratory and supply containers, and the variable arrangement of other modular infrastructure (in particular, winches, cranes, etc.), free deck- space, and separate protected deck areas, will allow the planned
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Zones of impact around icebreakers affecting beluga whales in the Beaufort Sea.
Erbe, C; Farmer, D M
2000-09-01
A software model estimating zones of impact on marine mammals around man-made noise [C. Erbe and D. M. Farmer, J. Acoust. Soc. Am. 108, 1327-1331 (2000)] is applied to the case of icebreakers affecting beluga whales in the Beaufort Sea. Two types of noise emitted by the Canadian Coast Guard icebreaker Henry Larsen are analyzed: bubbler system noise and propeller cavitation noise. Effects on beluga whales are modeled both in a deep-water environment and a near-shore environment. The model estimates that the Henry Larsen is audible to beluga whales over ranges of 35-78 km, depending on location. The zone of behavioral disturbance is only slightly smaller. Masking of beluga communication signals is predicted within 14-71-km range. Temporary hearing damage can occur if a beluga stays within 1-4 km of the Henry Larsen for at least 20 min. Bubbler noise impacts over the short ranges quoted; propeller cavitation noise accounts for all the long-range effects. Serious problems can arise in heavily industrialized areas where animals are exposed to ongoing noise and where anthropogenic noise from a variety of sources adds up.
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AURORA BOREALIS - European Research Icebreaker With Drilling Capability
NASA Astrophysics Data System (ADS)
Biebow, N.; Lembke-Jene, L.; Kunz-Pirrung, M.; Thiede, J.
2008-12-01
The polar oceans are the least known areas of the globe, in although they hold the key to many of our climate´s secrets. How does the sea ice coverage and the sea water properties change? How do plants and animals survive under the most extreme conditions of the earth? Which information of past climate change can be read from the sediments at the sea-floor and how can the future changing climate be predicted? In order to answer such and further questions, for the moment a hypermodern research vessel, the AURORA BOREALIS, is planned, which can handle the cool summers and freezing winters of the polar oceans and which can drill deep into the sea floor. AURORA BOREALIS will be the most advanced Research Icebreaker in the world with a multi-functional role of drilling in deep ocean basins and supporting climate/environmental research and decision support for stakeholder governments for the next 35-40 years. It will have a high icebreaking capacity to penetrate autonomously (single ship operation) into the central Arctic Ocean with more than 2.5 meters of ice cover, during all seasons of the year. The new technological features will include dynamic positioning in closed sea- ice cover, satellite navigation and ice-management support and the deployment and operation of Remotely Operated Vehicles (ROV) and Autonomous Underwater Vehicles (AUVs) from the twin moon-pools. A unique feature of the vessel is the deep-sea drilling rig, which will enable sampling of the ocean floor and sub-sea up to 5000 m water and 1000 m penetration at the most inhospitable places on earth. The drilling capability will be deployed in both Polar Regions on the long run and AURORA BOREALIS will be the only vessel worldwide that could undertake this type of scientific investigation.
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The sample handling system for the Mars Icebreaker Life mission: from dirt to data.
Davé, Arwen; Thompson, Sarah J; McKay, Christopher P; Stoker, Carol R; Zacny, Kris; Paulsen, Gale; Mellerowicz, Bolek; Glass, Brian J; Willson, David; Bonaccorsi, Rosalba; Rask, Jon
2013-04-01
The Mars Icebreaker Life mission will search for subsurface life on Mars. It consists of three payload elements: a drill to retrieve soil samples from approximately 1 m below the surface, a robotic sample handling system to deliver the sample from the drill to the instruments, and the instruments themselves. This paper will discuss the robotic sample handling system. Collecting samples from ice-rich soils on Mars in search of life presents two challenges: protection of that icy soil--considered a "special region" with respect to planetary protection--from contamination from Earth, and delivery of the icy, sticky soil to spacecraft instruments. We present a sampling device that meets these challenges. We built a prototype system and tested it at martian pressure, drilling into ice-cemented soil, collecting cuttings, and transferring them to the inlet port of the SOLID2 life-detection instrument. The tests successfully demonstrated that the Icebreaker drill, sample handling system, and life-detection instrument can collectively operate in these conditions and produce science data that can be delivered via telemetry--from dirt to data. Our results also demonstrate the feasibility of using an air gap to prevent forward contamination. We define a set of six analog soils for testing over a range of soil cohesion, from loose sand to basalt soil, with angles of repose of 27° and 39°, respectively. Particle size is a key determinant of jamming of mechanical parts by soil particles. Jamming occurs when the clearance between moving parts is equal in size to the most common particle size or equal to three of these particles together. Three particles acting together tend to form bridges and lead to clogging. Our experiments show that rotary-hammer action of the Icebreaker drill influences the particle size, typically reducing particle size by ≈ 100 μm.
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The Sample Handling System for the Mars Icebreaker Life Mission: from Dirt to Data
NASA Technical Reports Server (NTRS)
Dave, Arwen; Thompson, Sarah J.; McKay, Christopher P.; Stoker, Carol R.; Zacny, Kris; Paulsen, Gale; Mellerowicz, Bolek; Glass, Brian J.; Wilson, David; Bonaccorsi, Rosalba;
2013-01-01
The Mars icebreaker life mission will search for subsurface life on mars. It consists of three payload elements: a drill to retrieve soil samples from approx. 1 meter below the surface, a robotic sample handling system to deliver the sample from the drill to the instruments, and the instruments themselves. This paper will discuss the robotic sample handling system.
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Computer Simulation of Great Lakes-St. Lawrence Seaway Icebreaker Requirements.
1980-01-01
of Run No. 1 for Taconite Task Command ... ....... 6-41 6.22d Results of Run No. I for Oil Can Task Command ........ ... 6-42 6.22e Results of Run No...Port and Period for Run No. 2 ... .. ... ... 6-47 6.23c Results of Run No. 2 for Taconite Task Command ... ....... 6-48 6.23d Results of Run No. 2 for...6-53 6.24b Predicted Icebreaker Fleet by Home Port and Period for Run No. 3 6-54 6.24c Results of Run No. 3 for Taconite Task Command. ....... 6
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Drilling Polar Oceans with the European Research Icebreaker AURORA BOREALIS: the IODP Context
NASA Astrophysics Data System (ADS)
Lembke-Jene, Lester; Wolff-Boenisch, Bonnie; Azzolini, Roberto; Thiede, Joern; Biebow, Nicole; Eldholm, Olav; Egerton, Paul
2010-05-01
Polar oceans are characterized by extreme environmental conditions for humans and materials, and have remained the least accessible regions to scientists of the IODP. DSDP and ODP have for long faced specific technical and logistical problems when attempting to drill in ice-covered polar deep-sea basins. The Arctic Ocean and large areas of the high-latitude Southern Ocean remained largely un-sampled by ODP and remain one of the major scientific and technological challenges for IODP. Drilling in these regions has been discussed and anticipated for decades and the scientific rationales are reflected in the science plans of the international Nansen Arctic Drilling Program (NAD) or the Arctic Program Planning Group (APPG) of ODP/IODP, amongst others. More recently, the rationale to investigate the polar oceans in a holistic approach has been outlined by workshops, leading to strategic assessments of the scientific potential and new drilling proposals. The European Polar Board took the initiative to develop a plan for a novel and dedicated research icebreaker with technical capabilities hitherto unrealised. This research icebreaker will enable autonomous operations in the central Arctic Ocean and the Southern Ocean, even during the severest ice conditions in the deep winter, serving all marine disciplines of polar research including scientific drilling: The European Research Icebreaker and Deep-Sea Drilling Vessel AURORA BOREALIS. AURORA BOREALIS is presently planned as a multi-purpose vessel. The ship can be deployed as a research icebreaker in all polar waters during any season of the year, as it shall meet the specifications of the highest ice-class attainable (IACS Polar Code 1) for icebreakers. During the times when it is not employed for drilling, it will operate as the most technically advanced multi-disciplinary research vessel in the Arctic or polar Southern Ocean. AURORA BOREALIS will be a "European scientific flagship facility" (fully open to non
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Collecting winter data on U.S. Coast Guard icebreakers
NASA Astrophysics Data System (ADS)
Oyserman, Ben O.; Woityra, William C.; Bullerjahn, George S.; Beall, Benjamin F. N.; McKay, Robert Michael L.
2012-03-01
Winter research and monitoring of icebound rivers, lakes, and coastal seas to date has usually involved seagoing civilian scientists leading survey efforts. However, because of poor weather conditions and a lack of safe research platforms, scientists collecting data during winter face some difficult and often insurmountable problems. To solve these problems and to further research and environmental monitoring goals, new partnerships can be formed through integrating efforts of the U.S. Coast Guard (USCG) with citizen science initiatives. USCG and a research group at Ohio's Bowling Green State University are entering the third year of such a partnership, in which icebreaking operations in Lake Erie using USCG Cutter Neah Bay support volunteer data collection. With two additional USCG vessels joining the program this winter season, the partnership serves as a timely and useful model for worldwide environmental research and monitoring through citizen science and government collaboration.
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Icebreaker-3 Drill Integration and Testing at Two Mars-Analog Sites
NASA Technical Reports Server (NTRS)
Glass, B.; Bergman, D.; Yaggi, B.; Dave, A.; Zacny, K.
2016-01-01
A decade of evolutionary development of integrated automated drilling and sample handling at analog sites and in test chambers has made it possible to go 1 meter through hard rocks and ice layers on Mars. The latest Icebreaker-3 drill has been field tested in 2014 at the Haughton Crater Marsanalog site in the Arctic and in 2015 with a Mars lander mockup in Rio Tinto, Spain, (with sample transfer arm and with a prototype life-detection instrument). Tests in Rio Tinto in 2015 successfully demonstrated that the drill sample (cuttings) was handed-off from the drill to the sample transfer arm and thence to the on-deck instrument inlet where it was taken in and analyzed ("dirt-to-data").
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Masked hearing thresholds of a beluga whale ( Delphinapterus leucas) in icebreaker noise
NASA Astrophysics Data System (ADS)
Erbe, C.; Farmer, D. M.
An experiment is presented that measured masked hearing thresholds of a beluga whale at the Vancouver Aquarium. The masked signal was a typical beluga vocalization; the masking noise included two types of icebreaker noise and naturally occurring icecracking noise. Thresholds were measured behaviorally in a go/no-go paradigm. Results were that bubbler system noise exhibited the strongest masking effect with a critical noise-to-signal ratio of 15.4 dB. Propeller cavitation noise completely masked the vocalization for noise-to-signal ratios greater than 18.0 dB. Natural icecracking noise showed the least interference with a threshold at 29.0 dB. A psychophysical analysis indicated that the whale did not have a consistent decision bias.
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NASA Astrophysics Data System (ADS)
Yu, Lisan; Jin, Xiangze; Schulz, Eric W.; Josey, Simon A.
2017-08-01
This study analyzed shipboard air-sea measurements acquired by the icebreaker Aurora Australis during its off-winter operation in December 2010 to May 2012. Mean conditions over 7 months (October-April) were compiled from a total of 22 ship tracks. The icebreaker traversed the water between Hobart, Tasmania, and the Antarctic continent, providing valuable in situ insight into two dynamically important, yet poorly sampled, regimes: the sub-Antarctic Southern Ocean and the Antarctic marginal ice zone (MIZ) in the Indian Ocean sector. The transition from the open water to the ice-covered surface creates sharp changes in albedo, surface roughness, and air temperature, leading to consequential effects on air-sea variables and fluxes. Major effort was made to estimate the air-sea fluxes in the MIZ using the bulk flux algorithms that are tuned specifically for the sea-ice effects, while computing the fluxes over the sub-Antarctic section using the COARE3.0 algorithm. The study evidenced strong sea-ice modulations on winds, with the southerly airflow showing deceleration (convergence) in the MIZ and acceleration (divergence) when moving away from the MIZ. Marked seasonal variations in heat exchanges between the atmosphere and the ice margin were noted. The monotonic increase in turbulent latent and sensible heat fluxes after summer turned the MIZ quickly into a heat loss regime, while at the same time the sub-Antarctic surface water continued to receive heat from the atmosphere. The drastic increase in turbulent heat loss in the MIZ contrasted sharply to the nonsignificant and seasonally invariant turbulent heat loss over the sub-Antarctic open water.
Plain Language SummaryThe <span class="hlt">icebreaker</span> Aurora Australis is a research and supply vessel that is regularly chartered by the Australian Antarctic Division during the southern summer to operate in waters between Hobart, Tasmania, and Antarctica. The vessel serves as the main lifeline to</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/26587241','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/26587241"><span>The <span class="hlt">ice-breaker</span> effect: singing mediates fast social bonding.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Pearce, Eiluned; Launay, Jacques; Dunbar, Robin I M</p> <p>2015-10-01</p> <p>It has been proposed that singing evolved to facilitate social cohesion. However, it remains unclear whether bonding arises out of properties intrinsic to singing or whether any social engagement can have a similar effect. Furthermore, previous research has used one-off singing sessions without exploring the emergence of social bonding over time. In this semi-naturalistic study, we followed newly formed singing and non-singing (crafts or creative writing) adult education classes over seven months. Participants rated their closeness to their group and their affect, and were given a proxy measure of endorphin release, before and after their class, at three timepoints (months 1, 3 and 7). We show that although singers and non-singers felt equally connected by timepoint 3, singers experienced much faster bonding: singers demonstrated a significantly greater increase in closeness at timepoint 1, but the more gradual increase shown by non-singers caught up over time. This represents the first evidence for an '<span class="hlt">ice-breaker</span> effect' of singing in promoting fast cohesion between unfamiliar individuals, which bypasses the need for personal knowledge of group members gained through prolonged interaction. We argue that singing may have evolved to quickly bond large human groups of relative strangers, potentially through encouraging willingness to coordinate by enhancing positive affect.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2014EGUGA..1616323A','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2014EGUGA..1616323A"><span>Arctic summer school onboard an <span class="hlt">icebreaker</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Alexeev, Vladimir A.; Repina, Irina A.</p> <p>2014-05-01</p> <p>The International Arctic Research Center (IARC) of the University of Alaska Fairbanks conducted a summer school for PhD students, post-docs and early career scientists in August-September 2013, jointly with an arctic expedition as a part of NABOS project (Nansen and Amundsen Basin Observational System) onboard the Russian research vessel "Akademik Fedorov". Both the summer school and NABOS expedition were funded by the National Science Foundation. The one-month long summer school brought together graduate students and young scientists with specialists in arctic oceanography and climate to convey to a new generation of scientists the opportunities and challenges of arctic climate observations and modeling. Young scientists gained hands-on experience during the field campaign and learned about key issues in arctic climate from observational, diagnostic, and modeling perspectives. The summer school consisted of background lectures, participation in fieldwork and mini-projects. The mini-projects were performed in collaboration with summer school instructors and members of the expedition. Key topics covered in the lectures included: - arctic climate: key characteristics and processes; - physical processes in the Arctic Ocean; - sea ice and the Arctic Ocean; - trace gases, aerosols, and chemistry: importance for climate changes; - feedbacks in the arctic system (e.g., surface albedo, clouds, water vapor, circulation); - arctic climate variations: past, ongoing, and projected; - global climate models: an overview. An outreach specialist from the Miami Science Museum was writing a blog from the <span class="hlt">icebreaker</span> with some very impressive statistics (results as of January 1, 2014): Total number of blog posts: 176 Blog posts written/contributed by scientists: 42 Blog views: 22,684 Comments: 1,215 Number of countries who viewed the blog: 89 (on 6 continents) The 33-day long NABOS expedition started on August 22, 2013 from Kirkenes, Norway. The vessel ("Akademik Fedorov") returned to</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2011AGUFM.C41D0444B','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2011AGUFM.C41D0444B"><span>Future Marine Polar Research Capacities - Science Planning and Research Services for a Multi-National Research <span class="hlt">Icebreaker</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Biebow, N.; Lembke-Jene, L.; Wolff-Boenisch, B.; Bergamasco, A.; De Santis, L.; Eldholm, O.; Mevel, C.; Willmott, V.; Thiede, J.</p> <p>2011-12-01</p> <p>Despite significant advances in Arctic and Antarctic marine science over the past years, the polar Southern Ocean remains a formidable frontier due to challenging technical and operational requirements. Thus, key data and observations from this important region are still missing or lack adequate lateral and temporal coverage, especially from time slots outside optimal weather seasons and ice conditions. These barriers combined with the obligation to efficiently use financial resources and funding for expeditions call for new approaches to create optimally equipped, but cost-effective infrastructures. These must serve the international science community in a dedicated long-term mode and enable participation in multi-disciplinary expeditions, with secured access to optimally equipped marine platforms for world-class research in a wide range of Antarctic science topics. The high operational and technical performance capacity of a future joint European Research <span class="hlt">Icebreaker</span> and Deep-sea Drilling Vessel (the AURORA BOREALIS concept) aims at integrating still separately operating national science programmes with different strategic priorities into joint development of long-term research missions with international cooperation both in Arctic and Antarctica. The <span class="hlt">icebreaker</span> is planned to enable, as a worldwide first, autonomous year-round operations in the central Arctic and polar Southern Ocean, including severest ice conditions in winter, and serving all polar marine disciplines. It will facilitate the implementation of atmospheric, oceanographic, cryospheric or geophysical observatories for long-term monitoring of the polar environment. Access to the biosphere and hydrosphere e.g. beneath ice shelves or in remote regions is made possible by acting as advanced deployment platform for instruments, robotic and autonomous vehicles and ship-based air operations. In addition to a report on the long-term strategic science and operational planning objectives, we describe foreseen</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2016ACP....16.7899A','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2016ACP....16.7899A"><span>Ship emissions measurement in the Arctic by plume intercepts of the Canadian Coast Guard <span class="hlt">icebreaker</span> Amundsen from the Polar 6 aircraft platform</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Aliabadi, Amir A.; Thomas, Jennie L.; Herber, Andreas B.; Staebler, Ralf M.; Leaitch, W. Richard; Schulz, Hannes; Law, Kathy S.; Marelle, Louis; Burkart, Julia; Willis, Megan D.; Bozem, Heiko; Hoor, Peter M.; Köllner, Franziska; Schneider, Johannes; Levasseur, Maurice; Abbatt, Jonathan P. D.</p> <p>2016-06-01</p> <p>Decreasing sea ice and increasing marine navigability in northern latitudes have changed Arctic ship traffic patterns in recent years and are predicted to increase annual ship traffic in the Arctic in the future. Development of effective regulations to manage environmental impacts of shipping requires an understanding of ship emissions and atmospheric processing in the Arctic environment. As part of the summer 2014 NETCARE (Network on Climate and Aerosols) campaign, the plume dispersion and gas and particle emission factors of effluents originating from the Canadian Coast Guard <span class="hlt">icebreaker</span> Amundsen operating near Resolute Bay, NU, Canada, were investigated. The Amundsen burned distillate fuel with 1.5 wt % sulfur. Emissions were studied via plume intercepts using the Polar 6 aircraft measurements, an analytical plume dispersion model, and using the FLEXPART-WRF Lagrangian particle dispersion model. The first plume intercept by the research aircraft was carried out on 19 July 2014 during the operation of the Amundsen in the open water. The second and third plume intercepts were carried out on 20 and 21 July 2014 when the Amundsen had reached the ice edge and operated under <span class="hlt">ice-breaking</span> conditions. Typical of Arctic marine navigation, the engine load was low compared to cruising conditions for all of the plume intercepts. The measured species included mixing ratios of CO2, NOx, CO, SO2, particle number concentration (CN), refractory black carbon (rBC), and cloud condensation nuclei (CCN). The results were compared to similar experimental studies in mid-latitudes. Plume expansion rates (γ) were calculated using the analytical model and found to be γ = 0.75 ± 0.81, 0.93 ± 0.37, and 1.19 ± 0.39 for plumes 1, 2, and 3, respectively. These rates were smaller than prior studies conducted at mid-latitudes, likely due to polar boundary layer dynamics, including reduced turbulent mixing compared to mid-latitudes. All emission factors were in agreement with prior</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2012AGUFM.P11E1881M','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2012AGUFM.P11E1881M"><span><span class="hlt">IceBreaker</span>: Mars Drill and Sample Delivery System</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Mellerowicz, B. L.; Paulsen, G. L.; Zacny, K.; McKay, C.; Glass, B. J.; Dave, A.; Davila, A. F.; Marinova, M.</p> <p>2012-12-01</p> <p>We report on the development and testing of a one meter class prototype Mars drill and cuttings sample delivery system. The <span class="hlt">IceBreaker</span> drill consists of a rotary-percussive drill head, a sampling auger with a bit at the end having an integrated temperature sensor, a Z-stage for advancing the auger into the ground, and a sam-pling station for moving the augered ice shavings or soil cuttings into a sample cup. The drill is deployed from a 3 Degree of Freedom (DOF) robotic arm. The drill demonstrated drilling in ice-cemented ground, ice, and rocks at the 1-1-100-100 level; that is the drill reached 1 meter in 1 hour with 100 Watts of power and 100 Newton Weight on Bit. This cor-responds to an average energy of 100 Whr. The drill has been extensively tested in the Mars chamber to a depth of 1 meter, as well as in the Antarctic and the Arctic Mars analog sites. We also tested three sample delivery systems: 1) 4 DOF arm with a custom soil scoop at the end; 2) Pneumatic based, and 3) Drill based enabled by the 3 (DOF) drill deployment boom. In all approaches there is an air-gap between the sterilized drill (which penetrates subsurface) and the sample transfer hardware (which is not going to be sterilized). The air gap satisfies the planetary protection requirements. The scoop acquires cuttings sample once they are augered to the surface, and drops them into an in-strument inlet port. The system has been tested in the Mars chamber and in the Arctic. The pneumatic sample delivery system uses compressed gas to move the sample captured inside a small chamber inte-grated with the auger, directly into the instrument. The system was tested in the Mars chamber. In the third approach the drill auger captures the sample on its flutes, the 3 DOF boom positions the tip of the auger above the instrument, and then the auger discharges the sample into an instrument. This approach was tested in the labolatory (at STP). The above drilling and sample delivery tests have shown that drilling</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/757140','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/757140"><span>Leaching of radionuclides from furfural-based polymers used to solidify <span class="hlt">reactor</span> compartments and components disposed of in the Arctic Kara Sea</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>HEISER,J.H.; SIVINTSEV,Y.; ALEXANDROV,V.P.</p> <p>1999-09-01</p> <p>Within the course of operating its nuclear navy, the former Soviet Union (FSU) disposed of <span class="hlt">reactor</span> vessels and spent nuclear fuel (SNF) in three fjords on the east coast of Novaya Zemlya and in the open Kara Sea within the Novaya Zemlya Trough during the period 1965 to 1988. The dumping consisted of 16 <span class="hlt">reactors</span>, six of which contained SNF and one special container that held ca. 60% of the damaged SNF and the screening assembly from the No. 2 <span class="hlt">reactor</span> of the atomic <span class="hlt">icebreaker</span> Lenin. At the time, the FSU considered dumping of decommissioned nuclear submarines with damaged coresmore » in the bays of and near by the Novaya Zemlya archipelago in the Arctic Kara Sea to be acceptable. To provide an additional level of safety, a group of Russian scientists embarked upon a course of research to develop a solidification agent that would provide an ecologically safe barrier. The barrier material would prevent direct contact of seawater with the SNF and the resultant leaching and release of radionuclides. The solidification agent was to be introduced by flooding the <span class="hlt">reactors</span> vessels and inner cavities. Once introduced the agent would harden and form an impermeable barrier. This report describes the sample preparation of several ``Furfurol'' compositions and their leach testing using cesium 137 as tracer.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/757138','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/757138"><span>Furfural-based polymers for the sealing of <span class="hlt">reactor</span> vessels dumped in the Arctic Kara Sea</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>HEISER,J.H.; COWGILL,M.G.; SIVINTSEV,Y.V.</p> <p>1996-10-07</p> <p>Between 1965 and 1988, 16 naval <span class="hlt">reactor</span> vessels were dumped in the Arctic Kara Sea. Six of the vessels contained spent nuclear fuel that had been damaged during accidents. In addition, a container holding {approximately} 60% of the damaged fuel from the No. 2 <span class="hlt">reactor</span> of the atomic <span class="hlt">icebreaker</span> Lenin was dumped in 1967. Before dumping, the vessels were filled with a solidification agent, Conservant F, in order to prevent direct contact between the seawater and the fuel and other activated components, thereby reducing the potential for release of radionuclides into the environment. The key ingredient in Conservant F ismore » furfural (furfuraldehyde). Other constituents vary, depending on specific property requirements, but include epoxy resin, mineral fillers, and hardening agents. In the liquid state (prior to polymerization) Conservant F is a low viscosity, homogeneous resin blend that provides long work times (6--9 hours). In the cured state, Conservant F provides resistance to water and radiation, has high adhesion properties, and results in minimal gas evolution. This paper discusses the properties of Conservant F in both its cured and uncured states and the potential performance of the waste packages containing spent nuclear fuel in the Arctic Kara Sea.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/1998PhDT........50E','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/1998PhDT........50E"><span>The masking of beluga whale (Delphinapterus leucas) vocalizations by <span class="hlt">icebreaker</span> noise</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Erbe, Christine</p> <p>1998-11-01</p> <p>This thesis examines the masking effect of underwater noise on beluga whale communication. As ocean water is greatly opaque for light but well conducting for sound, marine mammals rely primarily on their hearing for orientation and communication. Man-made underwater noise has the potential of interfering with sounds used by marine mammals. Masking to the point of incomprehensibility can have fatal results-for the individual, but ultimately for the entire species. As part of our understanding of whether marine mammals can cope with human impact on nature, this thesis is the first to study the interference of real ocean noises with complex animal vocalizations. At the Vancouver Aquarium, a beluga whale was trained for acoustic experiments, during which masked hearing thresholds were measured. Focus lay on noise created by <span class="hlt">icebreaking</span> ships in the Arctic. As experiments with trained animals are time and cost expensive, various techniques were examined for their ability to model the whale's response. These were human hearing tests, visual spectrogram discrimination, matched filtering, spectrogram cross-correlation, critical band cross-correlation, adaptive filtering and various types of artificial neural networks. The most efficient method with respect to similarity to the whale's data and speed, was a backpropagation neural net. Masked hearing thresholds would be of little use if they could not be related to accessible quantities in the wild. An ocean sound propagation model was applied to determine critical distances between a noise source, a calling whale and a listening whale. Colour diagrams, called maskograms, were invented to illustrate zones of masking in the wild. Results are that bubbler system noise with a source level of 194 dB re 1 μPa at 1 m has a maximum radius of masking of 15 km in a 3- dimensional ocean. Propeller noise with a source level of 203 dB re 1 μPa at 1 m has a maximum radius of masking of 22 km. A naturally occurring icecracking event</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/29402107','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/29402107"><span>Embracing life-the Bethlehem Schools' Project, an "<span class="hlt">icebreaker</span>" and "a foot in the door".</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Hocking, Mary</p> <p>2018-01-01</p> <p>This workshop details a Partnership involving a High school, a Hospital (Calvary Health Care Bethlehem), La Trobe University and Palliative Care Victoria which seeks to support Community Capacity and resilience in dealing with Life-Limiting illness, death, dying and Loss. This alliance has produced an educational resource which may be used, not only as a tool to normalize death, but also as a means of exploring 'keys to well-being' at any stage of life, through any loss or challenge. This workshop features a template which has been trialled, adapted and evaluated in High School, workshop and Hospital induction settings within Australia. Responses thus far have been "overwhelmingly positive". Translating evidence of positive outcomes into Education & Health Care Systems, is a challenge-this workshop offers a means of approaching both. The conclusion of the workshop provides a number of insights: (I) engaging communities in discussions about well-being and harnessing the insights of youth is a palatable means of discussing well-being at end-of-life; (II) what we know, as a community about supporting people with life-limiting illness is applicable across the span of life-not just at the end; (III) just as it takes a village to raise a child-it takes a village to ensure a quality end-of life experience. What began as a one-off hospital immersion for Secondary School students has grown to become a sustainable educational resource, applicable across a number of domains-with the capacity to become an evidence-based means of increasing community EOL capacity. This workshop details the evolution of a community partnership, which produced an evaluated, sustainable, educational resource encouraging conversations about death and loss whilst emphasizing the essentials of well-being. It is a potential "foot in the door" of the education system and an "<span class="hlt">ice-breaker</span>" for new staff/students to Palliative care.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2013AGUFMSA43A2132K','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2013AGUFMSA43A2132K"><span>Measurement of LF Standard-Frequency Waves JJY along the track of Shirase, the Japanese Antarctic Research <span class="hlt">Icebreaker</span>, during JARE53-JARE54</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Kitauchi, H.; Nozaki, K.; Ito, H.; Tsuchiya, S.; Imamura, K.; Nagatsuma, T.</p> <p>2013-12-01</p> <p>We first obtained a strong evidence of reception of the low frequency (LF) radio waves, 40 kHz and 60 kHz, of the call sign JJY by use of a newly developed, highly sensitive receiving system on board the Japanese Antarctic research <span class="hlt">icebreaker</span> Shirase offshore East Ongul Island, East Antarctica--about 14,000 km away from those transmitting stations in Japan. The measured data sets of the electric field intensity and phase of those signals are to be analysed to examine and/or improve numerical prediction methods of field strength for long-distance propagation of LF radio waves, contributing to the Recommendation 'Prediction of field strength at frequencies below about 150 kHz' made by International Telecommunication Union Radiocommunication Sector (ITU-R). The call sign JJY of standard frequency and time signals (SFTS) of LF 40 kHz and 60 kHz are emitted from the transmitting stations, respectively, Ohtakadoya-yama 37° 22‧ 21″ N, 140° 50‧ 56″ E in Fukushima Prefecture (eastern Japan) and Hagane-yama 33° 27‧ 56″ N, 130° 10‧ 32″ E in Saga/Fukuoka Prefecture (western Japan) by NICT. Those are widely used for calibrating frequency standard oscillators and radio-controlled clocks in Japan. Since low signal attenuation in LF radio band allows long distance communication, kilometre waves have been utilized for operations such as SFTS and military communications around the world. Therefore, there is a need to give guidance to engineers for the planning of radio services in LF band so as to avoid interference. ITU-R recommends the guidance 'Prediction of field strength at frequencies below about 150 kHz', in which a numerical prediction method is proposed to compute the electric field intensity, up to 16,000 km of long-distance propagation, away from the transmitting station. Since reliable data sets are limited for the long-distance propagation, in this study we tried to measure the field strength and phase of the LF SFTS JJY of 40 kHz and 60 kHz over 14</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2015IJNAO...7..708C','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2015IJNAO...7..708C"><span>A prediction method of ice breaking resistance using a multiple regression analysis</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Cho, Seong-Rak; Lee, Sungsu</p> <p>2015-07-01</p> <p>The two most important tasks of <span class="hlt">icebreakers</span> are first to secure a sailing route by breaking the thick sea ice and second to sail efficiently herself for purposes of exploration and transportation in the polar seas. The resistance of <span class="hlt">icebreakers</span> is a priority factor at the preliminary design stage; not only must their sailing efficiency be satisfied, but the design of the propulsion system will be directly affected. Therefore, the performance of <span class="hlt">icebreakers</span> must be accurately calculated and evaluated through the use of model tests in an ice tank before construction starts. In this paper, a new procedure is developed, based on model tests, to estimate a ship's ice breaking resistance during continuous <span class="hlt">ice-breaking</span> in ice. Some of the factors associated with crushing failures are systematically considered in order to correctly estimate her <span class="hlt">ice-breaking</span> resistance. This study is intended to contribute to the improvement of the techniques for ice resistance prediction with ice breaking ships.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_1");'>1</a></li> <li class="active"><span>2</span></li> <li><a href="#" onclick='return showDiv("page_3");'>3</a></li> <li><a href="#" onclick='return showDiv("page_4");'>4</a></li> <li><a href="#" onclick='return showDiv("page_5");'>5</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_2 --> <div id="page_3" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_1");'>1</a></li> <li><a href="#" onclick='return showDiv("page_2");'>2</a></li> <li class="active"><span>3</span></li> <li><a href="#" onclick='return showDiv("page_4");'>4</a></li> <li><a href="#" onclick='return showDiv("page_5");'>5</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="41"> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.dtic.mil/docs/citations/ADA082175','DTIC-ST'); return false;" href="http://www.dtic.mil/docs/citations/ADA082175"><span><span class="hlt">Icebreaking</span> Concepts.</span></a></p> <p><a target="_blank" href="http://www.dtic.mil/">DTIC Science & Technology</a></p> <p></p> <p>1980-01-01</p> <p>Development, Report No 731343 Tests of 102 mm dia milling 160-190 1.1-1.3 Bonz, 1973 cutters 6n floating .ce Tesis of chain saw on floating ice 1430 9.9 tlonz... dia (urcular saws 140 (field) 2 3 Lecourt. I . I W Lewis. I Kotras and I C Roth (1973) Mechan- cutting floating ice 290-32) flab) 20-22 ical ire (utter...8217 3 . NUMBER OF PAGES 21 14. MONITORING AGENCY NAME & ADORESS(II different from Controlling Offlce) 1S. SECURITY CLASS. (of this report) Unclassified</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866315','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866315"><span>Nuclear <span class="hlt">reactor</span> construction with bottom supported <span class="hlt">reactor</span> vessel</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Sharbaugh, John E.</p> <p>1987-01-01</p> <p>An improved liquid metal nuclear <span class="hlt">reactor</span> construction has a <span class="hlt">reactor</span> core and a generally cylindrical <span class="hlt">reactor</span> vessel for holding a large pool of low pressure liquid metal coolant and housing the core within the pool. The <span class="hlt">reactor</span> vessel has an open top end, a closed flat bottom end wall and a continuous cylindrical closed side wall interconnecting the top end and bottom end wall. The <span class="hlt">reactor</span> also has a generally cylindrical concrete containment structure surrounding the <span class="hlt">reactor</span> vessel and being formed by a cylindrical side wall spaced outwardly from the <span class="hlt">reactor</span> vessel side wall and a flat base mat spaced below the <span class="hlt">reactor</span> vessel bottom end wall. A central support pedestal is anchored to the containment structure base mat and extends upwardly therefrom to the <span class="hlt">reactor</span> vessel and upwardly therefrom to the <span class="hlt">reactor</span> core so as to support the bottom end wall of the <span class="hlt">reactor</span> vessel and the lower end of the <span class="hlt">reactor</span> core in spaced apart relationship above the containment structure base mat. Also, an annular reinforced support structure is disposed in the <span class="hlt">reactor</span> vessel on the bottom end wall thereof and extends about the lower end of the core so as to support the periphery thereof. In addition, an annular support ring having a plurality of inward radially extending linear members is disposed between the containment structure base mat and the bottom end of the <span class="hlt">reactor</span> vessel wall and is connected to and supports the <span class="hlt">reactor</span> vessel at its bottom end on the containment structure base mat so as to allow the <span class="hlt">reactor</span> vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event. The <span class="hlt">reactor</span> construction also includes a bed of insulating material in sand-like granular form, preferably being high density magnesium oxide particles, disposed between the containment structure base mat and the bottom end wall of the <span class="hlt">reactor</span> vessel and uniformly supporting the <span class="hlt">reactor</span> vessel at its bottom end wall on the containment</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19760016911','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19760016911"><span>Alternative approaches to fusion. [<span class="hlt">reactor</span> design and <span class="hlt">reactor</span> physics for Tokamak fusion <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Roth, R. J.</p> <p>1976-01-01</p> <p>The limitations of the Tokamak fusion <span class="hlt">reactor</span> concept are discussed and various other fusion <span class="hlt">reactor</span> concepts are considered that employ the containment of thermonuclear plasmas by magnetic fields (i.e., stellarators). Progress made in the containment of plasmas in toroidal devices is reported. <span class="hlt">Reactor</span> design concepts are illustrated. The possibility of using fusion <span class="hlt">reactors</span> as a power source in interplanetary space travel and electric power plants is briefly examined.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://eric.ed.gov/?q=Bayes&pg=5&id=EJ869630','ERIC'); return false;" href="https://eric.ed.gov/?q=Bayes&pg=5&id=EJ869630"><span>Bayes <span class="hlt">Ice-Breaker</span></span></a></p> <p><a target="_blank" href="http://www.eric.ed.gov/ERICWebPortal/search/extended.jsp?_pageLabel=advanced">ERIC Educational Resources Information Center</a></p> <p>Jessop, Alan</p> <p>2010-01-01</p> <p>Showing simply how statistical thinking can help in weighing evidence and reaching decisions can be useful both as an introduction to an extended presentation of statistical theory and as an introduction to a looser discussion of the nature and value of data.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2003EAEJA......143M','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2003EAEJA......143M"><span>Stationary spiraling eddies in presence of polar amplification of global warming as a governing factor of ecology of Greenland seals White Sea population: results of verification study</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Melentyev, K.; Chernook, V.; Melentyev, V.</p> <p>2003-04-01</p> <p>Ice-associated forms of marine mammals are representatives of a high level of fodder chains in the ocean and taxation of population number for different group, as assessment of ecology and animal welfare are the important tasks for marine biology, ecology, fishery and other application uses. Many problems create a global warming and antropogenical impact on marine and coastal ecosystem. In order to investigate ice covered Arctic Ocean and charting the number of seals were performed annual inspections onboard research aircraft PINRO "<span class="hlt">Arktika</span>". Multi-spectral airborne and satellite observations were fulfilled regularly from Barents and White Sea to the Bering and Okhotsk Sea (1996-2002). A contemporary status of different group of sea mammals was evaluated, where number of adults and pups were checked separately. In situ observations were provided with using helicopter and <span class="hlt">icebreaker</span> for gathering a water samples and ice cores (with following biochemical and toxicological analysis). A prevailing part of life cycle of Greenland seals (harp seal) is strongly depended from winter hydrology (water masses, stable currents, meandering fronts, stationary eddies) and closely connected with type of ice (pack, fast ice) and other parameters of ice (age, origin, salinity, ice edge.). First-year ice floes which has a specific properties and distinctive features are used by harp seals for pupping, lactation, molting, pairing and resting. Ringed seals, inversely, use for corresponding purposes only fast-ice. Different aspects of ecology, and migration features of harp seals were analyzed in frame of verification study. It was revealed a scale of influence of winter severity and wind regime, but stationary eddies in the White Sea is most effective governing factor (novelty). Following relationship " eddies - ecology of Greenland seal White Sea population " will be discussed: A) regularities of eddies formation and their spatial arrangement, temporal (seasonal and annual</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4330350','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4330350"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wigner, E.P.</p> <p>1958-04-22</p> <p>A nuclear <span class="hlt">reactor</span> for isotope production is described. This <span class="hlt">reactor</span> is designed to provide a maximum thermal neutron flux in a region adjacent to the periphery of the <span class="hlt">reactor</span> rather than in the center of the <span class="hlt">reactor</span>. The core of the <span class="hlt">reactor</span> is generally centrally located with respect tn a surrounding first reflector, constructed of beryllium. The beryllium reflector is surrounded by a second reflector, constructed of graphite, which, in tune, is surrounded by a conventional thermal shield. Water is circulated through the core and the reflector and functions both as a moderator and a coolant. In order to produce a greatsr maximum thermal neutron flux adjacent to the periphery of the <span class="hlt">reactor</span> rather than in the core, the <span class="hlt">reactor</span> is designed so tbat the ratio of neutron scattering cross section to neutron absorption cross section averaged over all of the materials in the reflector is approximately twice the ratio of neutron scattering cross section to neutron absorption cross section averaged over all of the material of the core of the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866703','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866703"><span>Control of <span class="hlt">reactor</span> coolant flow path during <span class="hlt">reactor</span> decay heat removal</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hunsbedt, Anstein N.</p> <p>1988-01-01</p> <p>An improved <span class="hlt">reactor</span> vessel auxiliary cooling system for a sodium cooled nuclear <span class="hlt">reactor</span> is disclosed. The sodium cooled nuclear <span class="hlt">reactor</span> is of the type having a <span class="hlt">reactor</span> vessel liner separating the <span class="hlt">reactor</span> hot pool on the upstream side of an intermediate heat exchanger and the <span class="hlt">reactor</span> cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the <span class="hlt">reactor</span> vessel liner flow gap which dissipates core heat across the <span class="hlt">reactor</span> vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the <span class="hlt">reactor</span> vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the <span class="hlt">reactor</span> hot pool and then through an intermediate heat exchanger where the heat generated in the <span class="hlt">reactor</span> core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the <span class="hlt">reactor</span> cold pool. The improvement includes placing a jet pump across the <span class="hlt">reactor</span> vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the <span class="hlt">reactor</span> pumps. During normal operation, the jet pumps supplement the normal <span class="hlt">reactor</span> pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the <span class="hlt">reactor</span> vessel hot pool to the <span class="hlt">reactor</span> vessel cold pool. The cooling circuit includes flow into the <span class="hlt">reactor</span> vessel liner flow gap immediate the <span class="hlt">reactor</span> vessel wall and containment vessel where optimum and immediate discharge of residual <span class="hlt">reactor</span> heat occurs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4284313','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4284313"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Fermi, E.; Zinn, W.H.; Anderson, H.L.</p> <p>1958-09-16</p> <p>Means are presenied for increasing the reproduction ratio of a gaphite- moderated neutronic <span class="hlt">reactor</span> by diminishing the neutron loss due to absorption or capture by gaseous impurities within the <span class="hlt">reactor</span>. This means comprised of a fluid-tight casing or envelope completely enclosing the <span class="hlt">reactor</span> and provided with a valve through which the casing, and thereby the <span class="hlt">reactor</span>, may be evacuated of atmospheric air.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://files.eric.ed.gov/fulltext/ED107523.pdf','ERIC'); return false;" href="http://files.eric.ed.gov/fulltext/ED107523.pdf"><span>Nuclear <span class="hlt">Reactors</span>. Revised.</span></a></p> <p><a target="_blank" href="http://www.eric.ed.gov/ERICWebPortal/search/extended.jsp?_pageLabel=advanced">ERIC Educational Resources Information Center</a></p> <p>Hogerton, John F.</p> <p></p> <p>This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. Among the topics discussed are: How <span class="hlt">Reactors</span> Work; <span class="hlt">Reactor</span> Design; Research, Teaching, and Materials Testing; <span class="hlt">Reactors</span> (Research, Teaching and Materials); Production <span class="hlt">Reactors</span>; <span class="hlt">Reactors</span> for Electric Power…</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4182041','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4182041"><span>CONVECTION <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hammond, R.P.; King, L.D.P.</p> <p>1960-03-22</p> <p>An homogeneous nuclear power <span class="hlt">reactor</span> utilizing convection circulation of the liquid fuel is proposed. The <span class="hlt">reactor</span> has an internal heat exchanger looated in the same pressure vessel as the critical assembly, thereby eliminating necessity for handling the hot liquid fuel outside the <span class="hlt">reactor</span> pressure vessel during normal operation. The liquid fuel used in this <span class="hlt">reactor</span> eliminates the necessity for extensive radiolytic gas rocombination apparatus, and the <span class="hlt">reactor</span> is resiliently pressurized and, without any movable mechanical apparatus, automatically regulates itself to the condition of criticality during moderate variations in temperature snd pressure and shuts itself down as the pressure exceeds a predetermined safe operating value.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4785558','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4785558"><span>BOILING <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Untermyer, S.</p> <p>1962-04-10</p> <p>A boiling <span class="hlt">reactor</span> having a reactivity which is reduced by an increase in the volume of vaporized coolant therein is described. In this system unvaporized liquid coolant is extracted from the <span class="hlt">reactor</span>, heat is extracted therefrom, and it is returned to the <span class="hlt">reactor</span> as sub-cooled liquid coolant. This reduces a portion of the coolant which includes vaporized coolant within the core assembly thereby enhancing the power output of the assembly and rendering the <span class="hlt">reactor</span> substantially self-regulating. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2001nrp..book.....S','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2001nrp..book.....S"><span>Nuclear <span class="hlt">Reactor</span> Physics</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Stacey, Weston M.</p> <p>2001-02-01</p> <p>An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear <span class="hlt">reactors</span> now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear <span class="hlt">reactors</span>. Nuclear <span class="hlt">reactor</span> physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear <span class="hlt">reactor</span> physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear <span class="hlt">Reactor</span> Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear <span class="hlt">reactors</span> work, as well as for those who are, or wish to become, specialists in nuclear <span class="hlt">reactor</span> physics and <span class="hlt">reactor</span> physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear <span class="hlt">reactors</span>. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear <span class="hlt">reactors</span>. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear <span class="hlt">Reactor</span> Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear <span class="hlt">reactors</span>, as well as government regulators who wish to increase their understanding of nuclear <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4843232','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4843232"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Treshow, M.</p> <p>1961-09-01</p> <p>A boiling-water nuclear <span class="hlt">reactor</span> is described wherein control is effected by varying the moderator-to-fuel ratio in the <span class="hlt">reactor</span> core. This is accomplished by providing control tubes containing a liquid control moderator in the <span class="hlt">reactor</span> core and providing means for varying the amount of control moderatcr within the control tubes.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.dtic.mil/docs/citations/ADA535964','DTIC-ST'); return false;" href="http://www.dtic.mil/docs/citations/ADA535964"><span>Environmental Activities of the U.S. Coast Guard</span></a></p> <p><a target="_blank" href="http://www.dtic.mil/">DTIC Science & Technology</a></p> <p></p> <p>2010-12-06</p> <p>scientific efforts of other groups. The Coast Guard operates three <span class="hlt">icebreakers</span> in the Arctic and Antarctic , and provides supplies to remote stations...and Atmospheric Administration (NOAA). The Coast Guard operates three <span class="hlt">icebreakers</span> in the Arctic and Antarctic , and provides supplies to remote...stations.17 The Coast Guard also participates in the International Ice Patrol, which monitors iceberg danger in the northwest Atlantic, particularly in the</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.dtic.mil/docs/citations/ADA463776','DTIC-ST'); return false;" href="http://www.dtic.mil/docs/citations/ADA463776"><span>Environmental Activities of the U.S. Coast Guard</span></a></p> <p><a target="_blank" href="http://www.dtic.mil/">DTIC Science & Technology</a></p> <p></p> <p>2007-01-16</p> <p><span class="hlt">icebreakers</span> in the Arctic and Antarctic , and provides supplies to remote stations. These <span class="hlt">icebreakers</span> typically carry about 40 scientists from universities as...the International Ice Patrol, which monitors iceberg danger in the northwest Atlantic, particularly in the area of the Grand Banks of Newfoundland...The iceberg season is usually from February to July, but the Ice Patrol is logistically flexible and can commence operations when iceberg conditions</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.dtic.mil/docs/citations/ADA472753','DTIC-ST'); return false;" href="http://www.dtic.mil/docs/citations/ADA472753"><span>Environmental Activities of the U.S. Coast Guard</span></a></p> <p><a target="_blank" href="http://www.dtic.mil/">DTIC Science & Technology</a></p> <p></p> <p>2007-04-25</p> <p>Guard operates three <span class="hlt">icebreakers</span> in the Arctic and Antarctic , and provides supplies to remote stations. These <span class="hlt">icebreakers</span> typically carry about 40...USCG also participates in the International Ice Patrol, which monitors iceberg danger in the northwest Atlantic, particularly in the area of the Grand...Banks of Newfoundland. The iceberg season is usually from February to July, but the Ice Patrol is logistically flexible and can commence operations</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1361360','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1361360"><span>Proposed Advanced <span class="hlt">Reactor</span> Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (<span class="hlt">Reactor</span>) for Sodium-Cooled Fast <span class="hlt">Reactors</span> and Modular High-Temperature Gas-Cooled <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Belles, Randy; Poore, III, Willis P.; Brown, Nicholas R.</p> <p>2017-03-01</p> <p>This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (<span class="hlt">Reactor</span>) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water <span class="hlt">Reactor</span>] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced <span class="hlt">reactors</span>. This report addresses two technologies: the sodium-cooled fast <span class="hlt">reactor</span> (SFR) and the modular high temperature gas-cooled <span class="hlt">reactor</span> (mHTGR). SRP Chapter 4, which addresses <span class="hlt">reactor</span> components, was selected for adaptation because of the possible significant differences in advanced non-light water <span class="hlt">reactor</span> (non-LWR) technologies compared with the current LWR-basedmore » description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2001AIPC..552..815W','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2001AIPC..552..815W"><span>Coupled <span class="hlt">reactor</span> kinetics and heat transfer model for heat pipe cooled <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Wright, Steven A.; Houts, Michael</p> <p>2001-02-01</p> <p>Heat pipes are often proposed as cooling system components for small fission <span class="hlt">reactors</span>. SAFE-300 and STAR-C are two <span class="hlt">reactor</span> concepts that use heat pipes as an integral part of the cooling system. Heat pipes have been used in <span class="hlt">reactors</span> to cool components within radiation tests (Deverall, 1973); however, no <span class="hlt">reactor</span> has been built or tested that uses heat pipes solely as the primary cooling system. Heat pipe cooled <span class="hlt">reactors</span> will likely require the development of a test <span class="hlt">reactor</span> to determine the main differences in operational behavior from forced cooled <span class="hlt">reactors</span>. The purpose of this paper is to describe the results of a systems code capable of modeling the coupling between the <span class="hlt">reactor</span> kinetics and heat pipe controlled heat transport. Heat transport in heat pipe <span class="hlt">reactors</span> is complex and highly system dependent. Nevertheless, in general terms it relies on heat flowing from the fuel pins through the heat pipe, to the heat exchanger, and then ultimately into the power conversion system and heat sink. A system model is described that is capable of modeling coupled <span class="hlt">reactor</span> kinetics phenomena, heat transfer dynamics within the fuel pins, and the transient behavior of heat pipes (including the melting of the working fluid). This paper focuses primarily on the coupling effects caused by <span class="hlt">reactor</span> feedback and compares the observations with forced cooled <span class="hlt">reactors</span>. A number of <span class="hlt">reactor</span> startup transients have been modeled, and issues such as power peaking, and power-to-flow mismatches, and loading transients were examined, including the possibility of heat flow from the heat exchanger back into the <span class="hlt">reactor</span>. This system model is envisioned as a tool to be used for screening various heat pipe cooled <span class="hlt">reactor</span> concepts, for designing and developing test facility requirements, for use in safety evaluations, and for developing test criteria for in-pile and out-of-pile test facilities. .</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4248184','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4248184"><span>NEUTRONIC <span class="hlt">REACTOR</span> SYSTEM</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Treshow, M.</p> <p>1959-02-10</p> <p>A <span class="hlt">reactor</span> system incorporating a <span class="hlt">reactor</span> of the heterogeneous boiling water type is described. The <span class="hlt">reactor</span> is comprised essentially of a core submerged adwater in the lower half of a pressure vessel and two distribution rings connected to a source of water are disposed within the pressure vessel above the <span class="hlt">reactor</span> core, the lower distribution ring being submerged adjacent to the uppcr end of the <span class="hlt">reactor</span> core and the other distribution ring being located adjacent to the top of the pressure vessel. A feed-water control valve, responsive to the steam demand of the load, is provided in the feedwater line to the distribution rings and regulates the amount of feed water flowing to each distribution ring, the proportion of water flowing to the submerged distribution ring being proportional to the steam demand of the load. This invention provides an automatic means exterior to the <span class="hlt">reactor</span> to control the reactivity of the <span class="hlt">reactor</span> over relatively long periods of time without relying upon movement of control rods or of other moving parts within the <span class="hlt">reactor</span> structure.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/863525','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/863525"><span><span class="hlt">Reactor</span> safety method</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Vachon, Lawrence J.</p> <p>1980-03-11</p> <p>This invention relates to safety means for preventing a gas cooled nuclear <span class="hlt">reactor</span> from attaining criticality prior to start up in the event the <span class="hlt">reactor</span> core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the <span class="hlt">reactor</span> coolant channels with a neutral absorbing material that will vaporize at the <span class="hlt">reactor</span>'s operating temperature.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_1");'>1</a></li> <li><a href="#" onclick='return showDiv("page_2");'>2</a></li> <li class="active"><span>3</span></li> <li><a href="#" onclick='return showDiv("page_4");'>4</a></li> <li><a href="#" onclick='return showDiv("page_5");'>5</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_3 --> <div id="page_4" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_2");'>2</a></li> <li><a href="#" onclick='return showDiv("page_3");'>3</a></li> <li class="active"><span>4</span></li> <li><a href="#" onclick='return showDiv("page_5");'>5</a></li> <li><a href="#" onclick='return showDiv("page_6");'>6</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="61"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1389838','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1389838"><span>Nuclear <span class="hlt">reactor</span> neutron shielding</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Speaker, Daniel P; Neeley, Gary W; Inman, James B</p> <p></p> <p>A nuclear <span class="hlt">reactor</span> includes a <span class="hlt">reactor</span> pressure vessel and a nuclear <span class="hlt">reactor</span> core comprising fissile material disposed in a lower portion of the <span class="hlt">reactor</span> pressure vessel. The lower portion of the <span class="hlt">reactor</span> pressure vessel is disposed in a <span class="hlt">reactor</span> cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear <span class="hlt">reactor</span> core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the <span class="hlt">reactor</span> pressure vessel and the wall of the <span class="hlt">reactor</span> cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactormore » cavity, and an inner neutron stop ring attached to the <span class="hlt">reactor</span> pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1080313','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1080313"><span>Spinning fluids <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Miller, Jan D; Hupka, Jan; Aranowski, Robert</p> <p>2012-11-20</p> <p>A spinning fluids <span class="hlt">reactor</span>, includes a <span class="hlt">reactor</span> body (24) having a circular cross-section and a fluid contactor screen (26) within the <span class="hlt">reactor</span> body (24). The fluid contactor screen (26) having a plurality of apertures and a circular cross-section concentric with the <span class="hlt">reactor</span> body (24) for a length thus forming an inner volume (28) bound by the fluid contactor screen (26) and an outer volume (30) bound by the <span class="hlt">reactor</span> body (24) and the fluid contactor screen (26). A primary inlet (20) can be operatively connected to the <span class="hlt">reactor</span> body (24) and can be configured to produce flow-through first spinning flow of a first fluid within the inner volume (28). A secondary inlet (22) can similarly be operatively connected to the <span class="hlt">reactor</span> body (24) and can be configured to produce a second flow of a second fluid within the outer volume (30) which is optionally spinning.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017AIPC.1799e0012S','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017AIPC.1799e0012S"><span>Thorium fueled <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Sipaun, S.</p> <p>2017-01-01</p> <p>Current development in thorium fueled <span class="hlt">reactors</span> shows that they can be designed to operate in the fast or thermal spectrum. The thorium/uranium fuel cycle converts fertile thorium-232 into fissile uranium-233, which fissions and releases energy. This paper analyses the characteristics of thorium fueled <span class="hlt">reactors</span> and discusses the thermal <span class="hlt">reactor</span> option. It is found that thorium fuel can be utilized in molten salt <span class="hlt">reactors</span> through many configurations and designs. A balanced assessment on the feasibility of adopting one <span class="hlt">reactor</span> technology versus another could lead to optimized benefits of having thorium resource.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/883434','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/883434"><span>Request for Naval <span class="hlt">Reactors</span> Comment on Proposed Prometheus Space Flight Nuclear <span class="hlt">Reactor</span> High Tier <span class="hlt">Reactor</span> Safety Requirements and for Naval <span class="hlt">Reactors</span> Approval to Transmit These Requirements to JPL</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>D. Kokkinos</p> <p>2005-04-28</p> <p>The purpose of this letter is to request Naval <span class="hlt">Reactors</span> comments on the nuclear <span class="hlt">reactor</span> high tier requirements for the PROMETHEUS space flight <span class="hlt">reactor</span> design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval <span class="hlt">Reactors</span> approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the <span class="hlt">reactor</span> safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear <span class="hlt">reactor</span> high tier safety requirements are consistent with the long standing safety culture of the Naval <span class="hlt">Reactors</span> Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophymore » on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear <span class="hlt">Reactors</span> (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5017112-thermos-reactors','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/5017112-thermos-reactors"><span>Thermos <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Labrousse, M.; Lerouge, B.; Dupuy, G.</p> <p>1978-04-01</p> <p>THERMOS is a water <span class="hlt">reactor</span> designed to provide hot water up to 120/sup 0/C for district heating or for desalination applications. It is a 100-MW <span class="hlt">reactor</span> based on proven technology: oxide fuel plate elements, integrated primary circuit, and <span class="hlt">reactor</span> vessel located in the bottom of a pool. As in swimming pool <span class="hlt">reactors</span>, the pool is used for biological shielding, emergency core cooling, and fission product filtering (in case of an accident). Before economics, safety is the main characteristic of the concept: no fuel failure admitted, core under water in any accidental configuration, inspection of every ''nuclear'' component, and double-wall containment.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4170746','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4170746"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Daniels, F.</p> <p>1959-10-27</p> <p>A <span class="hlt">reactor</span> in which at least a portion of the moderator is in the form of movable refractory balls is described. In addition to their moderating capacity, these balls may serve as carriers for fissionable material or fertile material, or may serve in a coolant capacity to remove heat from the <span class="hlt">reactor</span>. A pneumatic system is used to circulate the balls through the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/4091938','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/4091938"><span>Control Means for <span class="hlt">Reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Manley, J. H.</p> <p>1961-06-27</p> <p>An apparatus for controlling a nuclear <span class="hlt">reactor</span> includes a tank just below the <span class="hlt">reactor</span>, tubes extending from the tank into the <span class="hlt">reactor</span>, and a thermally expansible liquid neutron absorbent material in the tank. The liquid in the tank is exposed to a beam of neutrons from the <span class="hlt">reactor</span> which heats the liquid causing it to expand into the <span class="hlt">reactor</span> when the neutron flux in the <span class="hlt">reactor</span> rises above a predetermincd danger point. Boron triamine may be used for this purpose.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1016389','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1016389"><span><span class="hlt">REACTOR</span> PHYSICS MODELING OF SPENT RESEARCH <span class="hlt">REACTOR</span> FUEL FOR TECHNICAL NUCLEAR FORENSICS</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Nichols, T.; Beals, D.; Sternat, M.</p> <p>2011-07-18</p> <p>Technical nuclear forensics (TNF) refers to the collection, analysis and evaluation of pre- and post-detonation radiological or nuclear materials, devices, and/or debris. TNF is an integral component, complementing traditional forensics and investigative work, to help enable the attribution of discovered radiological or nuclear material. Research is needed to improve the capabilities of TNF. One research area of interest is determining the isotopic signatures of research <span class="hlt">reactors</span>. Research <span class="hlt">reactors</span> are a potential source of both radiological and nuclear material. Research <span class="hlt">reactors</span> are often the least safeguarded type of <span class="hlt">reactor</span>; they vary greatly in size, fuel type, enrichment, power, and burn-up. Manymore » research <span class="hlt">reactors</span> are fueled with highly-enriched uranium (HEU), up to {approx}93% {sup 235}U, which could potentially be used as weapons material. All of them have significant amounts of radiological material with which a radioactive dispersal device (RDD) could be built. Therefore, the ability to attribute if material originated from or was produced in a specific research <span class="hlt">reactor</span> is an important tool in providing for the security of the United States. Currently there are approximately 237 operating research <span class="hlt">reactors</span> worldwide, another 12 are in temporary shutdown and 224 research <span class="hlt">reactors</span> are reported as shut down. Little is currently known about the isotopic signatures of spent research <span class="hlt">reactor</span> fuel. An effort is underway at Savannah River National Laboratory (SRNL) to analyze spent research <span class="hlt">reactor</span> fuel to determine these signatures. Computer models, using <span class="hlt">reactor</span> physics codes, are being compared to the measured analytes in the spent fuel. This allows for improving the <span class="hlt">reactor</span> physics codes in modeling research <span class="hlt">reactors</span> for the purpose of nuclear forensics. Currently the Oak Ridge Research <span class="hlt">reactor</span> (ORR) is being modeled and fuel samples are being analyzed for comparison. Samples of an ORR spent fuel assembly were taken by SRNL for analytical and</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4202847','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4202847"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Grebe, J.J.</p> <p>1959-07-14</p> <p>High temperature <span class="hlt">reactors</span> which are uniquely adapted to serve as the heat source for nuclear pcwered rockets are described. The <span class="hlt">reactor</span> is comprised essentially of an outer tubular heat resistant casing which provides the main coolant passageway to and away from the <span class="hlt">reactor</span> core within the casing and in which the working fluid is preferably hydrogen or helium gas which is permitted to vaporize from a liquid storage tank. The <span class="hlt">reactor</span> core has a generally spherical shape formed entirely of an active material comprised of fissile material and a moderator material which serves as a diluent. The active material is fabricated as a gas permeable porous material and is interlaced in a random manner with very small inter-connecting bores or capillary tubes through which the coolant gas may flow. The entire <span class="hlt">reactor</span> is divided into successive sections along the direction of the temperature gradient or coolant flow, each section utilizing materials of construction which are most advantageous from a nuclear standpoint and which at the same time can withstand the operating temperature of that particular zone. This design results in a nuclear <span class="hlt">reactor</span> characterized simultaneously by a minimum critiral size and mass and by the ability to heat a working fluid to an extremely high temperature.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4836210','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4836210"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Fraas, A.P.; Mills, C.B.</p> <p>1961-11-21</p> <p>A neutronic <span class="hlt">reactor</span> in which neutron moderation is achieved primarily in its reflector is described. The <span class="hlt">reactor</span> structure consists of a cylindrical central "island" of moderator and a spherical moderating reflector spaced therefrom, thereby providing an annular space. An essentially unmoderated liquid fuel is continuously passed through the annular space and undergoes fission while contained therein. The <span class="hlt">reactor</span>, because of its small size, is particularly adapted for propulsion uses, including the propulsion of aircraft. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/26476649','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/26476649"><span><span class="hlt">Reactor</span> performances and microbial communities of biogas <span class="hlt">reactors</span>: effects of inoculum sources.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Han, Sheng; Liu, Yafeng; Zhang, Shicheng; Luo, Gang</p> <p>2016-01-01</p> <p>Anaerobic digestion is a very complex process that is mediated by various microorganisms, and the understanding of the microbial community assembly and its corresponding function is critical in order to better control the anaerobic process. The present study investigated the effect of different inocula on the microbial community assembly in biogas <span class="hlt">reactors</span> treating cellulose with various inocula, and three parallel biogas <span class="hlt">reactors</span> with the same inoculum were also operated in order to reveal the reproducibility of both microbial communities and functions of the biogas <span class="hlt">reactors</span>. The results showed that the biogas production, volatile fatty acid (VFA) concentrations, and pH were different for the biogas <span class="hlt">reactors</span> with different inocula, and different steady-state microbial community patterns were also obtained in different biogas <span class="hlt">reactors</span> as reflected by Bray-Curtis similarity matrices and taxonomic classification. It indicated that inoculum played an important role in shaping the microbial communities of biogas <span class="hlt">reactor</span> in the present study, and the microbial community assembly in biogas <span class="hlt">reactor</span> did not follow the niche-based ecology theory. Furthermore, it was found that the microbial communities and <span class="hlt">reactor</span> performances of parallel biogas <span class="hlt">reactors</span> with the same inoculum were different, which could be explained by the neutral-based ecology theory and stochastic factors should played important roles in the microbial community assembly in the biogas <span class="hlt">reactors</span>. The Bray-Curtis similarity matrices analysis suggested that inoculum affected more on the microbial community assembly compared to stochastic factors, since the samples with different inocula had lower similarity (10-20 %) compared to the samples from the parallel biogas <span class="hlt">reactors</span> (30 %).</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4329372','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4329372"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Miller, H.I.; Smith, R.C.</p> <p>1958-01-21</p> <p>This patent relates to nuclear <span class="hlt">reactors</span> of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The <span class="hlt">reactor</span> is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the <span class="hlt">reactor</span>. An additional means for increasing the safety factor of the <span class="hlt">reactor</span> by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/869665','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/869665"><span><span class="hlt">Reactor</span> water cleanup system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Gluntz, Douglas M.; Taft, William E.</p> <p>1994-01-01</p> <p>A <span class="hlt">reactor</span> water cleanup system includes a <span class="hlt">reactor</span> pressure vessel containing a <span class="hlt">reactor</span> core submerged in <span class="hlt">reactor</span> water. First and second parallel cleanup trains are provided for extracting portions of the <span class="hlt">reactor</span> water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the <span class="hlt">reactor</span> water, and a cleaner for cleaning the cooled <span class="hlt">reactor</span> water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6890352','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/6890352"><span><span class="hlt">Reactor</span> water cleanup system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Gluntz, D.M.; Taft, W.E.</p> <p>1994-12-20</p> <p>A <span class="hlt">reactor</span> water cleanup system includes a <span class="hlt">reactor</span> pressure vessel containing a <span class="hlt">reactor</span> core submerged in <span class="hlt">reactor</span> water. First and second parallel cleanup trains are provided for extracting portions of the <span class="hlt">reactor</span> water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the <span class="hlt">reactor</span> water, and a cleaner for cleaning the cooled <span class="hlt">reactor</span> water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling. 1 figure.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.loc.gov/pictures/collection/hh/item/id0410.photos.195683p/','SCIGOV-HHH'); return false;" href="https://www.loc.gov/pictures/collection/hh/item/id0410.photos.195683p/"><span>97. ARAIII. ML1 <span class="hlt">reactor</span> has been moved into GCRE <span class="hlt">reactor</span> ...</span></a></p> <p><a target="_blank" href="http://www.loc.gov/pictures/collection/hh/">Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey</a></p> <p></p> <p></p> <p>97. ARA-III. ML-1 <span class="hlt">reactor</span> has been moved into GCRE <span class="hlt">reactor</span> building (ARA-608) for examination of corrosion on its underside and repair. May 24, 1963. Ineel photo no. 63-3485. - Idaho National Engineering Laboratory, Army <span class="hlt">Reactors</span> Experimental Area, Scoville, Butte County, ID</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4042999','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4042999"><span>NEUTRONIC <span class="hlt">REACTOR</span> SHIELDING</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Borst, L.B.</p> <p>1961-07-11</p> <p>A special hydrogenous concrete shielding for <span class="hlt">reactors</span> is described. In addition to Portland cement and water, the concrete essentially comprises 30 to 60% by weight barytes aggregate for enhanced attenuation of fast neutrons. The biological shields of AEC's Oak Ridge Graphite <span class="hlt">Reactor</span> and Materials Testing <span class="hlt">Reactor</span> are particular embodiments.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017IzAOP..53.1142G','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017IzAOP..53.1142G"><span>Basic Geometric Support of Systems for Earth Observation from Geostationary and Highly Elliptical Orbits</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Gektin, Yu. M.; Egoshkin, N. A.; Eremeev, V. V.; Kuznecov, A. E.; Moskatinyev, I. V.; Smelyanskiy, M. B.</p> <p>2017-12-01</p> <p>A set of standardized models and algorithms for geometric normalization and georeferencing images from geostationary and highly elliptical Earth observation systems is considered. The algorithms can process information from modern scanning multispectral sensors with two-coordinate scanning and represent normalized images in optimal projection. Problems of the high-precision ground calibration of the imaging equipment using reference objects, as well as issues of the flight calibration and refinement of geometric models using the absolute and relative reference points, are considered. Practical testing of the models, algorithms, and technologies is performed in the calibration of sensors for spacecrafts of the Electro-L series and during the simulation of the <span class="hlt">Arktika</span> prospective system.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4055848','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4055848"><span><span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Roman, W.G.</p> <p>1961-06-27</p> <p>A pressurized water <span class="hlt">reactor</span> in which automatic control is achieved by varying the average density of the liquid moderator-cooiant is patented. Density is controlled by the temperature and power level of the <span class="hlt">reactor</span> ftself. This control can be effected by the use of either plate, pellet, or tubular fuel elements. The fuel elements are disposed between upper and lower coolant plenum chambers and are designed to permit unrestricted coolant flow. The control chamber has an inlet opening communicating with the lower coolant plenum chamber and a restricted vapor vent communicating with the upper coolant plenum chamber. Thus, a variation in temperature of the fuel elements will cause a variation in the average moderator density in the chamber which directly affects the power level of the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/203877','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/203877"><span>Pressurized fluidized bed <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Isaksson, J.</p> <p>1996-03-19</p> <p>A pressurized fluid bed <span class="hlt">reactor</span> power plant includes a fluidized bed <span class="hlt">reactor</span> contained within a pressure vessel with a pressurized gas volume between the <span class="hlt">reactor</span> and the vessel. A first conduit supplies primary gas from the gas volume to the <span class="hlt">reactor</span>, passing outside the pressure vessel and then returning through the pressure vessel to the <span class="hlt">reactor</span>, and pressurized gas is supplied from a compressor through a second conduit to the gas volume. A third conduit, comprising a hot gas discharge, carries gases from the <span class="hlt">reactor</span>, through a filter, and ultimately to a turbine. During normal operation of the plant, pressurized gas is withdrawn from the gas volume through the first conduit and introduced into the <span class="hlt">reactor</span> at a substantially continuously controlled rate as the primary gas to the <span class="hlt">reactor</span>. In response to an operational disturbance of the plant, the flow of gas in the first, second, and third conduits is terminated, and thereafter the pressure in the gas volume and in the <span class="hlt">reactor</span> is substantially simultaneously reduced by opening pressure relief valves in the first and third conduits, and optionally by passing air directly from the second conduit to the turbine. 1 fig.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/870341','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/870341"><span>Pressurized fluidized bed <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Isaksson, Juhani</p> <p>1996-01-01</p> <p>A pressurized fluid bed <span class="hlt">reactor</span> power plant includes a fluidized bed <span class="hlt">reactor</span> contained within a pressure vessel with a pressurized gas volume between the <span class="hlt">reactor</span> and the vessel. A first conduit supplies primary gas from the gas volume to the <span class="hlt">reactor</span>, passing outside the pressure vessel and then returning through the pressure vessel to the <span class="hlt">reactor</span>, and pressurized gas is supplied from a compressor through a second conduit to the gas volume. A third conduit, comprising a hot gas discharge, carries gases from the <span class="hlt">reactor</span>, through a filter, and ultimately to a turbine. During normal operation of the plant, pressurized gas is withdrawn from the gas volume through the first conduit and introduced into the <span class="hlt">reactor</span> at a substantially continuously controlled rate as the primary gas to the <span class="hlt">reactor</span>. In response to an operational disturbance of the plant, the flow of gas in the first, second, and third conduits is terminated, and thereafter the pressure in the gas volume and in the <span class="hlt">reactor</span> is substantially simultaneously reduced by opening pressure relief valves in the first and third conduits, and optionally by passing air directly from the second conduit to the turbine.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_2");'>2</a></li> <li><a href="#" onclick='return showDiv("page_3");'>3</a></li> <li class="active"><span>4</span></li> <li><a href="#" onclick='return showDiv("page_5");'>5</a></li> <li><a href="#" onclick='return showDiv("page_6");'>6</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_4 --> <div id="page_5" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_3");'>3</a></li> <li><a href="#" onclick='return showDiv("page_4");'>4</a></li> <li class="active"><span>5</span></li> <li><a href="#" onclick='return showDiv("page_6");'>6</a></li> <li><a href="#" onclick='return showDiv("page_7");'>7</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="81"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1369358','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1369358"><span>Neutron fluxes in test <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Youinou, Gilles Jean-Michel</p> <p></p> <p>Communicate the fact that high-power water-cooled test <span class="hlt">reactors</span> such as the Advanced Test <span class="hlt">Reactor</span> (ATR), the High Flux Isotope <span class="hlt">Reactor</span> (HFIR) or the Jules Horowitz <span class="hlt">Reactor</span> (JHR) cannot provide fast flux levels as high as sodium-cooled fast test <span class="hlt">reactors</span>. The memo first presents some basics physics considerations about neutron fluxes in test <span class="hlt">reactors</span> and then uses ATR, HFIR and JHR as an illustration of the performance of modern high-power water-cooled test <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.loc.gov/pictures/collection/hh/item/id0410.photos.203806p/','SCIGOV-HHH'); return false;" href="https://www.loc.gov/pictures/collection/hh/item/id0410.photos.203806p/"><span>151. ARAIII <span class="hlt">Reactor</span> building (ARA608) Details of <span class="hlt">reactor</span> pit and ...</span></a></p> <p><a target="_blank" href="http://www.loc.gov/pictures/collection/hh/">Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey</a></p> <p></p> <p></p> <p>151. ARA-III <span class="hlt">Reactor</span> building (ARA-608) Details of <span class="hlt">reactor</span> pit and instrument plan. Aerojet-general 880-area/GCRE-608-T-19. Date: November 1958. Ineel index code no. 063-0608-25-013-102678. - Idaho National Engineering Laboratory, Army <span class="hlt">Reactors</span> Experimental Area, Scoville, Butte County, ID</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4807325','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4807325"><span>NEUTRONIC <span class="hlt">REACTOR</span> MANIPULATING DEVICE</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ohlinger, L.A.</p> <p>1962-08-01</p> <p>A cable connecting a control rod in a <span class="hlt">reactor</span> with a motor outside the <span class="hlt">reactor</span> for moving the rod, and a helical conduit in the <span class="hlt">reactor</span> wall, through which the cable passes are described. The helical shape of the conduit prevents the escape of certain harmful radiations from the <span class="hlt">reactor</span>. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.loc.gov/pictures/collection/hh/item/id0410.photos.203810p/','SCIGOV-HHH'); return false;" href="https://www.loc.gov/pictures/collection/hh/item/id0410.photos.203810p/"><span>155. ARAIII <span class="hlt">Reactor</span> building (ARA608) Details of <span class="hlt">reactor</span> pit showing ...</span></a></p> <p><a target="_blank" href="http://www.loc.gov/pictures/collection/hh/">Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey</a></p> <p></p> <p></p> <p>155. ARA-III <span class="hlt">Reactor</span> building (ARA-608) Details of <span class="hlt">reactor</span> pit showing tray supports and fuel element storage rack. Aerojet-general 880-area/GCRE-608-MS-2. Date: November 1958. Ineel index code no. 063-0608-40-013-102625. - Idaho National Engineering Laboratory, Army <span class="hlt">Reactors</span> Experimental Area, Scoville, Butte County, ID</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4060405','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4060405"><span>FAST NEUTRON <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Soodak, H.; Wigner, E.P.</p> <p>1961-07-25</p> <p>A <span class="hlt">reactor</span> comprising fissionable material in concentration sufficiently high so that the average neutron enengy within the <span class="hlt">reactor</span> is at least 25,000 ev is described. A natural uranium blanket surrounds the <span class="hlt">reactor</span>, and a moderating reflector surrounds the blanket. The blanket is thick enough to substantially eliminate flow of neutrons from the reflector.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4242598','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4242598"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hurwitz, H. Jr.; Brooks, H.; Mannal, C.; Payne, J.H.; Luebke, E.A.</p> <p>1959-03-24</p> <p>A <span class="hlt">reactor</span> of the heterogeneous, liquid cooled type is described. This <span class="hlt">reactor</span> is comprised of a central region of a plurality of vertically disposed elongated tubes surrounded by a region of moderator material. The central region is comprised of a central core surrounded by a reflector region which is surrounded by a fast neutron absorber region, which in turn is surrounded by a slow neutron absorber region. Liquid sodium is used as the primary coolant and circulates through the core which contains the fuel elements. Control of the <span class="hlt">reactor</span> is accomplished by varying the ability of the reflector region to reflect neutrons back into the core of the <span class="hlt">reactor</span>. For this purpose the reflector is comprised of moderator and control elements having varying effects on reactivity, the control elements being arranged and actuated by groups to give regulation, shim, and safety control.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.osti.gov/sciencecinema/biblio/1164319','SCIGOVIMAGE-SCICINEMA'); return false;" href="http://www.osti.gov/sciencecinema/biblio/1164319"><span>F <span class="hlt">Reactor</span> Inspection</span></a></p> <p><a target="_blank" href="http://www.osti.gov/sciencecinema/">ScienceCinema</a></p> <p>Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike</p> <p>2018-01-16</p> <p>Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F <span class="hlt">Reactor</span> before stepping inside the <span class="hlt">reactor</span> to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the <span class="hlt">reactor</span> open since 2008. The F <span class="hlt">Reactor</span> is one of nine <span class="hlt">reactors</span> along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned <span class="hlt">reactors</span> periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1164319','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1164319"><span>F <span class="hlt">Reactor</span> Inspection</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike</p> <p>2014-10-29</p> <p>Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F <span class="hlt">Reactor</span> before stepping inside the <span class="hlt">reactor</span> to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the <span class="hlt">reactor</span> open since 2008. The F <span class="hlt">Reactor</span> is one of nine <span class="hlt">reactors</span> along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned <span class="hlt">reactors</span> periodically to evaluate the structural integrity of the safe storage enclosuremore » and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4631454','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4631454"><span><span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Szilard, L.</p> <p>1963-09-10</p> <p>A breeder <span class="hlt">reactor</span> is described, including a mass of fissionable material that is less than critical with respect to unmoderated neutrons and greater than critical with respect to neutrons of average energies substantially greater than thermal, a coolant selected from sodium or sodium--potassium alloys, a control liquid selected from lead or lead--bismuth alloys, and means for varying the quantity of control liquid in the <span class="hlt">reactor</span>. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5266104-reactor-operations-monitoring-system','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/5266104-reactor-operations-monitoring-system"><span><span class="hlt">Reactor</span> Operations Monitoring System</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Hart, M.M.</p> <p>1989-01-01</p> <p>The <span class="hlt">Reactor</span> Operations Monitoring System (ROMS) is a VME based, parallel processor data acquisition and safety action system designed by the Equipment Engineering Section and <span class="hlt">Reactor</span> Engineering Department of the Savannah River Site. The ROMS will be analyzing over 8 million signal samples per minute. Sixty-eight microprocessors are used in the ROMS in order to achieve a real-time data analysis. The ROMS is composed of multiple computer subsystems. Four redundant computer subsystems monitor 600 temperatures with 2400 thermocouples. Two computer subsystems share the monitoring of 600 <span class="hlt">reactor</span> coolant flows. Additional computer subsystems are dedicated to monitoring 400 signals from assortedmore » process sensors. Data from these computer subsystems are transferred to two redundant process display computer subsystems which present process information to <span class="hlt">reactor</span> operators and to <span class="hlt">reactor</span> control computers. The ROMS is also designed to carry out safety functions based on its analysis of process data. The safety functions include initiating a <span class="hlt">reactor</span> scram (shutdown), the injection of neutron poison, and the loadshed of selected equipment. A complete development <span class="hlt">Reactor</span> Operations Monitoring System has been built. It is located in the Program Development Center at the Savannah River Site and is currently being used by the <span class="hlt">Reactor</span> Engineering Department in software development. The Equipment Engineering Section is designing and fabricating the process interface hardware. Upon proof of hardware and design concept, orders will be placed for the final five systems located in the three <span class="hlt">reactor</span> areas, the <span class="hlt">reactor</span> training simulator, and the hardware maintenance center.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/20110008917','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/20110008917"><span>Hybrid adsorptive membrane <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Tsotsis, Theodore T. (Inventor); Sahimi, Muhammad (Inventor); Fayyaz-Najafi, Babak (Inventor); Harale, Aadesh (Inventor); Park, Byoung-Gi (Inventor); Liu, Paul K. T. (Inventor)</p> <p>2011-01-01</p> <p>A hybrid adsorbent-membrane <span class="hlt">reactor</span> in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-<span class="hlt">reactor</span> apparatus and a process using the <span class="hlt">reactor</span> or the apparatus.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1016557','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1016557"><span>Hybrid adsorptive membrane <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Tsotsis, Theodore T [Huntington Beach, CA; Sahimi, Muhammad [Altadena, CA; Fayyaz-Najafi, Babak [Richmond, CA; Harale, Aadesh [Los Angeles, CA; Park, Byoung-Gi [Yeosu, KR; Liu, Paul K. T. [Lafayette Hill, PA</p> <p>2011-03-01</p> <p>A hybrid adsorbent-membrane <span class="hlt">reactor</span> in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-<span class="hlt">reactor</span> apparatus and a process using the <span class="hlt">reactor</span> or the apparatus.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4247330','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4247330"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Moore, R.V.; Bowen, J.H.; Dent, K.H.</p> <p>1958-12-01</p> <p>A heterogeneous, natural uranium fueled, solid moderated, gas cooled <span class="hlt">reactor</span> is described, in which the fuel elements are in the form of elongated rods and are dlsposed within vertical coolant channels ln the moderator symmetrically arranged as a regular lattice in groups. This <span class="hlt">reactor</span> employs control rods which operate in vertical channels in the moderator so that each control rod is centered in one of the fuel element groups. The <span class="hlt">reactor</span> is enclosed in a pressure vessel which ls provided with access holes at the top to facilitate loading and unloadlng of the fuel elements, control rods and control rod driving devices.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/869563','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/869563"><span>Cross-flow electrochemical <span class="hlt">reactor</span> cells, cross-flow <span class="hlt">reactors</span>, and use of cross-flow <span class="hlt">reactors</span> for oxidation reactions</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Balachandran, Uthamalingam; Poeppel, Roger B.; Kleefisch, Mark S.; Kobylinski, Thaddeus P.; Udovich, Carl A.</p> <p>1994-01-01</p> <p>This invention discloses cross-flow electrochemical <span class="hlt">reactor</span> cells containing oxygen permeable materials which have both electron conductivity and oxygen ion conductivity, cross-flow <span class="hlt">reactors</span>, and electrochemical processes using cross-flow <span class="hlt">reactor</span> cells having oxygen permeable monolithic cores to control and facilitate transport of oxygen from an oxygen-containing gas stream to oxidation reactions of organic compounds in another gas stream. These cross-flow electrochemical <span class="hlt">reactors</span> comprise a hollow ceramic blade positioned across a gas stream flow or a stack of crossed hollow ceramic blades containing a channel or channels for flow of gas streams. Each channel has at least one channel wall disposed between a channel and a portion of an outer surface of the ceramic blade, or a common wall with adjacent blades in a stack comprising a gas-impervious mixed metal oxide material of a perovskite structure having electron conductivity and oxygen ion conductivity. The invention includes <span class="hlt">reactors</span> comprising first and second zones seprated by gas-impervious mixed metal oxide material material having electron conductivity and oxygen ion conductivity. Prefered gas-impervious materials comprise at least one mixed metal oxide having a perovskite structure or perovskite-like structure. The invention includes, also, oxidation processes controlled by using these electrochemical <span class="hlt">reactors</span>, and these reactions do not require an external source of electrical potential or any external electric circuit for oxidation to proceed.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4303004','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4303004"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ohlinger, L.A.; Wigner, E.P.; Weinberg, A.M.; Young, G.J.</p> <p>1958-09-01</p> <p>This patent relates to neutronic <span class="hlt">reactors</span> of the heterogeneous water cooled type, and in particular to a fuel element charging and discharging means therefor. In the embodiment illustrated the <span class="hlt">reactor</span> contains horizontal, parallel coolant tubes in which the fuel elements are disposed. A loading cart containing a magnzine for holding a plurality of fuel elements operates along the face of the <span class="hlt">reactor</span> at the inlet ends of the coolant tubes. The loading cart is equipped with a ram device for feeding fuel elements from the magazine through the inlot ends of the coolant tubes. Operating along the face adjacent the discharge ends of the tubes there is provided another cart means adapted to receive irradiated fuel elements as they are forced out of the discharge ends of the coolant tubes by the incoming new fuel elements. This cart is equipped with a tank coataining a coolant, such as water, into which the fuel elements fall, and a hydraulically operated plunger to hold the end of the fuel element being discharged. This inveation provides an apparatus whereby the fuel elements may be loaded into the <span class="hlt">reactor</span>, irradiated therein, and unloaded from the <span class="hlt">reactor</span> without stopping the fiow of the coolant and without danger to the operating personnel.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4296274','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4296274"><span>HORIZONTAL BOILING <span class="hlt">REACTOR</span> SYSTEM</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Treshow, M.</p> <p>1958-11-18</p> <p><span class="hlt">Reactors</span> of the boiling water type are described wherein water serves both as the moderator and coolant. The <span class="hlt">reactor</span> system consists essentially of a horizontal pressure vessel divided into two compartments by a weir, a thermal neutronic <span class="hlt">reactor</span> core having vertical coolant passages and designed to use water as a moderator-coolant posltioned in one compartment, means for removing live steam from the other compartment and means for conveying feed-water and water from the steam compartment to the <span class="hlt">reactor</span> compartment. The system further includes auxiliary apparatus to utilize the steam for driving a turbine and returning the condensate to the feed-water inlet of the <span class="hlt">reactor</span>. The entire system is designed so that the <span class="hlt">reactor</span> is self-regulating and has self-limiting power and self-limiting pressure features.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.loc.gov/pictures/collection/hh/item/mo1871.photos.364015p/','SCIGOV-HHH'); return false;" href="https://www.loc.gov/pictures/collection/hh/item/mo1871.photos.364015p/"><span>Looking Southwest at <span class="hlt">Reactor</span> Box Furnaces With <span class="hlt">Reactor</span> Boxes and ...</span></a></p> <p><a target="_blank" href="http://www.loc.gov/pictures/collection/hh/">Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey</a></p> <p></p> <p></p> <p>Looking Southwest at <span class="hlt">Reactor</span> Box Furnaces With <span class="hlt">Reactor</span> Boxes and Repossessed Uranium in Recycle Recovery Building - Hematite Fuel Fabrication Facility, Recycle Recovery Building, 3300 State Road P, Festus, Jefferson County, MO</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4054791','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4054791"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Metcalf, H.E.; Johnson, H.W.</p> <p>1961-04-01</p> <p>BS>A nuclear <span class="hlt">reactor</span> incorporating fuel rods passing through a moderator and including tubes of a material of higher Thermal conductivity than the fuel in contact with the fuel is described. The tubes extend beyond the active portion of the <span class="hlt">reactor</span> into contant with a fiuld coolant.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4739696','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4739696"><span>NEUTRONIC <span class="hlt">REACTOR</span> POWER PLANT</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Metcalf, H.E.</p> <p>1962-12-25</p> <p>This patent relates to a nuclear <span class="hlt">reactor</span> power plant incorporating an air-cooled, beryllium oxide-moderated, pebble bed <span class="hlt">reactor</span>. According to the invention means are provided for circulating a flow of air through tubes in the <span class="hlt">reactor</span> to a turbine and for directing a sidestream of the circu1ating air through the pebble bed to remove fission products therefrom as well as assist in cooling the <span class="hlt">reactor</span>. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4243177','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4243177"><span><span class="hlt">REACTOR</span> SHIELD</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.</p> <p>1959-02-17</p> <p>Radiation shield construction is described for a nuclear <span class="hlt">reactor</span>. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. <span class="hlt">Reactor</span> coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the <span class="hlt">reactor</span> container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the <span class="hlt">reactor</span> container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_3");'>3</a></li> <li><a href="#" onclick='return showDiv("page_4");'>4</a></li> <li class="active"><span>5</span></li> <li><a href="#" onclick='return showDiv("page_6");'>6</a></li> <li><a href="#" onclick='return showDiv("page_7");'>7</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_5 --> <div id="page_6" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_4");'>4</a></li> <li><a href="#" onclick='return showDiv("page_5");'>5</a></li> <li class="active"><span>6</span></li> <li><a href="#" onclick='return showDiv("page_7");'>7</a></li> <li><a href="#" onclick='return showDiv("page_8");'>8</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="101"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4306723-experience-united-states-reactor-operation-reactor-safeguards','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/4306723-experience-united-states-reactor-operation-reactor-safeguards"><span>THE EXPERIENCE IN THE UNITED STATES WITH <span class="hlt">REACTOR</span> OPERATION AND <span class="hlt">REACTOR</span> SAFEGUARDS</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>McCullough, C.R.</p> <p>1958-10-31</p> <p><span class="hlt">Reactors</span> are operating or planned at locations in the United States in cities, near cities, and at remote locations. There is a general pattern that the higher power <span class="hlt">reactors</span> are not in, but fairly uear cities, and the testing <span class="hlt">reactors</span> for more hazardous experiments are at remote locations. A great deal has been done on the theoretical and experimental study of importunt features of <span class="hlt">reactor</span> design. The metal-water reaction is still a theoretical possibility but tests of fuel element burnout under conditions approaching <span class="hlt">reactor</span> operation gave no reaction. It appears that nucleate boiling does not necessarily result in steam blanketingmore » and fuel melting. Much attention is being given to the calculation of core kinetics but it is being found that temperature, power, and void coefficients cannot be calculated with accuracy and experiments are required. Some surprises are found giving positive localized void coefficients. Possible oscillatory behavior of <span class="hlt">reactors</span> is being given careful study. No dangerous oscillations have been found in operating <span class="hlt">reactors</span> but osciliations hare appeared in experimeats. The design of control and safety systems varies wvith different constructors. The relation of control to the kinetic behavior of the <span class="hlt">reactor</span> is being studied. The importance of sensing element locations in order to know actual local <span class="hlt">reactor</span> power level is being recognized. The time constants of instrumentation as related to <span class="hlt">reactor</span> kinetics are being studied. Pressure vessels for <span class="hlt">reactors</span> are being designed and manufactured. Many of these are beyond any previous experience. The stress problem is being given careful study. The effect of radiation is being studied experimentally. The stress problems of piping and pressure vessels is a difficult design problem being met successfully in <span class="hlt">reactor</span> plants. The proper organization and procedure for operation of <span class="hlt">reactors</span> is being evolved for resourch, testing, and power <span class="hlt">reactors</span>. The importance of written standards and</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.osti.gov/sciencecinema/biblio/1046054','SCIGOVIMAGE-SCICINEMA'); return false;" href="http://www.osti.gov/sciencecinema/biblio/1046054"><span>Advanced Test <span class="hlt">Reactor</span> Tour</span></a></p> <p><a target="_blank" href="http://www.osti.gov/sciencecinema/">ScienceCinema</a></p> <p>Miley, Don</p> <p>2017-12-21</p> <p>The Advanced Test <span class="hlt">Reactor</span> at Idaho National Laboratory is the foremost nuclear materials test <span class="hlt">reactor</span> in the world. This virtual tour describes the <span class="hlt">reactor</span>, how experiments are conducted, and how spent nuclear fuel is handled and stored.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.loc.gov/pictures/collection/hh/item/id0445.photos.224331p/','SCIGOV-HHH'); return false;" href="https://www.loc.gov/pictures/collection/hh/item/id0445.photos.224331p/"><span>PBF <span class="hlt">Reactor</span> Building (PER620). Camera faces north into highbay/<span class="hlt">reactor</span> pit ...</span></a></p> <p><a target="_blank" href="http://www.loc.gov/pictures/collection/hh/">Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey</a></p> <p></p> <p></p> <p>PBF <span class="hlt">Reactor</span> Building (PER-620). Camera faces north into high-bay/<span class="hlt">reactor</span> pit area. Inside from for <span class="hlt">reactor</span> enclosure is in place. Photographer: John Capek. Date: March 15, 1967. INEEL negative no. 67-1769 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/864300','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/864300"><span>Nuclear <span class="hlt">reactor</span> control column</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Bachovchin, Dennis M.</p> <p>1982-01-01</p> <p>The nuclear <span class="hlt">reactor</span> control column comprises a column disposed within the nuclear <span class="hlt">reactor</span> core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the <span class="hlt">reactor</span> coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest cross-sectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the <span class="hlt">reactor</span> coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the <span class="hlt">reactor</span> coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the <span class="hlt">reactor</span> core and shutting down the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/862716','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/862716"><span>Nuclear <span class="hlt">reactor</span> overflow line</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Severson, Wayne J.</p> <p>1976-01-01</p> <p>The overflow line for the <span class="hlt">reactor</span> vessel of a liquid-metal-cooled nuclear <span class="hlt">reactor</span> includes means for establishing and maintaining a continuous bleed flow of coolant amounting to 5 to 10% of the total coolant flow through the overflow line to prevent thermal shock to the overflow line when the <span class="hlt">reactor</span> is restarted following a trip. Preferably a tube is disposed concentrically just inside the overflow line extending from a point just inside the <span class="hlt">reactor</span> vessel to an overflow tank and a suction line is provided opening into the body of liquid metal in the <span class="hlt">reactor</span> vessel and into the annulus between the overflow line and the inner tube.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4036294','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4036294"><span><span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Christy, R.F.</p> <p>1961-07-25</p> <p>A means is described for co-relating the essential physical requirements of a fission chain reaction in order that practical, compact, and easily controllable <span class="hlt">reactors</span> can be built. These objects are obtained by employing a composition of fissionsble isotope and moderator in fluid form in which the amount of fissionsble isotcpe present governs the reaction. The size of the <span class="hlt">reactor</span> is no longer a critical factor, the new criterion being the concentration of the fissionable isotope.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1176175','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1176175"><span>Methanation assembly using multiple <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Jahnke, Fred C.; Parab, Sanjay C.</p> <p>2007-07-24</p> <p>A methanation assembly for use with a water supply and a gas supply containing gas to be methanated in which a <span class="hlt">reactor</span> assembly has a plurality of methanation <span class="hlt">reactors</span> each for methanating gas input to the assembly and a gas delivery and cooling assembly adapted to deliver gas from the gas supply to each of said methanation <span class="hlt">reactors</span> and to combine water from the water supply with the output of each methanation <span class="hlt">reactor</span> being conveyed to a next methanation <span class="hlt">reactor</span> and carry the mixture to such next methanation <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4111719','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4111719"><span>NEUTRONIC <span class="hlt">REACTOR</span> SYSTEM</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Goett, J.J.</p> <p>1961-01-24</p> <p>A system is described which includes a neutronic <span class="hlt">reactor</span> containing a dispersion of fissionable material in a liquid moderator as fuel and a conveyor to which a portion of the dispersion may be passed and wherein the self heat of the slurry evaporates the moderator. Means are provided for condensing the liquid moderator and returning it to the <span class="hlt">reactor</span> and for conveying the dried fissionable material away from the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5045510-major-safety-provisions-nuclear-powered-ships','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/5045510-major-safety-provisions-nuclear-powered-ships"><span>Major safety provisions in nuclear-powered ships</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Khlopkin, N.S.; Belyaev, V.M.; Dubrovin, A.M.</p> <p>1984-12-01</p> <p>Considerable experience has been accumulated in the Soviet Union on the design, construction and operation of nuclear-powered civilian ships: the <span class="hlt">icebreakers</span> Lenin, Leonid Brezhnev and Sibir. The nuclear steam plants (NSP) used on these as the main energy source have been found to be highly reliable and safe, and it is desirable to use them in the future not only in <span class="hlt">icebreakers</span> but also in transport ships for use in ice fields. The Soviet program for building and developing nuclear-powered ships has involved careful attention to safety in ships containing NSP. The experience with the design and operation of nuclearmore » <span class="hlt">icebreakers</span> in recent years has led to the revision of safety standards for the nuclear ships and correspondingly ship NSP and international guidelines have been developed. If one meets the requirements as set forth in these documents, one has a safe basis for future Soviet nuclear-powered ships. The primary safety provisions for NSP are presented in this paper.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2010npnr.book..513F','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2010npnr.book..513F"><span>Neutronic <span class="hlt">Reactor</span> III</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Fermi, Enrico; Zinn, Walter H.; Anderson, Herbert L.</p> <p></p> <p>An improvement of the <span class="hlt">reactors</span> described in the previous Patents, aimed at increasing the reproduction factor, is reported here, such improvement being obtained by diminishing the neutron loss due to impurities within the <span class="hlt">reactor</span>. This is achieved by encasing the <span class="hlt">reactor</span> in a rubberized balloon cloth housing (or something like this) in order to eliminate the atmospheric air therefrom, thus eliminating both the effect of the danger coefficient of nitrogen (70% of the atmospheric air) and that of the argon present in the air, which can become radioactive. Since the removal of the air from the <span class="hlt">reactor</span> may result in structural problems, caused by the forces brought into play by that evacuation, the <span class="hlt">reactor</span> is then filled with a non-reactive (from a chemical and nuclear standpoint) gas such as helium or carbon dioxide. It is interesting to point out that the authors consider also the possibility to control (a little) the reproduction ratio of the <span class="hlt">reactor</span> by varying the air content of it. Just a rapid mention of the main idea of the present Patent (i.e. the encasing of the pile in a balloon cloth) appeared in [Fermi (1942f)], but no detailed description of the system considered here is reported in any other published paper.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/862441','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/862441"><span>Period meter for <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Rusch, Gordon K.</p> <p>1976-01-06</p> <p>An improved log N amplifier type nuclear <span class="hlt">reactor</span> period meter with reduced probability for noise-induced scrams is provided. With the <span class="hlt">reactor</span> at low power levels a sampling circuit is provided to determine the <span class="hlt">reactor</span> period by measuring the finite change in the amplitude of the log N amplifier output signal for a predetermined time period, while at high power levels, differentiation of the log N amplifier output signal provides an additional measure of the <span class="hlt">reactor</span> period.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017AIPC.1815f0013K','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017AIPC.1815f0013K"><span>Comparing the new generation accelerator driven subcritical <span class="hlt">reactor</span> system (ADS) to traditional critical <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Kemah, Elif; Akkaya, Recep; Tokgöz, Seyit Rıza</p> <p>2017-02-01</p> <p>In recent years, the accelerator driven subcritical <span class="hlt">reactors</span> have taken great interest worldwide. The Accelerator Driven System (ADS) has been used to produce neutron in subcritical state by the external proton beam source. These <span class="hlt">reactors</span>, which are hybrid systems, are important in production of clean and safe energy and conversion of radioactive waste. The ADS with the selection of reliability and robust target materials have been the new generation of fission <span class="hlt">reactors</span>. In addition, in the ADS <span class="hlt">Reactors</span> the problems of long-lived radioactive fission products and waste actinides encountered in the fission process of the <span class="hlt">reactor</span> during incineration can be solved, and ADS has come to the forefront of thorium as fuel for the <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2015AIPC.1659d0001B','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2015AIPC.1659d0001B"><span>Advantages of liquid fluoride thorium <span class="hlt">reactor</span> in comparison with light water <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Bahri, Che Nor Aniza Che Zainul; Majid, Amran Ab.; Al-Areqi, Wadeeah M.</p> <p>2015-04-01</p> <p>Liquid Fluoride Thorium <span class="hlt">Reactor</span> (LFTR) is an innovative design for the thermal breeder <span class="hlt">reactor</span> that has important potential benefits over the traditional <span class="hlt">reactor</span> design. LFTR is fluoride based liquid fuel, that use the thorium dissolved in salt mixture of lithium fluoride and beryllium fluoride. Therefore, LFTR technology is fundamentally different from the solid fuel technology currently in use. Although the traditional nuclear <span class="hlt">reactor</span> technology has been proven, it has perceptual problems with safety and nuclear waste products. The aim of this paper is to discuss the potential advantages of LFTR in three aspects such as safety, fuel efficiency and nuclear waste as an alternative energy generator in the future. Comparisons between LFTR and Light Water <span class="hlt">Reactor</span> (LWR), on general principles of fuel cycle, resource availability, radiotoxicity and nuclear weapon proliferation shall be elaborated.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.loc.gov/pictures/collection/hh/item/id0445.photos.224345p/','SCIGOV-HHH'); return false;" href="https://www.loc.gov/pictures/collection/hh/item/id0445.photos.224345p/"><span>PBF <span class="hlt">Reactor</span> Building (PER620). After lowering <span class="hlt">reactor</span> vessel onto blocks, ...</span></a></p> <p><a target="_blank" href="http://www.loc.gov/pictures/collection/hh/">Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey</a></p> <p></p> <p></p> <p>PBF <span class="hlt">Reactor</span> Building (PER-620). After lowering <span class="hlt">reactor</span> vessel onto blocks, it is rolled on logs into PBF. Metal framework under vessel is handling device. Various penetrations in <span class="hlt">reactor</span> bottom were for instrumentation, poison injection, drains. Large one, below center "manhole" was for primary coolant. Photographer: Larry Page. Date: February 13, 1970. INEEL negative no. 70-736 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4136916','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4136916"><span>NEUTRONIC <span class="hlt">REACTOR</span> CONSTRUCTION AND OPERATION</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>West, J.M.; Weills, J.T.</p> <p>1960-03-15</p> <p>A method is given for operating a nuclear <span class="hlt">reactor</span> having a negative coefficient of reactivity to compensate for the change in <span class="hlt">reactor</span> reactivity due to the burn-up of the xenon peak following start-up of the <span class="hlt">reactor</span>. When it is desired to start up the <span class="hlt">reactor</span> within less than 72 hours after shutdown, the temperature of the <span class="hlt">reactor</span> is lowered prior to start-up, and then gradually raised after start-up.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/7201310','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/7201310"><span><span class="hlt">Reactor</span> operation environmental information document</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Haselow, J.S.; Price, V.; Stephenson, D.E.</p> <p>1989-12-01</p> <p>The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear <span class="hlt">reactors</span> that were built during 1950--1955 at the SRS. K, L, and P <span class="hlt">reactors</span> are three of five <span class="hlt">reactors</span> that have been used in the past to produce the nuclear materials. All three of these <span class="hlt">reactors</span> discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three <span class="hlt">reactors</span> for restart in a manner that protects human health and the environment. To document that restarting the <span class="hlt">reactors</span> will have minimalmore » impacts to human health and the environment, a three-volume <span class="hlt">Reactor</span> Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P <span class="hlt">reactors</span> on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/103245-reactor-shutdown-experience','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/103245-reactor-shutdown-experience"><span><span class="hlt">Reactor</span> shutdown experience</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Cletcher, J.W.</p> <p>1995-10-01</p> <p>This is a regular report of summary statistics relating to recent <span class="hlt">reactor</span> shutdown experience. The information includes both number of events and rates of occurence. It was compiled from data about operating events that were entered into the SCSS data system by the Nuclear Operations Analysis Center at the Oak ridge National Laboratory and covers the six mont period of July 1 to December 31, 1994. Cumulative information, starting from May 1, 1994, is also reported. Updates on shutdown events included in earlier reports is excluded. Information on shutdowns as a function of <span class="hlt">reactor</span> power at the time of themore » shutdown for both BWR and PWR <span class="hlt">reactors</span> is given. Data is also discerned by shutdown type and <span class="hlt">reactor</span> age.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/20160002244','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/20160002244"><span>Crater Morphology in the Phoenix Landing Ellipse: Insights Into Net Erosion and Ice Table Depth</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Noe Dobrea, E. Z.; Stoker, C. R.; McKay, C. P.; Davila, A. F.; Krco, M.</p> <p>2015-01-01</p> <p><span class="hlt">Icebreaker</span> [1] is a Discovery class mission being developed for future flight opportunities. Under this mission concept, the <span class="hlt">Icebreaker</span> payload is carried on a stationary lander, and lands in the same landing ellipse as Phoenix. Samples are acquired from the subsurface using a drilling system that penetrates into materials which may include loose or cemented soil, icy soil, pure ice, rocks, or mixtures of these. To avoid the complexity of mating additional strings, the drill is single-string, limiting it to a total length of 1 m.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4164322','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4164322"><span>THERMAL NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Spinrad, B.I.</p> <p>1960-01-12</p> <p>A novel thermal <span class="hlt">reactor</span> was designed in which a first reflector formed from a high atomic weight, nonmoderating material is disposed immediately adjacent to the <span class="hlt">reactor</span> core. A second reflector composed of a moderating material is disposed outwardly of the first reflector. The advantage of this novel reflector arrangement is that the first reflector provides a high slow neutron flux in the second reflector, where irradiation experiments may be conducted with a small effect on <span class="hlt">reactor</span> reactivity.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/868175','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/868175"><span>Bioconversion <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>McCarty, Perry L.; Bachmann, Andre</p> <p>1992-01-01</p> <p>A bioconversion <span class="hlt">reactor</span> for the anaerobic fermentation of organic material. The bioconversion <span class="hlt">reactor</span> comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the <span class="hlt">reactor</span> but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_4");'>4</a></li> <li><a href="#" onclick='return showDiv("page_5");'>5</a></li> <li class="active"><span>6</span></li> <li><a href="#" onclick='return showDiv("page_7");'>7</a></li> <li><a href="#" onclick='return showDiv("page_8");'>8</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_6 --> <div id="page_7" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_5");'>5</a></li> <li><a href="#" onclick='return showDiv("page_6");'>6</a></li> <li class="active"><span>7</span></li> <li><a href="#" onclick='return showDiv("page_8");'>8</a></li> <li><a href="#" onclick='return showDiv("page_9");'>9</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="121"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/22391629-advantages-liquid-fluoride-thorium-reactor-comparison-light-water-reactor','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/22391629-advantages-liquid-fluoride-thorium-reactor-comparison-light-water-reactor"><span>Advantages of liquid fluoride thorium <span class="hlt">reactor</span> in comparison with light water <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Bahri, Che Nor Aniza Che Zainul, E-mail: anizazainul@gmail.com; Majid, Amran Ab.; Al-Areqi, Wadeeah M.</p> <p>2015-04-29</p> <p>Liquid Fluoride Thorium <span class="hlt">Reactor</span> (LFTR) is an innovative design for the thermal breeder <span class="hlt">reactor</span> that has important potential benefits over the traditional <span class="hlt">reactor</span> design. LFTR is fluoride based liquid fuel, that use the thorium dissolved in salt mixture of lithium fluoride and beryllium fluoride. Therefore, LFTR technology is fundamentally different from the solid fuel technology currently in use. Although the traditional nuclear <span class="hlt">reactor</span> technology has been proven, it has perceptual problems with safety and nuclear waste products. The aim of this paper is to discuss the potential advantages of LFTR in three aspects such as safety, fuel efficiency and nuclearmore » waste as an alternative energy generator in the future. Comparisons between LFTR and Light Water <span class="hlt">Reactor</span> (LWR), on general principles of fuel cycle, resource availability, radiotoxicity and nuclear weapon proliferation shall be elaborated.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/22472357-hybrid-plasmachemical-reactor','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/22472357-hybrid-plasmachemical-reactor"><span>Hybrid plasmachemical <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Lelevkin, V. M., E-mail: lelevkin44@mail.ru; Smirnova, Yu. G.; Tokarev, A. V.</p> <p>2015-04-15</p> <p>A hybrid plasmachemical <span class="hlt">reactor</span> on the basis of a dielectric barrier discharge in a transformer is developed. The characteristics of the <span class="hlt">reactor</span> as functions of the dielectric barrier discharge parameters are determined.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4188938','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4188938"><span>HOMOGENEOUS NUCLEAR POWER <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>King, L.D.P.</p> <p>1959-09-01</p> <p>A homogeneous nuclear power <span class="hlt">reactor</span> utilizing forced circulation of the liquid fuel is described. The <span class="hlt">reactor</span> does not require fuel handling outside of the <span class="hlt">reactor</span> vessel during any normal operation including complete shutdown to room temperature, the <span class="hlt">reactor</span> being selfregulating under extreme operating conditions and controlled by the thermal expansion of the liquid fuel. The liquid fuel utilized is a uranium, phosphoric acid, and water solution which requires no gus exhaust system or independent gas recombining system, thereby eliminating the handling of radioiytic gas.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/1991PhyB..174..491R','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/1991PhyB..174..491R"><span>Update on <span class="hlt">reactors</span> and <span class="hlt">reactor</span> instruments in Asia</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Rao, K. R.</p> <p>1991-10-01</p> <p>The 1980s have seen the commissioning of several medium flux (∼10 14 neutrons/cm 2s) research <span class="hlt">reactors</span> in Asia. The <span class="hlt">reactors</span> are based on indigenous design and development in India and China. At Dhruva <span class="hlt">reactor</span> (India), a variety of neutron spectrometers have been established that have provided useful data related to the structure of high- Tc materials, phonon density of states, magnetic moment distributions and micellar aggregation during the last couple of years. Polarised neutron analysis, neutron interferometry and neutron spin echo methods are some of the new techniques under development. The spectrometers and associated automaton, detectors and neutron guides have all been indigenously developed. This paper summarises the developments and on-going activities in Bangladesh, China, India, Indonesia, Korea, Malaysia, the Philippines and Thailand.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/864773','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/864773"><span>Solvent refined coal <span class="hlt">reactor</span> quench system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Thorogood, Robert M.</p> <p>1983-01-01</p> <p>There is described an improved SRC <span class="hlt">reactor</span> quench system using a condensed product which is recycled to the <span class="hlt">reactor</span> and provides cooling by evaporation. In the process, the second and subsequent <span class="hlt">reactors</span> of a series of <span class="hlt">reactors</span> are cooled by the addition of a light oil fraction which provides cooling by evaporation in the <span class="hlt">reactor</span>. The vaporized quench liquid is recondensed from the <span class="hlt">reactor</span> outlet vapor stream.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/7159530','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/7159530"><span>Solvent refined coal <span class="hlt">reactor</span> quench system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Thorogood, R.M.</p> <p>1983-11-08</p> <p>There is described an improved SRC <span class="hlt">reactor</span> quench system using a condensed product which is recycled to the <span class="hlt">reactor</span> and provides cooling by evaporation. In the process, the second and subsequent <span class="hlt">reactors</span> of a series of <span class="hlt">reactors</span> are cooled by the addition of a light oil fraction which provides cooling by evaporation in the <span class="hlt">reactor</span>. The vaporized quench liquid is recondensed from the <span class="hlt">reactor</span> outlet vapor stream. 1 fig.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4786727','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4786727"><span><span class="hlt">REACTOR</span> FUEL SCAVENGING MEANS</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Coffinberry, A.S.</p> <p>1962-04-10</p> <p>A process for removing fission products from <span class="hlt">reactor</span> liquid fuel without interfering with the <span class="hlt">reactor</span>'s normal operation or causing a significant change in its fuel composition is described. The process consists of mixing a liquid scavenger alloy composed of about 44 at.% plutoniunm, 33 at.% lanthanum, and 23 at.% nickel or cobalt with a plutonium alloy <span class="hlt">reactor</span> fuel containing about 3 at.% lanthanum; removing a portion of the fuel and scavenger alloy from the <span class="hlt">reactor</span> core and replacing it with an equal amount of the fresh scavenger alloy; transferring the portion to a quiescent zone where the scavenger and the plutonium fuel form two distinct liquid layers with the fission products being dissolved in the lanthanum-rich scavenger layer; and the clean plutonium-rich fuel layer being returned to the <span class="hlt">reactor</span> core. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/1033143-reactor-produced-medical-radionuclides','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/1033143-reactor-produced-medical-radionuclides"><span><span class="hlt">Reactor</span>-Produced Medical Radionuclides</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Mirzadeh, Saed; Mausner, Leonard; Garland, Marc A</p> <p>2011-01-01</p> <p>The therapeutic use of radionuclides in nuclear medicine, oncology and cardiology is the most rapidly growing use of medical radionuclides. Since most therapeutic radionuclides are neutron rich and decay by beta emission, they are <span class="hlt">reactor</span>-produced. This chapter deals mainly with production approaches with neutrons. Neutron interactions with matter, neutron transmission and activation rates, and neutron spectra of nuclear <span class="hlt">reactors</span> are discussed in some detail. Further, a short discussion of the neutron-energy dependence of cross sections, reaction rates in thermal <span class="hlt">reactors</span>, cross section measurements and flux monitoring, and general equations governing the <span class="hlt">reactor</span> production of radionuclides are presented. Finally, the chaptermore » is concluded by providing a number of examples encompassing the various possible reaction routes for production of a number of medical radionuclides in a <span class="hlt">reactor</span>.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4321416','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4321416"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Metcalf, H.E.</p> <p>1957-10-01</p> <p>A <span class="hlt">reactor</span> of the type which preferably uses plutonium as the fuel and a liquid moderator, preferably ordinary water, and which produces steam within the <span class="hlt">reactor</span> core due to the heat of the chain reaction is described. In the <span class="hlt">reactor</span> shown the fuel elements are essentially in the form of trays and are ventically stacked in spaced relationship. The water moderator is continuously supplied to the trays to maintain a constant level on the upper surfaces of the fuel element as it is continually evaporated by the heat. The steam passes out through the spaces between the fuel elements and is drawn off at the top of the core. The fuel elements are clad in aluminum to prevent deterioration thereof with consequent contamimation of the water.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4795388','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4795388"><span><span class="hlt">REACTOR</span> CONTROL</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Fortescue, P.; Nicoll, D.</p> <p>1962-04-24</p> <p>A control system employed with a high pressure gas cooled <span class="hlt">reactor</span> in which a control rod is positioned for upward and downward movement into the neutron field from a position beneath the <span class="hlt">reactor</span> is described. The control rod is positioned by a coupled piston cylinder releasably coupled to a power drive means and the pressurized coolant is directed against the lower side of the piston. The coolant pressure is offset by a higher fiuid pressure applied to the upper surface of the piston and means are provided for releasing the higher pressure on the upper side of the piston so that the pressure of the coolant drives the piston upwardly, forcing the coupled control rod into the ncutron field of the <span class="hlt">reactor</span>. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4170745','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4170745"><span>NUCLEAR <span class="hlt">REACTOR</span> CONTROL SYSTEM</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Epler, E.P.; Hanauer, S.H.; Oakes, L.C.</p> <p>1959-11-01</p> <p>A control system is described for a nuclear <span class="hlt">reactor</span> using enriched uranium fuel of the type of the swimming pool and other heterogeneous nuclear <span class="hlt">reactors</span>. Circuits are included for automatically removing and inserting the control rods during the course of normal operation. Appropriate safety circuits close down the nuclear <span class="hlt">reactor</span> in the event of emergency.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6617445','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/6617445"><span><span class="hlt">Reactor</span> vessel support system. [LMFBR</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Golden, M.P.; Holley, J.C.</p> <p>1980-05-09</p> <p>A <span class="hlt">reactor</span> vessel support system includes a support ring at the <span class="hlt">reactor</span> top supported through a box ring on a ledge of the <span class="hlt">reactor</span> containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the <span class="hlt">reactor</span> vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the <span class="hlt">reactor</span> vessel and support ledge into the containment space.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/868938','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/868938"><span>Attrition <span class="hlt">reactor</span> system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Scott, Charles D.; Davison, Brian H.</p> <p>1993-01-01</p> <p>A <span class="hlt">reactor</span> vessel for reacting a solid particulate with a liquid reactant has a centrifugal pump in circulatory flow communication with the <span class="hlt">reactor</span> vessel for providing particulate attrition, resulting in additional fresh surface where the reaction can occur.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1016354','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1016354"><span>Microfluidic electrochemical <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Nuzzo, Ralph G [Champaign, IL; Mitrovski, Svetlana M [Urbana, IL</p> <p>2011-03-22</p> <p>A microfluidic electrochemical <span class="hlt">reactor</span> includes an electrode and one or more microfluidic channels on the electrode, where the microfluidic channels are covered with a membrane containing a gas permeable polymer. The distance between the electrode and the membrane is less than 500 micrometers. The microfluidic electrochemical <span class="hlt">reactor</span> can provide for increased reaction rates in electrochemical reactions using a gaseous reactant, as compared to conventional electrochemical cells. Microfluidic electrochemical <span class="hlt">reactors</span> can be incorporated into devices for applications such as fuel cells, electrochemical analysis, microfluidic actuation, pH gradient formation.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4169015','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4169015"><span><span class="hlt">REACTOR</span> CONTROL SYSTEM</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>MacNeill, J.H.; Estabrook, J.Y.</p> <p>1960-05-10</p> <p>A <span class="hlt">reactor</span> control system including a continuous tape passing through a first coolant passageway, over idler rollers, back through another parallel passageway, and over motor-driven rollers is described. Discrete portions of fuel or poison are carried on two opposed active sections of the tape. Driving the tape in forward or reverse directions causes both active sections to be simultaneously inserted or withdrawn uniformly, tending to maintain a more uniform flux within the <span class="hlt">reactor</span>. The system is particularly useful in mobile <span class="hlt">reactors</span>, where reduced inertial resistance to control rod movement is important.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4282238','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4282238"><span>NEUTRONIC <span class="hlt">REACTOR</span> CONTROL</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Metcalf, H.E.</p> <p>1958-10-14</p> <p>Methods of controlling <span class="hlt">reactors</span> are presented. Specifically, a plurality of neutron absorber members are adjustably disposed in the <span class="hlt">reactor</span> core at different distances from the center thereof. The absorber members extend into the core from opposite faces thereof and are operated by motive means coupled in a manner to simultaneously withdraw at least one of the absorber members while inserting one of the other absorber members. This feature effects fine control of the neutron reproduction ratio by varying the total volume of the <span class="hlt">reactor</span> effective in developing the neutronic reaction.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/567620','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/567620"><span>Status of French <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Ballagny, A.</p> <p>1997-08-01</p> <p>The status of French <span class="hlt">reactors</span> is reviewed. The ORPHEE and RHF <span class="hlt">reactors</span> can not be operated with a LEU fuel which would be limited to 4.8 g U/cm{sup 3}. The OSIRIS <span class="hlt">reactor</span> has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 2} fuel is used up, at the end of 1994. The decision to close down the SILOE <span class="hlt">reactor</span> in the near future is not propitious for the start of a conversion process. The REX 2000 <span class="hlt">reactor</span>, which is expected to be commissioned in 2005, will use LEU (exceptmore » if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/17583763','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/17583763"><span>Startup of <span class="hlt">reactors</span> for anoxic ammonium oxidation: experiences from the first full-scale anammox <span class="hlt">reactor</span> in Rotterdam.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>van der Star, Wouter R L; Abma, Wiebe R; Blommers, Dennis; Mulder, Jan-Willem; Tokutomi, Takaaki; Strous, Marc; Picioreanu, Cristian; van Loosdrecht, Mark C M</p> <p>2007-10-01</p> <p>The first full-scale anammox <span class="hlt">reactor</span> in the world was started in Rotterdam (NL). The <span class="hlt">reactor</span> was scaled-up directly from laboratory-scale to full-scale and treats up to 750 kg-N/d. In the initial phase of the startup, anammox conversions could not be identified by traditional methods, but quantitative PCR proved to be a reliable indicator for growth of the anammox population, indicating an anammox doubling time of 10-12 days. The experience gained during this first startup in combination with the availability of seed sludge from this <span class="hlt">reactor</span>, will lead to a faster startup of anammox <span class="hlt">reactors</span> in the future. The anammox <span class="hlt">reactor</span> type employed in Rotterdam was compared to other <span class="hlt">reactor</span> types for the anammox process. <span class="hlt">Reactors</span> with a high specific surface area like the granular sludge <span class="hlt">reactor</span> employed in Rotterdam provide the highest volumetric loading rates. Mass transfer of nitrite into the biofilm is limiting the conversion of those <span class="hlt">reactor</span> types that have a lower specific surface area. Now the first full-scale commercial anammox <span class="hlt">reactor</span> is in operation, a consistent and descriptive nomenclature is suggested for <span class="hlt">reactors</span> in which the anammox process is employed.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4091940','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4091940"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Breden, C.R.; Dietrich, J.R.</p> <p>1961-06-20</p> <p>A water-soluble non-volatile poison may be introduced into a <span class="hlt">reactor</span> to nullify excess reactivity. The poison is removed by passing a side stream of the water containing the soluble poison to an evaporation chamber. The vapor phase is returned to the <span class="hlt">reactor</span> to decrease the concentration of soluble poison and the liquid phase is returned to increase the concentration of soluble poison.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5302131','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/5302131"><span>Attrition <span class="hlt">reactor</span> system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Scott, C.D.; Davison, B.H.</p> <p>1993-09-28</p> <p>A <span class="hlt">reactor</span> vessel for reacting a solid particulate with a liquid reactant has a centrifugal pump in circulatory flow communication with the <span class="hlt">reactor</span> vessel for providing particulate attrition, resulting in additional fresh surface where the reaction can occur. 2 figures.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_5");'>5</a></li> <li><a href="#" onclick='return showDiv("page_6");'>6</a></li> <li class="active"><span>7</span></li> <li><a href="#" onclick='return showDiv("page_8");'>8</a></li> <li><a href="#" onclick='return showDiv("page_9");'>9</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_7 --> <div id="page_8" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_6");'>6</a></li> <li><a href="#" onclick='return showDiv("page_7");'>7</a></li> <li class="active"><span>8</span></li> <li><a href="#" onclick='return showDiv("page_9");'>9</a></li> <li><a href="#" onclick='return showDiv("page_10");'>10</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="141"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/4620873','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/4620873"><span><span class="hlt">REACTOR</span> PHYSICS CONSTANTS</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>None</p> <p>1963-07-01</p> <p>This second edition is based on data available on March 15, 1961. Sections on constants necessary for the interpretation of experimental data and on digital computer programs for <span class="hlt">reactor</span> design and <span class="hlt">reactor</span> physics have been added. 1344 references. (D.C.W.)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2013AGUFMOS12B..03J','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2013AGUFMOS12B..03J"><span>Scientific Discoveries in the Central Arctic Ocean Based on Seafloor Mapping Carried out to Support Article 76 Extended Continental Shelf Claims (Invited)</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Jakobsson, M.; Mayer, L. A.; Marcussen, C.</p> <p>2013-12-01</p> <p>Despite the last decades of diminishing sea-ice cover in the Arctic Ocean, ship operations are only possible in vast sectors of the central Arctic using the most capable polar-class <span class="hlt">icebreakers</span>. There are less than a handful of these <span class="hlt">icebreakers</span> outfitted with modern seafloor mapping equipment. This implies either fierce competition between those having an interest in using these <span class="hlt">icebreakers</span> for investigations of the shape and properties of Arctic Ocean seafloor or, preferably, collaboration. In this presentation examples will be shown of scientific discoveries based on mapping data collected during Arctic Ocean <span class="hlt">icebreaker</span> expeditions carried out for the purpose of substantiating claims for an extended continental shelf under United Nations Convention of the Law of the Sea (UNCLOS) Article 76. Scientific results will be presented from the suite of Lomonosov Ridge off Greenland (LOMROG) expeditions (2007, 2009, and 2012), shedding new light on Arctic Ocean oceanography and glacial history. The Swedish <span class="hlt">icebreaker</span> Oden was used in collaboration between Sweden and Denmark during LOMROG to map and sample portions of the central Arctic Ocean; specifically focused on the Lomonosov Ridge north of Greenland. While the main objective of the Danish participation was seafloor and sub-seabed mapping to substantiate their Article 76 claim, LOMROG also included several scientific components, with scientists from both countries involved. Other examples to be presented are based on data collected using US Coast Guard Cutter Healy, which for several years has carried out mapping in the western Arctic Ocean for the US continental shelf program. All bathymetric data collected with Oden and Healy have been contributed to the International Bathymetric Chart of the Arctic Ocean (IBCAO). This is also the case for bathymetric data collected by Canadian Coast Guard Ship Louis S. St-Laurent for Canada's extended continental shelf claim. Together, the bathymetric data collected during these</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/869869','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/869869"><span>Improved vortex <span class="hlt">reactor</span> system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Diebold, James P.; Scahill, John W.</p> <p>1995-01-01</p> <p>An improved vortex <span class="hlt">reactor</span> system for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex <span class="hlt">reactor</span> having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2011NuPhS.217..134B','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2011NuPhS.217..134B"><span><span class="hlt">Reactor</span> monitoring using antineutrino detectors</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Bowden, N. S.</p> <p>2011-08-01</p> <p>Nuclear <span class="hlt">reactors</span> have served as the antineutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a <span class="hlt">reactor</span> carries information about two quantities of interest for safeguards: the <span class="hlt">reactor</span> power and fissile inventory. Measurements made with antineutrino detectors could therefore offer an alternative means for verifying the power history and fissile inventory of a <span class="hlt">reactor</span> as part of International Atomic Energy Agency (IAEA) and/or other <span class="hlt">reactor</span> safeguards regimes. Several efforts to develop this monitoring technique are underway worldwide.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/292702','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/292702"><span>Use of {sup 59}Ni, {sup 99}Tc, and {sup 236}U to monitor the release of radionuclides from objects containing spent nuclear fuel dumped in the Kara Sea</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Mount, M.E.; Layton, D.W.; Lynn, N.M.</p> <p>1998-04-01</p> <p>Between 1965 and 1981, five objects - six naval <span class="hlt">reactor</span> pressure vessels (RPVs) from four former Soviet Union submarines and a special containers from the <span class="hlt">icebreaker</span> Lenin, each of which contained damaged spent nuclear fuel (SNF) - were dumped in a variety of containments, using a number of sealing methods, at four sites in the Kara Sea. All objects were dumped at sites that varied in depth from 12 to 300 m. This paper examines the use of the long-lived radionuclides {sup 59}Ni, {sup 99}Tc, and {sup 236}U encased within these objects to monitor the breakdown of the containments duemore » to corrosion. Included are discussions of the radionuclide inventory and their release rate model, the estimated radionuclide mass in a typical seawater sample, and the potential for radionuclide measurement via Accelerator Mass Spectrometry (AMS).« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/46290','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/46290"><span>Improved vortex <span class="hlt">reactor</span> system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Diebold, J.P.; Scahill, J.W.</p> <p>1995-05-09</p> <p>An improved vortex <span class="hlt">reactor</span> system is described for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex <span class="hlt">reactor</span> having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said <span class="hlt">reactor</span>. 12 figs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1176652','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1176652"><span>High solids fermentation <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wyman, Charles E.; Grohmann, Karel; Himmel, Michael E.; Richard, Christopher J.</p> <p>1993-03-02</p> <p>A fermentation <span class="hlt">reactor</span> and method for fermentation of materials having greater than about 10% solids. The <span class="hlt">reactor</span> includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The <span class="hlt">reactor</span> and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/875154','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/875154"><span>High solids fermentation <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wyman, Charles E.; Grohmann, Karel; Himmel, Michael E.; Richard, Christopher J.</p> <p>1993-01-01</p> <p>A fermentation <span class="hlt">reactor</span> and method for fermentation of materials having greater than about 10% solids. The <span class="hlt">reactor</span> includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The <span class="hlt">reactor</span> and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017JCrGr.469...31X','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017JCrGr.469...31X"><span>Morphological evolution of copper nanoparticles: Microemulsion <span class="hlt">reactor</span> system versus batch <span class="hlt">reactor</span> system</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Xia, Ming; Tang, Zengmin; Kim, Woo-Sik; Yu, Taekyung; Park, Bum Jun</p> <p>2017-07-01</p> <p>In the synthesis of nanoparticles, the reaction rate is important to determine the morphology of nanoparticles. We investigated morphology evolution of Cu nanoparticles in this two different <span class="hlt">reactors</span>, microemulsion <span class="hlt">reactor</span> and batch <span class="hlt">reactor</span>. In comparison with the batch <span class="hlt">reactor</span> system, the enhanced mass and heat transfers in the emulsion system likely led to the relatively short nucleation time and the highly homogeneous environment in the reaction mixture, resulting in suppressing one or two dimensional growth of the nanoparticles. We believe that this work can offer a good model system to quantitatively understand the crystal growth mechanism that depends strongly on the local monomer concentration, the efficiency of heat transfer, and the relative contribution of the counter ions (Br- and Cl-) as capping agents.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://eric.ed.gov/?q=polymerization&pg=3&id=EJ362796','ERIC'); return false;" href="https://eric.ed.gov/?q=polymerization&pg=3&id=EJ362796"><span>Polymerization <span class="hlt">Reactor</span> Engineering.</span></a></p> <p><a target="_blank" href="http://www.eric.ed.gov/ERICWebPortal/search/extended.jsp?_pageLabel=advanced">ERIC Educational Resources Information Center</a></p> <p>Skaates, J. Michael</p> <p>1987-01-01</p> <p>Describes a polymerization <span class="hlt">reactor</span> engineering course offered at Michigan Technological University which focuses on the design and operation of industrial polymerization <span class="hlt">reactors</span> to achieve a desired degree of polymerization and molecular weight distribution. Provides a list of the course topics and assigned readings. (TW)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4169533','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4169533"><span>NEUTRONIC <span class="hlt">REACTOR</span> CONTROL</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hurwitz, H. Jr.</p> <p>1960-04-01</p> <p>An apparatus is described for indicating the approach to prompt criticality of a neutronic <span class="hlt">reactor</span> and comprises means for oscillating an absorber in the <span class="hlt">reactor</span>, a detector for measuring neutron flux in the <span class="hlt">reactor</span>, two channels into which the output of the detector can be directed, one of which includes a narrow band filter with band pass frequency equal to that of the oscillator, and means for indicating the ratio of the signal produced by the channel with the filter to the signal produced by the other channel, which constitutes an indication of the approach to prompt criticality.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4287212','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4287212"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Christy, R.F.</p> <p>1958-07-15</p> <p>A nuclear <span class="hlt">reactor</span> of the homogeneous liquid fuel type is described wherein the fissionable isotope is suspended or dissolved in a liquid moderator such as water. The <span class="hlt">reactor</span> core is comprised essentially of a spherical vessel for containing the reactive composition surrounded by a reflector, preferably of beryllium oxide. The reactive composition may be an ordinary water solution of a soluble salt of uranium, the quantity of fissionable isotope in solution being sufficient to provide a critical mass in the vessel. The liquid fuel is stored in a tank of non-crtttcal geometry below the <span class="hlt">reactor</span> vessel and outside of the reflector and is passed from the tank to the vessel through a pipe connecting the two by air pressure means. Neutron absorbing control and safety rods are operated within slots in the reflector adjacent to the vessel.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/869230','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/869230"><span>Nuclear <span class="hlt">reactor</span> building</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Gou, Perng-Fei; Townsend, Harold E.; Barbanti, Giancarlo</p> <p>1994-01-01</p> <p>A <span class="hlt">reactor</span> building for enclosing a nuclear <span class="hlt">reactor</span> includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed thereabove. The wetwell and containment vessel define a drywell surrounding the <span class="hlt">reactor</span>. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the <span class="hlt">reactor</span> during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define therebetween an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.congress.gov/bill/111th-congress/house-bill/1747?q=%7B%22search%22%3A%5B%22coal%22%5D%7D&r=59','CONGRESS-111'); return false;" href="https://www.congress.gov/bill/111th-congress/house-bill/1747?q=%7B%22search%22%3A%5B%22coal%22%5D%7D&r=59"><span>Great Lakes <span class="hlt">Icebreaker</span> Replacement Act</span></a></p> <p><a target="_blank" href="http://thomas.loc.gov/home/LegislativeData.php?&n=BSS&c=111">THOMAS, 111th Congress</a></p> <p>Rep. Oberstar, James L. [D-MN-8</p> <p>2009-03-26</p> <p>House - 10/23/2009 Provisions of measure incorporated in to Title IV of H.R. 3619. (All Actions) Notes: For further action, see H.R.3619, which became Public Law 111-281 on 10/15/2010. Tracker: This bill has the status Passed HouseHere are the steps for Status of Legislation:</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.congress.gov/bill/111th-congress/senate-bill/1024?q=%7B%22search%22%3A%5B%22coal%22%5D%7D&r=66','CONGRESS-111'); return false;" href="https://www.congress.gov/bill/111th-congress/senate-bill/1024?q=%7B%22search%22%3A%5B%22coal%22%5D%7D&r=66"><span>Great Lakes <span class="hlt">Icebreaker</span> Replacement Act</span></a></p> <p><a target="_blank" href="http://thomas.loc.gov/home/LegislativeData.php?&n=BSS&c=111">THOMAS, 111th Congress</a></p> <p>Sen. Levin, Carl [D-MI</p> <p>2009-05-12</p> <p>Senate - 05/12/2009 Read twice and referred to the Committee on Commerce, Science, and Transportation. (All Actions) Notes: For further action, see H.R.3619, which became Public Law 111-281 on 10/15/2010. Tracker: This bill has the status IntroducedHere are the steps for Status of Legislation:</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4691997','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4691997"><span>FLOW SYSTEM FOR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Zinn, W.H.</p> <p>1963-06-11</p> <p>A <span class="hlt">reactor</span> is designed with means for terminating the reaction when returning coolant is below a predetermined temperature. Coolant flowing from the <span class="hlt">reactor</span> passes through a heat exchanger to a lower reservoir, and then circulates between the lower reservoir and an upper reservoir before being returned to the <span class="hlt">reactor</span>. Means responsive to the temperature of the coolant in the return conduit terminate the chain reaction when the temperature reaches a predetermined minimum value. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4128093','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4128093"><span>SELF-REGULATING BOILING-WATER NUCLEAR <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ransohoff, J.A.; Plawchan, J.D.</p> <p>1960-08-16</p> <p>A boiling-water <span class="hlt">reactor</span> was designed which comprises a pressure vessel containing a mass of water, a <span class="hlt">reactor</span> core submerged within the water, a reflector tank disposed within the <span class="hlt">reactor</span>, the reflector tank being open at the top to the interior of the pressure vessel, and a surge tank connected to the reflector tank. In operation the reflector level changes as a function of the pressure witoin the <span class="hlt">reactor</span> so that the reactivity of the <span class="hlt">reactor</span> is automatically controlled.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/869347','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/869347"><span>Nuclear <span class="hlt">reactor</span> reflector</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hopkins, Ronald J.; Land, John T.; Misvel, Michael C.</p> <p>1994-01-01</p> <p>A nuclear <span class="hlt">reactor</span> reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for <span class="hlt">reactor</span> fuel rods. Water flows between the reflector and the <span class="hlt">reactor</span> barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/7201801','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/7201801"><span>Nuclear <span class="hlt">reactor</span> reflector</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hopkins, R.J.; Land, J.T.; Misvel, M.C.</p> <p>1994-06-07</p> <p>A nuclear <span class="hlt">reactor</span> reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for <span class="hlt">reactor</span> fuel rods. Water flows between the reflector and the <span class="hlt">reactor</span> barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled. 12 figs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2013AIPA....3e2133M','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2013AIPA....3e2133M"><span>Imaging Fukushima Daiichi <span class="hlt">reactors</span> with muons</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Miyadera, Haruo; Borozdin, Konstantin N.; Greene, Steve J.; Lukić, Zarija; Masuda, Koji; Milner, Edward C.; Morris, Christopher L.; Perry, John O.</p> <p>2013-05-01</p> <p>A study of imaging the Fukushima Daiichi <span class="hlt">reactors</span> with cosmic-ray muons to assess the damage to the <span class="hlt">reactors</span> is presented. Muon scattering imaging has high sensitivity for detecting uranium fuel and debris even through thick concrete walls and a <span class="hlt">reactor</span> pressure vessel. Technical demonstrations using a <span class="hlt">reactor</span> mockup, detector radiation test at Fukushima Daiichi, and simulation studies have been carried out. These studies establish feasibility for the <span class="hlt">reactor</span> imaging. A few months of measurement will reveal the spatial distribution of the <span class="hlt">reactor</span> fuel. The muon scattering technique would be the best and probably the only way for Fukushima Daiichi to make this determination in the near future.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_6");'>6</a></li> <li><a href="#" onclick='return showDiv("page_7");'>7</a></li> <li class="active"><span>8</span></li> <li><a href="#" onclick='return showDiv("page_9");'>9</a></li> <li><a href="#" onclick='return showDiv("page_10");'>10</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_8 --> <div id="page_9" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_7");'>7</a></li> <li><a href="#" onclick='return showDiv("page_8");'>8</a></li> <li class="active"><span>9</span></li> <li><a href="#" onclick='return showDiv("page_10");'>10</a></li> <li><a href="#" onclick='return showDiv("page_11");'>11</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="161"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4248185','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4248185"><span>NEUTRONIC <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Vernon, H.C.</p> <p>1959-01-13</p> <p>A neutronic <span class="hlt">reactor</span> of the heterogeneous, fluid cooled tvpe is described. The <span class="hlt">reactor</span> is comprised of a pressure vessel containing the moderator and a plurality of vertically disposed channels extending in spaced relationship through the moderator. Fissionable fuel material is placed within the channels in spaced relationship thereto to permit circulation of the coolant fluid. Separate means are provided for cooling the moderator and for circulating a fluid coolant thru the channel elements to cool the fuel material.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4296371','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4296371"><span>NEUTRONIC <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wigner, E.P.; Young, G.J.</p> <p>1958-10-14</p> <p>A method is presented for loading and unloading rod type fuel elements of a neutronic <span class="hlt">reactor</span> of the heterogeneous, solld moderator, liquid cooled type. In the embodiment illustrated, the fuel rods are disposed in vertical coolant channels in the <span class="hlt">reactor</span> core. The fuel rods are loaded and unloaded through the upper openings of the channels which are immersed in the coolant liquid, such as water. Unloading is accomplished by means of a coffer dam assembly having an outer sleeve which is placed in sealing relation around the upper opening. A radiation shield sleeve is disposed in and reciprocable through the coffer dam sleeve. A fuel rod engaging member operates through the axial bore in the radiation shield sleeve to withdraw the fuel rod from its position in the <span class="hlt">reactor</span> coolant channel into the shield, the shield snd rod then being removed. Loading is accomplished in the reverse procedure.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4304461','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4304461"><span>POWER <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Zinn, W.H.</p> <p>1958-07-01</p> <p>A fast nuclear <span class="hlt">reactor</span> system ls described for producing power and radioactive isotopes. The <span class="hlt">reactor</span> core is of the heterogeneous, fluid sealed type comprised of vertically arranged elongated tubular fuel elements having vertical coolant passages. The active portion is surrounded by a neutron reflector and a shield. The system includes pumps and heat exchangers for the primary and secondary coolant circuits. The core, primary coolant pump and primary heat exchanger are disposed within an irapenforate tank which is filled with the primary coolant, in this case a liquid metal such as Na or NaK, to completely submerge these elements. The tank is completely surrounded by a thick walled concrete shield. This <span class="hlt">reactor</span> system utilizes enriched uranium or plutonium as the fissionable material, uranium or thorium as a diluent and thorium or uranium containing less than 0 7% of the U/sup 235/ isotope as a fertile material.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4098409','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4098409"><span><span class="hlt">REACTOR</span>-FLASH BOILER-FLYWHEEL POWER PLANT</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Loeb, E.</p> <p>1961-01-17</p> <p>A power generator in the form of a flywheel with four <span class="hlt">reactors</span> positioned about its rim is described. The <span class="hlt">reactors</span> are so positioned that steam, produced in the <span class="hlt">reactor</span>, exists tangentially to the flywheel, giving it a rotation. The <span class="hlt">reactors</span> are incompletely moderated without water. The water enters the flywheel at its axis, under sufficient pressure to force it through the <span class="hlt">reactors</span>, where it is converted to steam. The fuel consists of parallel twisted ribbons assembled to approximate a cylinder.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4214736','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4214736"><span>NEUTRONIC <span class="hlt">REACTOR</span> CHARGING AND DISCHARGING</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Zinn, W.H.</p> <p>1959-07-14</p> <p>A method and arrangement is presented for removing a fuel element from a neutronic <span class="hlt">reactor</span> tube through which a liquid coolant is being circulaled. The fuel element is moved into a section of the tube beyond the <span class="hlt">reactor</span> proper, and then the coolant in the tube between the fuel element and the <span class="hlt">reactor</span> proper is frozen, so that the fuel element may be removed from the tube without loss of the coolant therein. The method is particularly useful in the case of a liquid metal- cooled <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19780011977','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19780011977"><span>Non-equilibrium radiation nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Thom, K.; Schneider, R. T. (Inventor)</p> <p>1978-01-01</p> <p>An externally moderated thermal nuclear <span class="hlt">reactor</span> is disclosed which is designed to provide output power in the form of electromagnetic radiation. The <span class="hlt">reactor</span> is a gaseous fueled nuclear cavity <span class="hlt">reactor</span> device which can operate over wide ranges of temperature and pressure, and which includes the capability of processing and recycling waste products such as long-lived transuranium actinides. The primary output of the device may be in the form of coherent radiation, so that the <span class="hlt">reactor</span> may be utilized as a self-critical nuclear pumped laser.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2006AIPC..813..932D','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2006AIPC..813..932D"><span>Design of a 25-kWe Surface <span class="hlt">Reactor</span> System Based on SNAP <span class="hlt">Reactor</span> Technologies</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Dixon, David D.; Hiatt, Matthew T.; Poston, David I.; Kapernick, Richard J.</p> <p>2006-01-01</p> <p>A Hastelloy-X clad, sodium-potassium (NaK-78) cooled, moderated spectrum <span class="hlt">reactor</span> using uranium zirconium hydride (UZrH) fuel based on the SNAP program <span class="hlt">reactors</span> is a promising design for use in surface power systems. This paper presents a 98 kWth <span class="hlt">reactor</span> for a power system the uses multiple Stirling engines to produce 25 kWe-net for 5 years. The design utilizes a pin type geometry containing UZrHx fuel clad with Hastelloy-X and NaK-78 flowing around the pins as coolant. A compelling feature of this design is its use of 49.9% enriched U, allowing it to be classified as a category III-D attractiveness and reducing facility costs relative to highly-enriched space <span class="hlt">reactor</span> concepts. Presented below are both the design and an analysis of this <span class="hlt">reactor</span>'s criticality under various safety and operations scenarios.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://files.eric.ed.gov/fulltext/ED054969.pdf','ERIC'); return false;" href="http://files.eric.ed.gov/fulltext/ED054969.pdf"><span>Breeder <span class="hlt">Reactors</span>, Understanding the Atom Series.</span></a></p> <p><a target="_blank" href="http://www.eric.ed.gov/ERICWebPortal/search/extended.jsp?_pageLabel=advanced">ERIC Educational Resources Information Center</a></p> <p>Mitchell, Walter, III; Turner, Stanley E.</p> <p></p> <p>The theory of breeder <span class="hlt">reactors</span> in relationship to a discussion of fission is presented. Different kinds of <span class="hlt">reactors</span> are characterized by the cooling fluids used, such as liquid metal, gas, and molten salt. The historical development of breeder <span class="hlt">reactors</span> over the past twenty-five years includes specific examples of <span class="hlt">reactors</span>. The location and a brief…</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/22118524-imaging-fukushima-daiichi-reactors-muons','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/22118524-imaging-fukushima-daiichi-reactors-muons"><span>Imaging Fukushima Daiichi <span class="hlt">reactors</span> with muons</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Miyadera, Haruo; Borozdin, Konstantin N.; Greene, Steve J.</p> <p>2013-05-15</p> <p>A study of imaging the Fukushima Daiichi <span class="hlt">reactors</span> with cosmic-ray muons to assess the damage to the <span class="hlt">reactors</span> is presented. Muon scattering imaging has high sensitivity for detecting uranium fuel and debris even through thick concrete walls and a <span class="hlt">reactor</span> pressure vessel. Technical demonstrations using a <span class="hlt">reactor</span> mockup, detector radiation test at Fukushima Daiichi, and simulation studies have been carried out. These studies establish feasibility for the <span class="hlt">reactor</span> imaging. A few months of measurement will reveal the spatial distribution of the <span class="hlt">reactor</span> fuel. The muon scattering technique would be the best and probably the only way for Fukushima Daiichi tomore » make this determination in the near future.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19730037999&hterms=Mason&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAuthor-Name%26N%3D0%26No%3D40%26Ntt%3DS%2BJ%2BMason','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19730037999&hterms=Mason&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAuthor-Name%26N%3D0%26No%3D40%26Ntt%3DS%2BJ%2BMason"><span>Zirconium Hydride Space Power <span class="hlt">Reactor</span> design.</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Asquith, J. G.; Mason, D. G.; Stamp, S.</p> <p>1972-01-01</p> <p>The Zirconium Hydride Space Power <span class="hlt">Reactor</span> being designed and fabricated at Atomics International is intended for a wide range of potential applications. Throughout the program a series of <span class="hlt">reactor</span> designs have been evaluated to establish the unique requirements imposed by coupling with various power conversion systems and for specific applications. Current design and development emphasis is upon a 100 kilowatt thermal <span class="hlt">reactor</span> for application in a 5 kwe thermoelectric space power generating system, which is scheduled to be fabricated and ground tested in the mid 70s. The <span class="hlt">reactor</span> design considerations reviewed in this paper will be discussed in the context of this 100 kwt <span class="hlt">reactor</span> and a 300 kwt <span class="hlt">reactor</span> previously designed for larger power demand applications.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4715958','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4715958"><span><span class="hlt">REACTOR</span> FUEL ELEMENTS TESTING CONTAINER</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Whitham, G.K.; Smith, R.R.</p> <p>1963-01-15</p> <p>This patent shows a method for detecting leaks in jacketed fuel elements. The element is placed in a sealed tank within a nuclear <span class="hlt">reactor</span>, and, while the <span class="hlt">reactor</span> operates, the element is sparged with gas. The gas is then led outside the <span class="hlt">reactor</span> and monitored for radioactive Xe or Kr. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2012AGUFM.C13E0664H','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2012AGUFM.C13E0664H"><span>FRAM-2012: Norwegians return to the High Arctic with a Hovercraft for Marine Geophysical Research</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Hall, J. K.; Kristoffersen, Y.; Brekke, H.; Hope, G.</p> <p>2012-12-01</p> <p>After four years of testing methods, craft reliability, and innovative equipment, the R/H SABVABAA has embarked on its first FRAM-201x expedition to the highest Arctic. Named after the Inupiaq word for 'flows swiftly over it', the 12m by 6m hovercraft has been home-based in Longyearbyen, Svalbard since June 2008. In this, its fifth summer of work on the ice pack north of 81N, the craft is supported by the Norwegian Petroleum Directorate (NPD) via the Nansen Environmental and Remote Sensing Center (NERSC) in Bergen, and the Norwegian Scientific Academy for Polar Research. FRAM-2012 represents renewed Norwegian interest in returning to the highest Arctic some 116 years after the 1893-96 drift of Fridtjof Nansen's ship FRAM, the first serious scientific investigation of the Arctic. When replenished by air or <span class="hlt">icebreaker</span>, the hovercraft Sabvabaa offers a hospitable scientific platform with crew of two, capable of marine geophysical, geological and oceanographic observations over long periods with relative mobility on the ice pack. FRAM-2012 is the first step towards this goal, accompanying the Swedish <span class="hlt">icebreaker</span> ODEN to the Lomonosov Ridge, north of Greenland, as part of the LOMROG III expedition. The science plan called for an initial drive from the ice edge to Gakkel Ridge at 85N where micro-earthquakes would be monitored, and then to continue north to a geological sampling area on the Lomonosov Ridge at about 88N, 65W. The micro-earthquake monitoring is part of Gaute Hope's MSc thesis and entails five hydrophones in a WiFi-connected hydrophone array deployed over the Gakkel Rift Valley, drifting with the ice at up to 0.4 knots. On August 3 the hovercraft was refueled from <span class="hlt">icebreaker</span> ODEN at 84-21'N and both vessels proceeded north. The progress of the hovercraft was hampered by insufficient visibility for safe driving and time consuming maneuvering in and around larger fields of rubble ice impassable by the hovercraft, but of little concern to the <span class="hlt">icebreaker</span>. It</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5128482','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/5128482"><span>Nuclear <span class="hlt">reactor</span> building</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Gou, P.F.; Townsend, H.E.; Barbanti, G.</p> <p>1994-04-05</p> <p>A <span class="hlt">reactor</span> building for enclosing a nuclear <span class="hlt">reactor</span> includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed there above. The wetwell and containment vessel define a drywell surrounding the <span class="hlt">reactor</span>. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the <span class="hlt">reactor</span> during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define there between an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin. 4 figures.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4106993','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4106993"><span>WATER BOILER <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>King, L.D.P.</p> <p>1960-11-22</p> <p>As its name implies, this <span class="hlt">reactor</span> utilizes an aqueous solution of a fissionable element salt, and is also conventional in that it contains a heat exchanger cooling coil immersed in the fuel. Its novelty lies in the utilization of a cylindrical <span class="hlt">reactor</span> vessel to provide a critical region having a large and constant interface with a supernatant vapor region, and the use of a hollow sleeve coolant member suspended from the cover assembly in coaxial relation with the <span class="hlt">reactor</span> vessel. Cool water is circulated inside this hollow coolant member, and a gap between its outer wall and the <span class="hlt">reactor</span> vessel is used to carry off radiolytic gases for recombination in an external catalyst chamber. The central passage of the coolant member defines a reflux condenser passage into which the externally recombined gases are returned and condensed. The large and constant interface between fuel solution and vapor region prevents the formation of large bubbles and minimizes the amount of fuel salt carried off by water vapor, thus making possible higher flux densities, specific powers and power densities.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4325452','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4325452"><span>COOLED NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Binner, C.R.; Wilkie, C.B.</p> <p>1958-03-18</p> <p>This patent relates to a design for a <span class="hlt">reactor</span> of the type in which a fluid coolant is flowed through the active portion of the <span class="hlt">reactor</span>. This design provides for the cooling of the shielding material as well as the <span class="hlt">reactor</span> core by the same fluid coolant. The core structure is a solid moderator having coolant channels in which are disposed the fuel elements in rod or slug form. The coolant fluid enters the chamber in the shield, in which the core is located, passes over the inner surface of said chamber, enters the core structure at the center, passes through the coolant channels over the fuel elements and out through exhaust ducts.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.loc.gov/pictures/collection/hh/item/id0445.photos.224344p/','SCIGOV-HHH'); return false;" href="https://www.loc.gov/pictures/collection/hh/item/id0445.photos.224344p/"><span>PBF <span class="hlt">Reactor</span> Building (PER620). <span class="hlt">Reactor</span> vessel arrives from gate city ...</span></a></p> <p><a target="_blank" href="http://www.loc.gov/pictures/collection/hh/">Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey</a></p> <p></p> <p></p> <p>PBF <span class="hlt">Reactor</span> Building (PER-620). <span class="hlt">Reactor</span> vessel arrives from gate city steel at door of PBF. On flatbed, it is too high to fit under door. Photographer: Larry Page. Date: February 13, 1970. INEEL negative no. 70-737 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/7155480','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/7155480"><span>Shutdown system for a nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Groh, E.F.; Olson, A.P.; Wade, D.C.; Robinson, B.W.</p> <p>1984-06-05</p> <p>An ultimate shutdown system is provided for termination of neutronic activity in a nuclear <span class="hlt">reactor</span>. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for <span class="hlt">reactor</span> poison material. The bead chains, normally suspended above the <span class="hlt">reactor</span> core on storage spools, are released for downward travel upon command from an external <span class="hlt">reactor</span> monitor. The chains are capable of horizontal movement, so as to flow around obstructions in the <span class="hlt">reactor</span> during their downward motion. 8 figs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/865030','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/865030"><span>Shutdown system for a nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Groh, Edward F.; Olson, Arne P.; Wade, David C.; Robinson, Bryan W.</p> <p>1984-01-01</p> <p>An ultimate shutdown system is provided for termination of neutronic activity in a nuclear <span class="hlt">reactor</span>. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for <span class="hlt">reactor</span> poison material. The bead chains, normally suspended above the <span class="hlt">reactor</span> core on storage spools, are released for downward travel upon command from an external <span class="hlt">reactor</span> monitor. The chains are capable of horizontal movement, so as to flow around obstructions in the <span class="hlt">reactor</span> during their downward motion.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/862454','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/862454"><span>Control rod drive for <span class="hlt">reactor</span> shutdown</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>McKeehan, Ernest R.; Shawver, Bruce M.; Schiro, Donald J.; Taft, William E.</p> <p>1976-01-20</p> <p>A means for rapidly shutting down or scramming a nuclear <span class="hlt">reactor</span>, such as a liquid metal-cooled fast breeder <span class="hlt">reactor</span>, and serves as a backup to the primary shutdown system. The control rod drive consists basically of an in-core assembly, a drive shaft and seal assembly, and a control drive mechanism. The control rod is driven into the core region of the <span class="hlt">reactor</span> by gravity and hydraulic pressure forces supplied by the <span class="hlt">reactor</span> coolant, thus assuring that common mode failures will not interfere with or prohibit scramming the <span class="hlt">reactor</span> when necessary.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/986479','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/986479"><span>Catalytic <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Aaron, Timothy Mark [East Amherst, NY; Shah, Minish Mahendra [East Amherst, NY; Jibb, Richard John [Amherst, NY</p> <p>2009-03-10</p> <p>A catalytic <span class="hlt">reactor</span> is provided with one or more reaction zones each formed of set(s) of reaction tubes containing a catalyst to promote chemical reaction within a feed stream. The reaction tubes are of helical configuration and are arranged in a substantially coaxial relationship to form a coil-like structure. Heat exchangers and steam generators can be formed by similar tube arrangements. In such manner, the reaction zone(s) and hence, the <span class="hlt">reactor</span> is compact and the pressure drop through components is minimized. The resultant compact form has improved heat transfer characteristics and is far easier to thermally insulate than prior art compact <span class="hlt">reactor</span> designs. Various chemical reactions are contemplated within such coil-like structures such that as steam methane reforming followed by water-gas shift. The coil-like structures can be housed within annular chambers of a cylindrical housing that also provide flow paths for various heat exchange fluids to heat and cool components.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_7");'>7</a></li> <li><a href="#" onclick='return showDiv("page_8");'>8</a></li> <li class="active"><span>9</span></li> <li><a href="#" onclick='return showDiv("page_10");'>10</a></li> <li><a href="#" onclick='return showDiv("page_11");'>11</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_9 --> <div id="page_10" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_8");'>8</a></li> <li><a href="#" onclick='return showDiv("page_9");'>9</a></li> <li class="active"><span>10</span></li> <li><a href="#" onclick='return showDiv("page_11");'>11</a></li> <li><a href="#" onclick='return showDiv("page_12");'>12</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="181"> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/20080004459','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/20080004459"><span><span class="hlt">Reactor</span> for making uniform capsules</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Wang, Taylor G. (Inventor); Anikumar, Amrutur V. (Inventor); Lacik, Igor (Inventor)</p> <p>1999-01-01</p> <p>The present invention provides a novel <span class="hlt">reactor</span> for making capsules with uniform membrane. The <span class="hlt">reactor</span> includes a source for providing a continuous flow of a first liquid through the <span class="hlt">reactor</span>; a source for delivering a steady stream of drops of a second liquid to the entrance of the <span class="hlt">reactor</span>; a main tube portion having at least one loop, and an exit opening, where the exit opening is at a height substantially equal to the entrance. In addition, a method for using the novel <span class="hlt">reactor</span> is provided. This method involves providing a continuous stream of a first liquid; introducing uniformly-sized drops of the second liquid into the stream of the first liquid; allowing the drops to react in the stream for a pre-determined period of time; and collecting the capsules.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/867176','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/867176"><span>Thermionic switched self-actuating <span class="hlt">reactor</span> shutdown system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Barrus, Donald M.; Shires, Charles D.; Brummond, William A.</p> <p>1989-01-01</p> <p>A self-actuating <span class="hlt">reactor</span> shutdown system incorporating a thermionic switched electromagnetic latch arrangement which is responsive to <span class="hlt">reactor</span> neutron flux changes and to <span class="hlt">reactor</span> coolant temperature changes. The system is self-actuating in that the sensing thermionic device acts directly to release (scram) the control rod (absorber) without reference or signal from the main <span class="hlt">reactor</span> plant protective and control systems. To be responsive to both temperature and neutron flux effects, two detectors are used, one responsive to <span class="hlt">reactor</span> coolant temperatures, and the other responsive to <span class="hlt">reactor</span> neutron flux increase. The detectors are incorporated into a thermionic diode connected electrically with an electromagnetic mechanism which under normal <span class="hlt">reactor</span> operating conditions holds the the control rod in its ready position (exterior of the <span class="hlt">reactor</span> core). Upon reaching either a specified temperature or neutron flux, the thermionic diode functions to short-circuit the electromagnetic mechanism causing same to lose its holding power and release the control rod, which drops into the <span class="hlt">reactor</span> core region under gravitational force.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4204380','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4204380"><span>NUCLEAR <span class="hlt">REACTOR</span> FUEL SYSTEMS</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Thamer, B.J.; Bidwell, R.M.; Hammond, R.P.</p> <p>1959-09-15</p> <p>Homogeneous <span class="hlt">reactor</span> fuel solutions are reported which provide automatic recombination of radiolytic gases and exhibit large thermal expansion characteristics, thereby providing stability at high temperatures and enabling <span class="hlt">reactor</span> operation without the necessity of apparatus to recombine gases formed by the radiolytic dissociation of water in the fuel and without the necessity of liquid fuel handling outside the <span class="hlt">reactor</span> vessel except for recovery processes. The fuels consist of phosphoric acid and water solutions of enriched uranium, wherein the uranium is in either the hexavalent or tetravalent state.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.pubmedcentral.nih.gov/articlerender.fcgi?tool=pmcentrez&artid=4423222','PMC'); return false;" href="https://www.pubmedcentral.nih.gov/articlerender.fcgi?tool=pmcentrez&artid=4423222"><span>Neutrino oscillation studies with <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pmc">PubMed Central</a></p> <p>Vogel, P.; Wen, L.J.; Zhang, C.</p> <p>2015-01-01</p> <p>Nuclear <span class="hlt">reactors</span> are one of the most intense, pure, controllable, cost-effective and well-understood sources of neutrinos. <span class="hlt">Reactors</span> have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavours are quantum mechanical mixtures. Over the past several decades, <span class="hlt">reactors</span> were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle θ13. In the near future, <span class="hlt">reactors</span> will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos. PMID:25913819</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/pages/biblio/1177002-neutrino-oscillation-studies-reactors','SCIGOV-DOEP'); return false;" href="https://www.osti.gov/pages/biblio/1177002-neutrino-oscillation-studies-reactors"><span>Neutrino oscillation studies with <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/pages">DOE PAGES</a></p> <p>Vogel, P.; Wen, L.J.; Zhang, C.</p> <p>2015-04-27</p> <p>Nuclear <span class="hlt">reactors</span> are one of the most intense, pure, controllable, cost-effective and well-understood sources of neutrinos. <span class="hlt">Reactors</span> have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavours are quantum mechanical mixtures. Over the past several decades, <span class="hlt">reactors</span> were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle θ 13. In the near future, <span class="hlt">reactors</span> will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/25913819','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/25913819"><span>Neutrino oscillation studies with <span class="hlt">reactors</span>.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Vogel, P; Wen, L J; Zhang, C</p> <p>2015-04-27</p> <p>Nuclear <span class="hlt">reactors</span> are one of the most intense, pure, controllable, cost-effective and well-understood sources of neutrinos. <span class="hlt">Reactors</span> have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavours are quantum mechanical mixtures. Over the past several decades, <span class="hlt">reactors</span> were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle θ13. In the near future, <span class="hlt">reactors</span> will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.eia.gov/nuclear/closures/closure16.pdf','EIAPUBS'); return false;" href="https://www.eia.gov/nuclear/closures/closure16.pdf"><span>When Do Commercial <span class="hlt">Reactors</span> Permanently Shut Down?</span></a></p> <p><a target="_blank" href="http://www.eia.doe.gov/reports/">EIA Publications</a></p> <p></p> <p>2011-01-01</p> <p>For those wishing to obtain current data, the following resources are available: U.S. <span class="hlt">reactors</span>, go to the Energy Information Administration's nuclear <span class="hlt">reactor</span> shutdown list. (Note: As of April 30, 2010, the last U.S. <span class="hlt">reactor</span> to permanently shut down was Big Rock Point in 1997.) Foreign <span class="hlt">Reactors</span>, go to the Power <span class="hlt">Reactor</span> Information System (PRIS) on the International Atomic Energy Agency's website.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/16604724','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/16604724"><span>Transmutation of actinides in power <span class="hlt">reactors</span>.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Bergelson, B R; Gerasimov, A S; Tikhomirov, G V</p> <p>2005-01-01</p> <p>Power <span class="hlt">reactors</span> can be used for partial short-term transmutation of radwaste. This transmutation is beneficial in terms of subsequent storage conditions for spent fuel in long-term storage facilities. CANDU-type <span class="hlt">reactors</span> can transmute the main minor actinides from two or three <span class="hlt">reactors</span> of the VVER-1000 type. A VVER-1000-type <span class="hlt">reactor</span> can operate in a self-service mode with transmutation of its own actinides.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19720027692&hterms=moderation&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D10%26Ntt%3Dmoderation','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19720027692&hterms=moderation&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D10%26Ntt%3Dmoderation"><span>A mini-cavity probe <span class="hlt">reactor</span>.</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Hyland, R. E.</p> <p>1971-01-01</p> <p>The mini-cavity <span class="hlt">reactor</span> is a rocket engine concept which combines the high specific impulse from a central gaseous fueled cavity (0.6 m diam) and NERVA type fuel elements in a driver region that is external to a moderator-reflector zone to produce a compact light weight <span class="hlt">reactor</span>. The overall dimension including a pressure vessel that is located outside of the spherical <span class="hlt">reactor</span> is approximately 1.21 m in diameter. Specific impulses up to 2000 sec are obtainable for 220 to 890 N of thrust with pressures less than 1000 atm. Powerplant weights including a radiator for disposing of the power in the driver region are between 4600 and 32,000 kg - less than payloads of the shuttle. This <span class="hlt">reactor</span> could also be used as a test <span class="hlt">reactor</span> for gas-core, MHD, breeding and materials research.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/871651','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/871651"><span>Self isolating high frequency saturable <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Moore, James A.</p> <p>1998-06-23</p> <p>The present invention discloses a saturable <span class="hlt">reactor</span> and a method for decoupling the interwinding capacitance from the frequency limitations of the <span class="hlt">reactor</span> so that the equivalent electrical circuit of the saturable <span class="hlt">reactor</span> comprises a variable inductor. The saturable <span class="hlt">reactor</span> comprises a plurality of physically symmetrical magnetic cores with closed loop magnetic paths and a novel method of wiring a control winding and a RF winding. The present invention additionally discloses a matching network and method for matching the impedances of a RF generator to a load. The matching network comprises a matching transformer and a saturable <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/20140001436','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/20140001436"><span>Autonomous Control of Space Nuclear <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Merk, John</p> <p>2013-01-01</p> <p>Nuclear <span class="hlt">reactors</span> to support future robotic and manned missions impose new and innovative technological requirements for their control and protection instrumentation. Long-duration surface missions necessitate reliable autonomous operation, and manned missions impose added requirements for failsafe <span class="hlt">reactor</span> protection. There is a need for an advanced instrumentation and control system for space-nuclear <span class="hlt">reactors</span> that addresses both aspects of autonomous operation and safety. The <span class="hlt">Reactor</span> Instrumentation and Control System (RICS) consists of two functionally independent systems: the <span class="hlt">Reactor</span> Protection System (RPS) and the Supervision and Control System (SCS). Through these two systems, the RICS both supervises and controls a nuclear <span class="hlt">reactor</span> during normal operational states, as well as monitors the operation of the <span class="hlt">reactor</span> and, upon sensing a system anomaly, automatically takes the appropriate actions to prevent an unsafe or potentially unsafe condition from occurring. The RPS encompasses all electrical and mechanical devices and circuitry, from sensors to actuation device output terminals. The SCS contains a comprehensive data acquisition system to measure continuously different groups of variables consisting of primary measurement elements, transmitters, or conditioning modules. These <span class="hlt">reactor</span> control variables can be categorized into two groups: those directly related to the behavior of the core (known as nuclear variables) and those related to secondary systems (known as process variables). Reliable closed-loop <span class="hlt">reactor</span> control is achieved by processing the acquired variables and actuating the appropriate device drivers to maintain the <span class="hlt">reactor</span> in a safe operating state. The SCS must prevent a deviation from the <span class="hlt">reactor</span> nominal conditions by managing limitation functions in order to avoid RPS actions. The RICS has four identical redundancies that comply with physical separation, electrical isolation, and functional independence. This architecture complies with the</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19940004536&hterms=fundamentals+operating+system&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D20%26Ntt%3Dfundamentals%2Boperating%2Bsystem','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19940004536&hterms=fundamentals+operating+system&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D20%26Ntt%3Dfundamentals%2Boperating%2Bsystem"><span>Moon base <span class="hlt">reactor</span> system</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Chavez, H.; Flores, J.; Nguyen, M.; Carsen, K.</p> <p>1989-01-01</p> <p>The objective of our <span class="hlt">reactor</span> design is to supply a lunar-based research facility with 20 MW(e). The fundamental layout of this lunar-based system includes the <span class="hlt">reactor</span>, power conversion devices, and a radiator. The additional aim of this <span class="hlt">reactor</span> is a longevity of 12 to 15 years. The <span class="hlt">reactor</span> is a liquid metal fast breeder that has a breeding ratio very close to 1.0. The geometry of the core is cylindrical. The metallic fuel rods are of beryllium oxide enriched with varying degrees of uranium, with a beryllium core reflector. The liquid metal coolant chosen was natural lithium. After the liquid metal coolant leaves the <span class="hlt">reactor</span>, it goes directly into the power conversion devices. The power conversion devices are Stirling engines. The heated coolant acts as a hot reservoir to the device. It then enters the radiator to be cooled and reenters the Stirling engine acting as a cold reservoir. The engines' operating fluid is helium, a highly conductive gas. These Stirling engines are hermetically sealed. Although natural lithium produces a lower breeding ratio, it does have a larger temperature range than sodium. It is also corrosive to steel. This is why the container material must be carefully chosen. One option is to use an expensive alloy of cerbium and zirconium. The radiator must be made of a highly conductive material whose melting point temperature is not exceeded in the <span class="hlt">reactor</span> and whose structural strength can withstand meteor showers.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4178017','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4178017"><span>A NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Luebke, E.A.; Vandenberg, L.B.</p> <p>1959-09-01</p> <p>A nuclear <span class="hlt">reactor</span> for producing thermoelectric power is described. The <span class="hlt">reactor</span> core comprises a series of thermoelectric assemblies, each assembly including fissionable fuel as an active element to form a hot junction and a thermocouple. The assemblies are disposed parallel to each other to form spaces and means are included for Introducing an electrically conductive coolant between the assemblies to form cold junctions of the thermocouples. An electromotive force is developed across the entire series of the thermoelectric assemblies due to fission heat generated in the fuel causing a current to flow perpendicular to the flow of coolant and is distributed to a load outside of the <span class="hlt">reactor</span> by means of bus bars electrically connected to the outermost thermoelectric assembly.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4779760','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4779760"><span><span class="hlt">REACTOR</span> CONTROL DEVICE</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Graham, R.H.</p> <p>1962-09-01</p> <p>A wholly mechanical compact control device is designed for automatically rendering the core of a fission <span class="hlt">reactor</span> subcritical in response to core temperatures in excess of the design operating temperature limit. The control device comprises an expansible bellows interposed between the base of a channel in a <span class="hlt">reactor</span> core and the inner end of a fuel cylinder therein which is normally resiliently urged inwardly. The bellows contains a working fluid which undergoes a liquid to vapor phase change at a temperature substantially equal to the design temperature limit. Hence, the bellows abruptiy expands at this limiting temperature to force the fuel cylinder outward and render the core subcritical. The control device is particularly applicable to aircraft propulsion <span class="hlt">reactor</span> service. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4149111','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4149111"><span>EMERGENCY SHUTDOWN FOR NUCLEAR <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Paget, J.A.; Koutz, S.L.; Stone, R.S.; Stewart, H.B.</p> <p>1963-12-24</p> <p>An emergency shutdown or scram apparatus for use in a nuclear <span class="hlt">reactor</span> that includes a neutron absorber suspended from a temperature responsive substance that is selected to fail at a preselected temperature in excess of the normal <span class="hlt">reactor</span> operating temperature, whereby the neutron absorber is released and allowed to fall under gravity to a preselected position within the <span class="hlt">reactor</span> core is presented. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4724464','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4724464"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Young, G.</p> <p>1963-01-01</p> <p>This patent covers a power-producing nuclear <span class="hlt">reactor</span> in which fuel rods of slightly enriched U are moderated by heavy water and cooled by liquid metal. The fuel rods arranged parallel to one another in a circle are contained in a large outer closed-end conduit that extends into a tank containing the heavy water. Liquid metal is introduced into the large conduit by a small inner conduit that extends within the circle of fuel rods to a point near the lower closed end of the outer conduit. (AEC) Production <span class="hlt">Reactors</span></p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2005AIPC..746.1229C','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2005AIPC..746.1229C"><span>Microchannel <span class="hlt">Reactors</span> for ISRU Applications</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Carranza, Susana; Makel, Darby B.; Blizman, Brandon; Ward, Benjamin J.</p> <p>2005-02-01</p> <p>Affordable planning and execution of prolonged manned space missions depend upon the utilization of local resources and the waste products which are formed in manned spacecraft and surface bases. Successful in-situ resources utilization (ISRU) will require component technologies which provide optimal size, weight, volume, and power efficiency. Microchannel <span class="hlt">reactors</span> enable the efficient chemical processing of in situ resources. The <span class="hlt">reactors</span> can be designed for the processes that generate the most benefit for each mission. For instance, propellants (methane) can be produced from carbon dioxide from the Mars atmosphere using the Sabatier reaction and ethylene can be produced from the partial oxidation of methane. A system that synthesizes ethylene could be the precursor for systems to synthesize ethanol and polyethylene. Ethanol can be used as a nutrient for Astrobiology experiments, as well as the production of nutrients for human crew (e.g. sugars). Polyethylene can be used in the construction of habitats, tools, and replacement parts. This paper will present recent developments in miniature chemical <span class="hlt">reactors</span> using advanced Micro Electro Mechanical Systems (MEMS) and microchannel technology to support ISRU of Mars and lunar missions. Among other applications, the technology has been demonstrated for the Sabatier process and for the partial oxidation of methane. Microchannel <span class="hlt">reactors</span> were developed based on ceramic substrates as well as metal substrates. In both types of <span class="hlt">reactors</span>, multiple layers coated with catalytic material are bonded, forming a monolithic structure. Such <span class="hlt">reactors</span> are readily scalable with the incorporation of extra layers. In addition, this <span class="hlt">reactor</span> structure minimizes pressure drop and catalyst settling, which are common problems in conventional packed bed <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1175624','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1175624"><span>Auxiliary <span class="hlt">reactor</span> for a hydrocarbon reforming system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Clawson, Lawrence G.; Dorson, Matthew H.; Mitchell, William L.; Nowicki, Brian J.; Bentley, Jeffrey M.; Davis, Robert; Rumsey, Jennifer W.</p> <p>2006-01-17</p> <p>An auxiliary <span class="hlt">reactor</span> for use with a reformer <span class="hlt">reactor</span> having at least one reaction zone, and including a burner for burning fuel and creating a heated auxiliary <span class="hlt">reactor</span> gas stream, and heat exchanger for transferring heat from auxiliary <span class="hlt">reactor</span> gas stream and heat transfer medium, preferably two-phase water, to reformer reaction zone. Auxiliary <span class="hlt">reactor</span> may include first cylindrical wall defining a chamber for burning fuel and creating a heated auxiliary <span class="hlt">reactor</span> gas stream, the chamber having an inlet end, an outlet end, a second cylindrical wall surrounding first wall and a second annular chamber there between. The <span class="hlt">reactor</span> being configured so heated auxiliary <span class="hlt">reactor</span> gas flows out the outlet end and into and through second annular chamber and conduit which is disposed in second annular chamber, the conduit adapted to carry heat transfer medium and being connectable to reformer reaction zone for additional heat exchange.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/868498','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/868498"><span>Propellant actuated nuclear <span class="hlt">reactor</span> steam depressurization valve</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ehrke, Alan C.; Knepp, John B.; Skoda, George I.</p> <p>1992-01-01</p> <p>A nuclear fission <span class="hlt">reactor</span> combined with a propellant actuated depressurization and/or water injection valve is disclosed. The depressurization valve releases pressure from a water cooled, steam producing nuclear <span class="hlt">reactor</span> when required to insure the safety of the <span class="hlt">reactor</span>. Depressurization of the <span class="hlt">reactor</span> pressure vessel enables gravity feeding of supplementary coolant water through the water injection valve to the <span class="hlt">reactor</span> pressure vessel to prevent damage to the fuel core.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4814688','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4814688"><span>RADIATION FACILITY FOR NUCLEAR <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Currier, E.L. Jr.; Nicklas, J.H.</p> <p>1961-12-12</p> <p>A radiation facility is designed for irradiating samples in close proximity to the core of a nuclear <span class="hlt">reactor</span>. The facility comprises essentially a tubular member extending through the biological shield of the <span class="hlt">reactor</span> and containing a manipulatable rod having the sample carrier at its inner end, the carrier being longitudinally movable from a position in close proximity to the <span class="hlt">reactor</span> core to a position between the inner and outer faces of the shield. Shield plugs are provided within the tubular member to prevent direct radiation from the core emanating therethrough. In this device, samples may be inserted or removed during normal operation of the <span class="hlt">reactor</span> without exposing personnel to direct radiation from the <span class="hlt">reactor</span> core. A storage chamber is also provided within the radiation facility to contain an irradiated sample during the period of time required to reduce the radioactivity enough to permit removal of the sample for external handling. (AEC)</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_8");'>8</a></li> <li><a href="#" onclick='return showDiv("page_9");'>9</a></li> <li class="active"><span>10</span></li> <li><a href="#" onclick='return showDiv("page_11");'>11</a></li> <li><a href="#" onclick='return showDiv("page_12");'>12</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_10 --> <div id="page_11" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_9");'>9</a></li> <li><a href="#" onclick='return showDiv("page_10");'>10</a></li> <li class="active"><span>11</span></li> <li><a href="#" onclick='return showDiv("page_12");'>12</a></li> <li><a href="#" onclick='return showDiv("page_13");'>13</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="201"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19860036004&hterms=nuclear+power+reactor&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D20%26Ntt%3Dnuclear%2Bpower%2Breactor','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19860036004&hterms=nuclear+power+reactor&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D20%26Ntt%3Dnuclear%2Bpower%2Breactor"><span>Thermionic <span class="hlt">reactors</span> for space nuclear power</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Homeyer, W. G.; Merrill, M. H.; Holland, J. W.; Fisher, C. R.; Allen, D. T.</p> <p>1985-01-01</p> <p>Thermionic <span class="hlt">reactor</span> designs for a variety of space power applications spanning the range from 5 kWe to 3 MWe are described. In all of these <span class="hlt">reactors</span>, nuclear heat is converted directly to electrical energy in thermionic fuel elements (TFEs). A circulating <span class="hlt">reactor</span> coolant carries heat from the core of TFEs directly to a heat rejection radiator system. The recent design of a thermionic <span class="hlt">reactor</span> to meet the SP-100 requirements is emphasized. Design studies of <span class="hlt">reactors</span> at other power levels show that the same TFE can be used over a broad range in power, and that design modifications can extend the range to many megawatts. The design of the SP-100 TFE is similar to that of TFEs operated successfully in test <span class="hlt">reactors</span>, but with design improvements to extend the operating lifetime to seven years.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/868878','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/868878"><span>Fast-acting nuclear <span class="hlt">reactor</span> control device</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Kotlyar, Oleg M.; West, Phillip B.</p> <p>1993-01-01</p> <p>A fast-acting nuclear <span class="hlt">reactor</span> control device for moving and positioning a fety control rod to desired positions within the core of the <span class="hlt">reactor</span> between a run position in which the safety control rod is outside the <span class="hlt">reactor</span> core, and a shutdown position in which the rod is fully inserted in the <span class="hlt">reactor</span> core. The device employs a hydraulic pump/motor, an electric gear motor, and solenoid valve to drive the safety control rod into the <span class="hlt">reactor</span> core through the entire stroke of the safety control rod. An overrunning clutch allows the safety control rod to freely travel toward a safe position in the event of a partial drive system failure.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4333532','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4333532"><span><span class="hlt">REACTOR</span> CONTROL</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ruano, W.J.</p> <p>1957-12-10</p> <p>This patent relates to nuclear <span class="hlt">reactors</span> of the type which utilize elongited rod type fuel elements immersed in a liquid moderator and shows a design whereby control of the chain reaction is obtained by varying the amount of moderator or reflector material. A central tank for containing liquid moderator and fuel elements immersed therein is disposed within a surrounding outer tank providing an annular space between the two tanks. This annular space is filled with liquid moderator which functions as a reflector to reflect neutrons back into the central <span class="hlt">reactor</span> tank to increase the reproduction ratio. Means are provided for circulating and cooling the moderator material in both tanks and additional means are provided for controlling separately the volume of moderator in each tank, which latter means may be operated automatically by a neutron density monitoring device. The patent also shows an arrangement for controlling the chain reaction by injecting and varying an amount of poisoning material in the moderator used in the reflector portion of the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/21064577-iris-spool-type-reactor-coolant-pump','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/21064577-iris-spool-type-reactor-coolant-pump"><span>The IRIS Spool-Type <span class="hlt">Reactor</span> Coolant Pump</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Kujawski, J.M.; Kitch, D.M.; Conway, L.E.</p> <p>2002-07-01</p> <p>IRIS (International <span class="hlt">Reactor</span> Innovative and Secure) is a light water cooled, 335 MWe power <span class="hlt">reactor</span> which is being designed by an international consortium as part of the US DOE NERI Program. IRIS features an integral <span class="hlt">reactor</span> vessel that contains all the major <span class="hlt">reactor</span> coolant system components including the <span class="hlt">reactor</span> core, the coolant pumps, the steam generators and the pressurizer. This integral design approach eliminates the large coolant loop piping, and thus eliminates large loss-of-coolant accidents (LOCAs) as well as the individual component pressure vessels and supports. In addition, IRIS is being designed with a long life core and enhanced safetymore » to address the requirements defined by the US DOE for Generation IV <span class="hlt">reactors</span>. One of the innovative features of the IRIS design is the adoption of a <span class="hlt">reactor</span> coolant pump (called 'spool' pump) which is completely contained inside the <span class="hlt">reactor</span> vessel. Background, status and future developments of the IRIS spool pump are presented in this paper. (authors)« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/21021140-research-program-super-fast-reactor','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/21021140-research-program-super-fast-reactor"><span>Research Program of a Super Fast <span class="hlt">Reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Oka, Yoshiaki; Ishiwatari, Yuki; Liu, Jie</p> <p>2006-07-01</p> <p>Research program of a supercritical-pressure light water cooled fast <span class="hlt">reactor</span> (Super Fast <span class="hlt">Reactor</span>) is funded by MEXT (Ministry of Education, Culture, Sports, Science and Technology) in December 2005 as one of the research programs of Japanese NERI (Nuclear Energy Research Initiative). It consists of three programs. (1) development of Super Fast <span class="hlt">Reactor</span> concept; (2) thermal-hydraulic experiments; (3) material developments. The purpose of the concept development is to pursue the advantage of high power density of fast <span class="hlt">reactor</span> over thermal <span class="hlt">reactors</span> to achieve economic competitiveness of fast <span class="hlt">reactor</span> for its deployment without waiting for exhausting uranium resources. Design goal is notmore » breeding, but maximizing <span class="hlt">reactor</span> power by using plutonium from spent LWR fuel. MOX will be the fuel of the Super Fast <span class="hlt">Reactor</span>. Thermal-hydraulic experiments will be conducted with HCFC22 (Hydro chlorofluorocarbons) heat transfer loop of Kyushu University and supercritical water loop at JAEA. Heat transfer data including effect of grid spacers will be taken. The critical flow and condensation of supercritical fluid will be studied. The materials research includes the development and testing of austenitic stainless steel cladding from the experience of PNC1520 for LMFBR. Material for thermal insulation will be tested. SCWR (Supercritical-Water Cooled <span class="hlt">Reactor</span>) of GIF (Generation-4 International Forum) includes both thermal and fast <span class="hlt">reactors</span>. The research of the Super Fast <span class="hlt">Reactor</span> will enhance SCWR research and the data base. The research period will be until March 2010. (authors)« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2018NucFu..58b6010K','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2018NucFu..58b6010K"><span>Tritium resources available for fusion <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Kovari, M.; Coleman, M.; Cristescu, I.; Smith, R.</p> <p>2018-02-01</p> <p>The tritium required for ITER will be supplied from the CANDU production in Ontario, but while Ontario may be able to supply 8 kg for a DEMO fusion <span class="hlt">reactor</span> in the mid-2050s, it will not be able to provide 10 kg at any realistic starting time. The tritium required to start DEMO will depend on advances in plasma fuelling efficiency, burnup fraction, and tritium processing technology. It is in theory possible to start up a fusion <span class="hlt">reactor</span> with little or no tritium, but at an estimated cost of 2 billion per kilogram of tritium saved, it is not economically sensible. Some heavy water <span class="hlt">reactor</span> tritium production scenarios with varying degrees of optimism are presented, with the assumption that only Canada, the Republic of Korea, and Romania make tritium available to the fusion community. Results for the tritium available for DEMO in 2055 range from zero to 30 kg. CANDU and similar heavy water <span class="hlt">reactors</span> could in theory generate additional tritium in a number of ways: (a) adjuster rods containing lithium could be used, giving 0.13 kg per year per <span class="hlt">reactor</span>; (b) a fuel bundle with a burnable absorber has been designed for CANDU <span class="hlt">reactors</span>, which might be adapted for tritium production; (c) tritium production could be increased by 0.05 kg per year per <span class="hlt">reactor</span> by doping the moderator with lithium-6. If a fusion <span class="hlt">reactor</span> is started up around 2055, governments in Canada, Argentina, China, India, South Korea and Romania will have the opportunity in the years leading up to that to take appropriate steps: (a) build, refurbish or upgrade tritium extraction facilities; (b) extend the lives of heavy water <span class="hlt">reactors</span>, or build new ones; (c) reduce tritium sales; (d) boost tritium production in the remaining heavy water <span class="hlt">reactors</span>. All of the alternative production methods considered have serious economic and regulatory drawbacks, and the risk of diversion of tritium or lithium-6 would also be a major concern. There are likely to be serious problems with supplying tritium for future</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4248815','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4248815"><span>CONTROL FOR NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Lichtenberger, H.V.; Cameron, R.A.</p> <p>1959-03-31</p> <p>S>A control rod operating device in a nuclear <span class="hlt">reactor</span> of the type in which the control rod is gradually withdrawn from the <span class="hlt">reactor</span> to a position desired during stable operation is described. The apparatus is comprised essentially of a stop member movable in the direction of withdrawal of the control rod, a follower on the control rod engageable with the stop and means urging the follower against the stop in the direction of withdrawal. A means responsive to disengagement of the follower from the stop is provided for actuating the control rod to return to the <span class="hlt">reactor</span> shut-down position.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5641672','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/5641672"><span>Spherical torus fusion <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Martin Peng, Y.K.M.</p> <p>1985-10-03</p> <p>The object of this invention is to provide a compact torus fusion <span class="hlt">reactor</span> with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion <span class="hlt">reactor</span> with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion <span class="hlt">reactor</span> in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866717','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866717"><span>Self-actuating <span class="hlt">reactor</span> shutdown system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Barrus, Donald M.; Brummond, Willian A; Peterson, Leslie F.</p> <p>1988-01-01</p> <p>A control system for the automatic or self-actuated shutdown or "scram" of a nuclear <span class="hlt">reactor</span>. The system is capable of initiating scram insertion by a signal from the plant protection system or by independent action directly sensing <span class="hlt">reactor</span> conditions of low-flow or over-power. Self-actuation due to a loss of <span class="hlt">reactor</span> coolant flow results from a decrease of pressure differential between the upper and lower ends of an absorber element. When the force due to this differential falls below the weight of the element, the element will fall by gravitational force to scram the <span class="hlt">reactor</span>. Self-actuation due to high neutron flux is accomplished via a valve controlled by an electromagnet and a thermionic diode. In a <span class="hlt">reactor</span> over-power, the diode will be heated to a change of state causing the electromagnet to be shorted thereby actuating the valve which provides the changed flow and pressure conditions required for scramming the absorber element.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/pages/biblio/1196380-generating-unstructured-nuclear-reactor-core-meshes-parallel','SCIGOV-DOEP'); return false;" href="https://www.osti.gov/pages/biblio/1196380-generating-unstructured-nuclear-reactor-core-meshes-parallel"><span>Generating unstructured nuclear <span class="hlt">reactor</span> core meshes in parallel</span></a></p> <p><a target="_blank" href="http://www.osti.gov/pages">DOE PAGES</a></p> <p>Jain, Rajeev; Tautges, Timothy J.</p> <p>2014-10-24</p> <p>Recent advances in supercomputers and parallel solver techniques have enabled users to run large simulations problems using millions of processors. Techniques for multiphysics nuclear <span class="hlt">reactor</span> core simulations are under active development in several countries. Most of these techniques require large unstructured meshes that can be hard to generate in a standalone desktop computers because of high memory requirements, limited processing power, and other complexities. We have previously reported on a hierarchical lattice-based approach for generating <span class="hlt">reactor</span> core meshes. Here, we describe efforts to exploit coarse-grained parallelism during <span class="hlt">reactor</span> assembly and <span class="hlt">reactor</span> core mesh generation processes. We highlight several <span class="hlt">reactor</span> coremore » examples including a very high temperature <span class="hlt">reactor</span>, a full-core model of the Korean MONJU <span class="hlt">reactor</span>, a ¼ pressurized water <span class="hlt">reactor</span> core, the fast <span class="hlt">reactor</span> Experimental Breeder <span class="hlt">Reactor</span>-II core with a XX09 assembly, and an advanced breeder test <span class="hlt">reactor</span> core. The times required to generate large mesh models, along with speedups obtained from running these problems in parallel, are reported. A graphical user interface to the tools described here has also been developed.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/1440657-assessment-sensor-technologies-advanced-reactors','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/1440657-assessment-sensor-technologies-advanced-reactors"><span>Assessment of Sensor Technologies for Advanced <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Korsah, Kofi; Kisner, R. A.; Britton Jr., C. L.</p> <p></p> <p>This paper provides an assessment of sensor technologies and a determination of measurement needs for advanced <span class="hlt">reactors</span> (AdvRx). It is a summary of a study performed to provide the technical basis for identifying and prioritizing research targets within the instrumentation and control (I&C) Technology Area under the Department of Energy’s (DOE’s) Advanced <span class="hlt">Reactor</span> Technology (ART) program. The study covered two broad <span class="hlt">reactor</span> technology categories: High Temperature <span class="hlt">Reactors</span> and Fast <span class="hlt">Reactors</span>. The scope of “High temperature reactors” included Gen IV <span class="hlt">reactors</span> whose coolant exit temperatures exceed ≈650 °C and are moderated (as opposed to fast <span class="hlt">reactors</span>). To bound the scope formore » fast <span class="hlt">reactors</span>, this report reviewed relevant operating experience from US-operated Sodium Fast <span class="hlt">Reactor</span> (SFR) and relevant test experience from the Fast Flux Test Facility (FFTF). For high temperature <span class="hlt">reactors</span> the study showed that in many cases instrumentation have performed reasonably well in research and demonstration <span class="hlt">reactors</span>. However, even in cases where the technology is “mature” (such as thermocouples), HTGRs can benefit from improved technologies. Current HTGR instrumentation is generally based on decades-old technology and adapting newer technologies could provide significant advantages. For sodium fast <span class="hlt">reactors</span>, the study found that several key research needs arise around (1) radiation-tolerant sensor design for in-vessel or in-core applications, where possible non-invasive sensing approaches for key parameters that minimize the need to deploy sensors in-vessel, (2) approaches to exfiltrating data from in-vessel sensors while minimizing penetrations, (3) calibration of sensors in-situ, and (4) optimizing sensor placements to maximize the information content while minimizing the number of sensors needed.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/645949','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/645949"><span>Fast quench <span class="hlt">reactor</span> and method</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Detering, B.A.; Donaldson, A.D.; Fincke, J.R.; Kong, P.C.</p> <p>1998-05-12</p> <p>A fast quench <span class="hlt">reactor</span> includes a <span class="hlt">reactor</span> chamber having a high temperature heating means such as a plasma torch at its inlet and a restrictive convergent-divergent nozzle at its outlet end. Reactants are injected into the <span class="hlt">reactor</span> chamber. The resulting heated gaseous stream is then rapidly cooled by passage through the nozzle. This ``freezes`` the desired end product(s) in the heated equilibrium reaction stage. 7 figs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/1988snps.symp..243B','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/1988snps.symp..243B"><span>A novel plant protection strategy for transient <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Bhattacharyya, Samit K.; Lipinski, Walter C.; Hanan, Nelson A.</p> <p></p> <p>A novel plant protection system designed for use in the TREAT Upgrade (TU) <span class="hlt">reactor</span> is described. The TU <span class="hlt">reactor</span> is designed for controlled transient operation in the testing of <span class="hlt">reactor</span> fuel behavior under simulated <span class="hlt">reactor</span> accident conditions. Safe operation of the <span class="hlt">reactor</span> is of paramount importance and the Plant Protection System (PPS) had to be designed to exacting requirements. Researchers believe that the strategy developed for the TU has potential application to the multimegawatt space <span class="hlt">reactors</span> and represents the state of the art in terrestrial transient <span class="hlt">reactor</span> protection systems.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1345963','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1345963"><span>Space Nuclear <span class="hlt">Reactor</span> Engineering</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Poston, David Irvin</p> <p></p> <p>We needed to find a space <span class="hlt">reactor</span> concept that could be attractive to NASA for flight and proven with a rapid turnaround, low-cost nuclear test. Heat-pipe-cooled <span class="hlt">reactors</span> coupled to Stirling engines long identified as the easiest path to near-term, low-cost concept.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/10171768','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/10171768"><span>Thermomechanical analysis of fast-burst <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Miller, J.D.</p> <p>1994-08-01</p> <p>Fast-burst <span class="hlt">reactors</span> are designed to provide intense, short-duration pulses of neutrons. The fission reaction also produces extreme time-dependent heating of the nuclear fuel. An existing transient-dynamic finite element code was modified specifically to compute the time-dependent stresses and displacements due to thermal shock loads of <span class="hlt">reactors</span>. Thermomechanical analysis was then applied to determine structural feasibility of various concepts for an EDNA-type <span class="hlt">reactor</span> and to optimize the mechanical design of the new SPR III-M <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866424','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866424"><span>Fossil fuel furnace <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Parkinson, William J.</p> <p>1987-01-01</p> <p>A fossil fuel furnace <span class="hlt">reactor</span> is provided for simulating a continuous processing plant with a batch <span class="hlt">reactor</span>. An internal reaction vessel contains a batch of shale oil, with the vessel having a relatively thin wall thickness for a heat transfer rate effective to simulate a process temperature history in the selected continuous processing plant. A heater jacket is disposed about the <span class="hlt">reactor</span> vessel and defines a number of independent controllable temperature zones axially spaced along the reaction vessel. Each temperature zone can be energized to simulate a time-temperature history of process material through the continuous plant. A pressure vessel contains both the heater jacket and the reaction vessel at an operating pressure functionally selected to simulate the continuous processing plant. The process yield from the oil shale may be used as feedback information to software simulating operation of the continuous plant to provide operating parameters, i.e., temperature profiles, ambient atmosphere, operating pressure, material feed rates, etc., for simulation in the batch <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4159291-jen-reactor-control-system-sistema-de-control-del-reactor-jen','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/4159291-jen-reactor-control-system-sistema-de-control-del-reactor-jen"><span>JEN-1 <span class="hlt">Reactor</span> Control System; SISTEMA DE CONTROL DEL <span class="hlt">REACTOR</span> JEN-1</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Cantillo, M.F.; Nuno, C.M.; Andreu, J.L.M.</p> <p>1963-01-01</p> <p>ABS>The JEN-1 3Mw power swimming pool <span class="hlt">reactor</span> electrical control circuits are described. Start-up, power generation in the core, and shutdown are controlled by the <span class="hlt">reactor</span> control system. This control system guarantees in each moment the safety conditions during <span class="hlt">reactor</span> operation. Each circuit was represented by a scheme, complemented with a description of its function, components, and operation theory. Components described include: scram circuit; fission counter control circuit; servo control circuit; control circuit of safety sheets; control circuits of primary, secondary, and clean-up pump motors and tower fan motor; primary valve motor circuit; center cubicle alarm circuit; and process alarm circuit.more » (auth)« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4337124','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4337124"><span><span class="hlt">REACTOR</span> UNLOADING MEANS</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Cooper, C.M.</p> <p>1957-08-20</p> <p>A means for remotely unloading irradiated fuel slugs from a neutronic <span class="hlt">reactor</span> core and conveying them to a remote storage tank is reported. The means shown is specifically adapted for use with a <span class="hlt">reactor</span> core wherein the fuel slugs are slidably held in end to end abutting relationship in the horizontal coolant flow tubes, the slugs being spaced from tae internal walls of the tubes to permit continuous circulation of coolant water therethrough. A remotely operated plunger at the charging ends of the tubes is used to push the slugs through the tubes and out the discharge ends into a special slug valve which transfers the slug to a conveying tube leading into a storage tank. Water under pressure is forced through the conveying tube to circulate around the slug to cool it and also to force the slug through the conveving tube into the storage tank. The slug valve and conveying tube are shielded to prevent amy harmful effects caused by the radioactive slug in its travel from the <span class="hlt">reactor</span> to the storage tank. With the disclosed apparatus, all the slugs in the <span class="hlt">reactor</span> core can be conveyed to the storage tank shortly after shutdown by remotely located operating personnel.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19980230598','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19980230598"><span>NASA <span class="hlt">Reactor</span> Facility Hazards Summary. Volume 1</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p></p> <p>1959-01-01</p> <p>The Lewis Research Center of the National Aeronautics and Space Administration proposes to build a nuclear research <span class="hlt">reactor</span> which will be located in the Plum Brook Ordnance Works near Sandusky, Ohio. The purpose of this report is to inform the Advisory Committee on <span class="hlt">Reactor</span> Safeguards of the U. S. Atomic Energy Commission in regard to the design Lq of the <span class="hlt">reactor</span> facility, the characteristics of the site, and the hazards of operation at this location. The purpose of this research <span class="hlt">reactor</span> is to make pumped loop studies of aircraft <span class="hlt">reactor</span> fuel elements and other <span class="hlt">reactor</span> components, radiation effects studies on aircraft <span class="hlt">reactor</span> materials and equipment, shielding studies, and nuclear and solid state physics experiments. The <span class="hlt">reactor</span> is light water cooled and moderated of the MTR-type with a primary beryllium reflector and a secondary water reflector. The core initially will be a 3 by 9 array of MTR-type fuel elements and is designed for operation up to a power of 60 megawatts. The <span class="hlt">reactor</span> facility is described in general terms. This is followed by a discussion of the nuclear characteristics and performance of the <span class="hlt">reactor</span>. Then details of the <span class="hlt">reactor</span> control system are discussed. A summary of the site characteristics is then presented followed by a discussion of the larger type of experiments which may eventually be operated in this facility. The considerations for normal operation are concluded with a proposed method of handling fuel elements and radioactive wastes. The potential hazards involved with failures or malfunctions of this facility are considered in some detail. These are examined first from the standpoint of preventing them or minimizing their effects and second from the standpoint of what effect they might have on the <span class="hlt">reactor</span> facility staff and the surrounding population. The most essential feature of the design for location at the proposed site is containment of the maximum credible accident.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/20080004427','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/20080004427"><span>Aerosol <span class="hlt">reactor</span> production of uniform submicron powders</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Flagan, Richard C. (Inventor); Wu, Jin J. (Inventor)</p> <p>1991-01-01</p> <p>A method of producing submicron nonagglomerated particles in a single stage <span class="hlt">reactor</span> includes introducing a reactant or mixture of reactants at one end while varying the temperature along the <span class="hlt">reactor</span> to initiate reactions at a low rate. As homogeneously small numbers of seed particles generated in the initial section of the <span class="hlt">reactor</span> progress through the <span class="hlt">reactor</span>, the reaction is gradually accelerated through programmed increases in temperature along the length of the <span class="hlt">reactor</span> to promote particle growth by chemical vapor deposition while minimizing agglomerate formation by maintaining a sufficiently low number concentration of particles in the <span class="hlt">reactor</span> such that coagulation is inhibited within the residence time of particles in the <span class="hlt">reactor</span>. The maximum temperature and minimum residence time is defined by a combination of temperature and residence time that is necessary to bring the reaction to completion. In one embodiment, electronic grade silane and high purity nitrogen are introduced into the <span class="hlt">reactor</span> and temperatures of approximately 770.degree. K. to 1550.degree. K. are employed. In another embodiment silane and ammonia are employed at temperatures from 750.degree. K. to 1800.degree. K.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_9");'>9</a></li> <li><a href="#" onclick='return showDiv("page_10");'>10</a></li> <li class="active"><span>11</span></li> <li><a href="#" onclick='return showDiv("page_12");'>12</a></li> <li><a href="#" onclick='return showDiv("page_13");'>13</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_11 --> <div id="page_12" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_10");'>10</a></li> <li><a href="#" onclick='return showDiv("page_11");'>11</a></li> <li class="active"><span>12</span></li> <li><a href="#" onclick='return showDiv("page_13");'>13</a></li> <li><a href="#" onclick='return showDiv("page_14");'>14</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="221"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/867710','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/867710"><span>Aerosol <span class="hlt">reactor</span> production of uniform submicron powders</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Flagan, Richard C.; Wu, Jin J.</p> <p>1991-02-19</p> <p>A method of producing submicron nonagglomerated particles in a single stage <span class="hlt">reactor</span> includes introducing a reactant or mixture of reactants at one end while varying the temperature along the <span class="hlt">reactor</span> to initiate reactions at a low rate. As homogeneously small numbers of seed particles generated in the initial section of the <span class="hlt">reactor</span> progress through the <span class="hlt">reactor</span>, the reaction is gradually accelerated through programmed increases in temperature along the length of the <span class="hlt">reactor</span> to promote particle growth by chemical vapor deposition while minimizing agglomerate formation by maintaining a sufficiently low number concentration of particles in the <span class="hlt">reactor</span> such that coagulation is inhibited within the residence time of particles in the <span class="hlt">reactor</span>. The maximum temperature and minimum residence time is defined by a combination of temperature and residence time that is necessary to bring the reaction to completion. In one embodiment, electronic grade silane and high purity nitrogen are introduced into the <span class="hlt">reactor</span> and temperatures of approximately 770.degree. K. to 1550.degree. K. are employed. In another embodiment silane and ammonia are employed at temperatures from 750.degree. K. to 1800.degree. K.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1330299','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1330299"><span>Strengthening IAEA Safeguards for Research <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Reid, Bruce D.; Anzelon, George A.; Budlong-Sylvester, Kory</p> <p></p> <p>During their December 10-11, 2013, workshop in Grenoble France, which focused on the history and future of safeguarding research <span class="hlt">reactors</span>, the United States, France and the United Kingdom (UK) agreed to conduct a joint study exploring ways to strengthen the IAEA’s safeguards approach for declared research <span class="hlt">reactors</span>. This decision was prompted by concerns about: 1) historical cases of non-compliance involving misuse (including the use of non-nuclear materials for production of neutron generators for weapons) and diversion that were discovered, in many cases, long after the violations took place and as part of broader pattern of undeclared activities in half amore » dozen countries; 2) the fact that, under the Safeguards Criteria, the IAEA inspects some <span class="hlt">reactors</span> (e.g., those with power levels under 25 MWt) less than once per year; 3) the long-standing precedent of States using heavy water research <span class="hlt">reactors</span> (HWRR) to produce plutonium for weapons programs; 4) the use of HEU fuel in some research <span class="hlt">reactors</span>; and 5) various technical characteristics common to some types of research <span class="hlt">reactors</span> that could provide an opportunity for potential proliferators to misuse the facility or divert material with low probability of detection by the IAEA. In some research <span class="hlt">reactors</span> it is difficult to detect diversion or undeclared irradiation. In addition, infrastructure associated with research <span class="hlt">reactors</span> could pose a safeguards challenge. To strengthen the effectiveness of safeguards at the State level, this paper advocates that the IAEA consider ways to focus additional attention and broaden its safeguards toolbox for research <span class="hlt">reactors</span>. This increase in focus on the research <span class="hlt">reactors</span> could begin with the recognition that the research <span class="hlt">reactor</span> (of any size) could be a common path element on a large number of technically plausible pathways that must be considered when performing acquisition pathway analysis (APA) for developing a State Level Approach (SLA) and Annual Implementation Plan</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1328309','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1328309"><span>Status Report on Scoping <span class="hlt">Reactor</span> Physics and Sensitivity/Uncertainty Analysis of LR-0 <span class="hlt">Reactor</span> Molten Salt Experiments</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Brown, Nicholas R.; Mueller, Donald E.; Patton, Bruce W.</p> <p>2016-08-31</p> <p>Experiments are being planned at Research Centre Rež (RC Rež) to use the FLiBe (2 7LiF-BeF 2) salt from the Molten Salt <span class="hlt">Reactor</span> Experiment (MSRE) to perform <span class="hlt">reactor</span> physics measurements in the LR-0 low power nuclear <span class="hlt">reactor</span>. These experiments are intended to inform on neutron spectral effects and nuclear data uncertainties for advanced <span class="hlt">reactor</span> systems utilizing FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL) is performing sensitivity/uncertainty (S/U) analysis of these planned experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. Themore » objective of these analyses is to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a status update on the S/U analyses of critical experiments at the LR-0 <span class="hlt">Reactor</span> relevant to fluoride salt-cooled high temperature <span class="hlt">reactor</span> (FHR) and liquid-fueled molten salt <span class="hlt">reactor</span> (MSR) concepts. The S/U analyses will be used to inform design of FLiBe-based experiments using the salt from MSRE.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/864163','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/864163"><span>Cooling system for a nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Amtmann, Hans H.</p> <p>1982-01-01</p> <p>A cooling system for a gas-cooled nuclear <span class="hlt">reactor</span> is disclosed which includes at least one primary cooling loop adapted to pass coolant gas from the <span class="hlt">reactor</span> core and an associated steam generator through a duct system having a main circulator therein, and at least one auxiliary cooling loop having communication with the <span class="hlt">reactor</span> core and adapted to selectively pass coolant gas through an auxiliary heat exchanger and circulator. The main and auxiliary circulators are installed in a common vertical cavity in the <span class="hlt">reactor</span> vessel, and a common return duct communicates with the <span class="hlt">reactor</span> core and intersects the common cavity at a junction at which is located a flow diverter valve operative to effect coolant flow through either the primary or auxiliary cooling loops.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/863226','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/863226"><span>Compact power <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wetch, Joseph R.; Dieckamp, Herman M.; Wilson, Lewis A.</p> <p>1978-01-01</p> <p>There is disclosed a small compact nuclear <span class="hlt">reactor</span> operating in the epithermal neutron energy range for supplying power at remote locations, as for a satellite. The core contains fuel moderator elements of Zr hydride with 7 w/o of 93% enriched uranium alloy. The core has a radial beryllium reflector and is cooled by liquid metal coolant such as NaK. The <span class="hlt">reactor</span> is controlled and shut down by moving portions of the reflector.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/757029','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/757029"><span>Radionuclides in the Arctic seas from the former Soviet Union: Potential health and ecological risks</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Layton, D W; Edson, R; Varela, M</p> <p>1999-11-15</p> <p>The primary goal of the assessment reported here is to evaluate the health and environmental threat to coastal Alaska posed by radioactive-waste dumping in the Arctic and Northwest Pacific Oceans by the FSU. In particular, the FSU discarded 16 nuclear <span class="hlt">reactors</span> from submarines and an <span class="hlt">icebreaker</span> in the Kara Sea near the island of Novaya Zemlya, of which 6 contained spent nuclear fuel (SNF); disposed of liquid and solid wastes in the Sea of Japan; lost a {sup 90}Sr-powered radioisotope thermoelectric generator at sea in the Sea of Okhotsk; and disposed of liquid wastes at several sites in the Pacificmore » Ocean, east of the Kamchatka Peninsula. In addition to these known sources in the oceans, the RAIG evaluated FSU waste-disposal practices at inland weapons-development sites that have contaminated major rivers flowing into the Arctic Ocean. The RAIG evaluated these sources for the potential for release to the environment, transport, and impact to Alaskan ecosystems and peoples through a variety of scenarios, including a worst-case total instantaneous and simultaneous release of the sources under investigation. The risk-assessment process described in this report is applicable to and can be used by other circumpolar countries, with the addition of information about specific ecosystems and human life-styles. They can use the ANWAP risk-assessment framework and approach used by ONR to establish potential doses for Alaska, but add their own specific data sets about human and ecological factors. The ANWAP risk assessment addresses the following Russian wastes, media, and receptors: dumped nuclear submarines and <span class="hlt">icebreaker</span> in Kara Sea--marine pathways; solid <span class="hlt">reactor</span> parts in Sea of Japan and Pacific Ocean--marine pathways; thermoelectric generator in Sea of Okhotsk--marine pathways; current known aqueous wastes in Mayak reservoirs and Asanov Marshes--riverine to marine pathways; and Alaska as receptor. For these waste and source terms addressed, other pathways, such as</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/4784788','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/4784788"><span>KINETICS OF TREAT USED AS A TEST <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Dickerman, C.E.; Johnson, R.D.; Gasidlo, J.</p> <p>1962-05-01</p> <p>An analysis is presented concerning the <span class="hlt">reactor</span> kinetics of TREAT used as a pulsed, engineering test <span class="hlt">reactor</span> for fast <span class="hlt">reactor</span> fuel element studies. A description of the <span class="hlt">reactor</span> performance is given for a wide range of conditions associated with its use as a test <span class="hlt">reactor</span>. Supplemental information on meltdown experimentation is included. (J.R.D.)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1083026','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1083026"><span>Nuclear <span class="hlt">reactor</span> vessel fuel thermal insulating barrier</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Keegan, C. Patrick; Scobel, James H.; Wright, Richard F.</p> <p>2013-03-19</p> <p>The <span class="hlt">reactor</span> vessel of a nuclear <span class="hlt">reactor</span> installation which is suspended from the cold leg nozzles in a <span class="hlt">reactor</span> cavity is provided with a lower thermal insulating barrier spaced from the <span class="hlt">reactor</span> vessel that has a hemispherical lower section that increases in volume from the center line of the <span class="hlt">reactor</span> to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the <span class="hlt">reactor</span> vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the <span class="hlt">reactor</span> vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/6592245','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/6592245"><span>Acceptability of <span class="hlt">reactors</span> in space</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Buden, D.</p> <p>1981-04-01</p> <p><span class="hlt">Reactors</span> are the key to our future expansion into space. However, there has been some confusion in the public as to whether they are a safe and acceptable technology for use in space. The answer to these questions is explored. The US position is that when <span class="hlt">reactors</span> are the preferred technical choice, that they can be used safely. In fact, it dies not appear that <span class="hlt">reactors</span> add measurably to the risk associated with the Space Transportation System.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4310575','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4310575"><span><span class="hlt">REACTOR</span> AND NOVEL METHOD</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Young, G.J.; Ohlinger, L.A.</p> <p>1958-06-24</p> <p>A nuclear <span class="hlt">reactor</span> of the type which uses a liquid fuel and a method of controlling such a <span class="hlt">reactor</span> are described. The <span class="hlt">reactor</span> is comprised essentially of a tank for containing the liquid fuel such as a slurry of discrete particles of fissionnble material suspended in a heavy water moderator, and a control means in the form of a disc of neutron absorbirg material disposed below the top surface of the slurry and parallel thereto. The diameter of the disc is slightly smaller than the diameter of the tank and the disc is perforated to permit a flow of the slurry therethrough. The function of the disc is to divide the body of slurry into two separate portions, the lower portion being of a critical size to sustain a nuclear chain reaction and the upper portion between the top surface of the slurry and the top surface of the disc being of a non-critical size. The method of operation is to raise the disc in the <span class="hlt">reactor</span> until the lower portion of the slurry has reached a critical size when it is desired to initiate the reaction, and to lower the disc in the <span class="hlt">reactor</span> to reduce the size of the lower active portion the slurry to below criticality when it is desired to stop the reaction.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017JNET...42..265K','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017JNET...42..265K"><span>Entropy Production in Chemical <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Kingston, Diego; Razzitte, Adrián C.</p> <p>2017-06-01</p> <p>We have analyzed entropy production in chemically reacting systems and extended previous results to the two limiting cases of ideal <span class="hlt">reactors</span>, namely continuous stirred tank <span class="hlt">reactor</span> (CSTR) and plug flow <span class="hlt">reactor</span> (PFR). We have found upper and lower bounds for the entropy production in isothermal systems and given expressions for non-isothermal operation and analyzed the influence of pressure and temperature in entropy generation minimization in <span class="hlt">reactors</span> with a fixed volume and production. We also give a graphical picture of entropy production in chemical reactions subject to constant volume, which allows us to easily assess different options. We show that by dividing a <span class="hlt">reactor</span> into two smaller ones, operating at different temperatures, the entropy production is lowered, going as near as 48 % less in the case of a CSTR and PFR in series, and reaching 58 % with two CSTR. Finally, we study the optimal pressure and temperature for a single isothermal PFR, taking into account the irreversibility introduced by a compressor and a heat exchanger, decreasing the entropy generation by as much as 30 %.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/7315563','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/7315563"><span>SNAP 10A FS-3 <span class="hlt">reactor</span> performance</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Hawley, J.P.; Johnson, R.A.</p> <p>1966-08-15</p> <p>SNAP 10FS-3 was the first flight-qualified SNAP <span class="hlt">reactor</span> system to be operated in a simulated space environment. Prestart-up qualification testing, automatic start-up, endurance period performance, extended operation test and <span class="hlt">reactor</span> shutdown are described as they affected, or were affected by, overall <span class="hlt">reactor</span> performance. Performance of the <span class="hlt">reactor</span> control system and the diagnostic instrumentation is critically evaluted.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1425472','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1425472"><span>Nuclear <span class="hlt">reactor</span> cavity floor passive heat removal system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Edwards, Tyler A.; Neeley, Gary W.; Inman, James B.</p> <p></p> <p>A nuclear <span class="hlt">reactor</span> includes a <span class="hlt">reactor</span> core disposed in a <span class="hlt">reactor</span> pressure vessel. A radiological containment contains the nuclear <span class="hlt">reactor</span> and includes a concrete floor located underneath the nuclear <span class="hlt">reactor</span>. An ex vessel corium retention system includes flow channels embedded in the concrete floor located underneath the nuclear <span class="hlt">reactor</span>, an inlet in fluid communication with first ends of the flow channels, and an outlet in fluid communication with second ends of the flow channels. In some embodiments the inlet is in fluid communication with the interior of the radiological containment at a first elevation and the outlet is in fluidmore » communication with the interior of the radiological containment at a second elevation higher than the first elevation. The radiological containment may include a <span class="hlt">reactor</span> cavity containing a lower portion of the pressure vessel, wherein the concrete floor located underneath the nuclear <span class="hlt">reactor</span> is the <span class="hlt">reactor</span> cavity floor.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/26871299','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/26871299"><span>Using thermal balance model to determine optimal <span class="hlt">reactor</span> volume and insulation material needed in a laboratory-scale composting <span class="hlt">reactor</span>.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Wang, Yongjiang; Pang, Li; Liu, Xinyu; Wang, Yuansheng; Zhou, Kexun; Luo, Fei</p> <p>2016-04-01</p> <p>A comprehensive model of thermal balance and degradation kinetics was developed to determine the optimal <span class="hlt">reactor</span> volume and insulation material. Biological heat production and five channels of heat loss were considered in the thermal balance model for a representative <span class="hlt">reactor</span>. Degradation kinetics was developed to make the model applicable to different types of substrates. Simulation of the model showed that the internal energy accumulation of compost was the significant heat loss channel, following by heat loss through <span class="hlt">reactor</span> wall, and latent heat of water evaporation. Lower proportion of heat loss occurred through the <span class="hlt">reactor</span> wall when the <span class="hlt">reactor</span> volume was larger. Insulating materials with low densities and low conductive coefficients were more desirable for building small <span class="hlt">reactor</span> systems. Model developed could be used to determine the optimal <span class="hlt">reactor</span> volume and insulation material needed before the fabrication of a lab-scale composting system. Copyright © 2016 Elsevier Ltd. All rights reserved.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2018JPhCS.962a2054S','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2018JPhCS.962a2054S"><span>The Simulator Development for RDE <span class="hlt">Reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Subekti, Muhammad; Bakhri, Syaiful; Sunaryo, Geni Rina</p> <p>2018-02-01</p> <p>BATAN is proposing the construction of experimental power <span class="hlt">reactor</span> (RDE <span class="hlt">reactor</span>) for increasing the public acceptance on NPP development plan, proofing the safety level of the most advanced <span class="hlt">reactor</span> by performing safety demonstration on the accidents such as Chernobyl and Fukushima, and owning the generation fourth (G4) <span class="hlt">reactor</span> technology. For owning the <span class="hlt">reactor</span> technology, the one of research activities is RDE’s simulator development that employing standard equation. The development utilizes standard point kinetic and thermal equation. The examination of the simulator carried out comparison in which the simulation’s calculation result has good agreement with assumed parameters and ChemCAD calculation results. The transient simulation describes the characteristic of the simulator to respond the variation of power increase of 1.5%/min, 2.5%/min, and 3.5%/min.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4318740','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4318740"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wigner, E.P.; Weinberg, A.W.; Young, G.J.</p> <p>1958-04-15</p> <p>A nuclear <span class="hlt">reactor</span> which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The <span class="hlt">reactor</span> is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/920045','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/920045"><span>Safety control circuit for a neutronic <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ellsworth, Howard C.</p> <p>2004-04-27</p> <p>A neutronic <span class="hlt">reactor</span> comprising an active portion containing material fissionable by neutrons of thermal energy, means to control a neutronic chain reaction within the <span class="hlt">reactor</span> comprising a safety device and a regulating device, a safety device including means defining a vertical channel extending into the <span class="hlt">reactor</span> from an aperture in the upper surface of the <span class="hlt">reactor</span>, a rod containing neutron-absorbing materials slidably disposed within the channel, means for maintaining the safety rod in a withdrawn position relative to the active portion of the <span class="hlt">reactor</span> including means for releasing said rod on actuation thereof, a hopper mounted above the active portion of the <span class="hlt">reactor</span> having a door disposed at the bottom of the hopper opening into the vertical channel, a plurality of bodies of neutron-absorbing materials disposed within the hopper, and means responsive to the failure of the safety rod on actuation thereof to enter the active portion of the <span class="hlt">reactor</span> for opening the door in the hopper.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5310931-nuclear-reactor-fuel-containment-safety-structure','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/5310931-nuclear-reactor-fuel-containment-safety-structure"><span>Nuclear <span class="hlt">reactor</span> fuel containment safety structure</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Rosewell, M.P.</p> <p></p> <p>A nuclear <span class="hlt">reactor</span> fuel containment safety structure is disclosed and is shown to include an atomic <span class="hlt">reactor</span> fuel shield with a fuel containment chamber and exhaust passage means, and a deactivating containment base attached beneath the fuel <span class="hlt">reactor</span> shield and having exhaust passages, manifold, and fluxing and control material and vessels. 1 claim, 8 figures.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/6670250','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/6670250"><span>Control console replacement at the WPI <span class="hlt">Reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Not Available</p> <p>1992-01-01</p> <p>With partial funding from the Department of Energy (DOE) University <span class="hlt">Reactor</span> Instrumentation Upgrade Program (DOE Grant No. DE-FG02-90ER12982), the original control console at the Worcester Polytechnic Institute (WPI) <span class="hlt">Reactor</span> has been replaced with a modern system. The new console maintains the original design bases and functionality while utilizing current technology. An advanced remote monitoring system has been added to augment the educational capabilities of the <span class="hlt">reactor</span>. Designed and built by General Electric in 1959, the open pool nuclear training <span class="hlt">reactor</span> at WPI was one of the first such facilities in the nation located on a university campus. Devoted to undergraduatemore » use, the <span class="hlt">reactor</span> and its related facilities have been since used to train two generations of nuclear engineers and scientists for the nuclear industry. The <span class="hlt">reactor</span> power level was upgraded from 1 to 10 kill in 1969, and its operating license was renewed for 20 years in 1983. In 1988, the <span class="hlt">reactor</span> was converted to low enriched uranium. The low power output of the <span class="hlt">reactor</span> and ergonomic facility design make it an ideal tool for undergraduate nuclear engineering education and other training.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2013NuPhS.235...33S','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2013NuPhS.235...33S"><span>Application of <span class="hlt">Reactor</span> Antineutrinos: Neutrinos for Peace</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Suekane, F.</p> <p>2013-02-01</p> <p>In nuclear <span class="hlt">reactors</span>, 239Pu are produced along with burn-up of nuclear fuel. 239Pu is subject of safeguard controls since it is an explosive component of nuclear weapon. International Atomic Energy Agency (IAEA) is watching undeclared operation of <span class="hlt">reactors</span> to prevent illegal production and removal of 239Pu. In operating <span class="hlt">reactors</span>, a huge numbers of anti electron neutrinos (ν) are produced. Neutrino flux is approximately proportional to the operating power of <span class="hlt">reactor</span> in short term and long term decrease of the neutrino flux per thermal power is proportional to the amount of 239Pu produced. Thus rector ν's carry direct and real time information useful for the safeguard purposes. Since ν can not be hidden, it could be an ideal medium to monitor the <span class="hlt">reactor</span> operation. IAEA seeks for novel technologies which enhance their ability and <span class="hlt">reactor</span> neutrino monitoring is listed as one of such candidates. Currently neutrino physicists are performing R&D of small <span class="hlt">reactor</span> neutrino detectors to use specifically for the safeguard use in response to the IAEA interest. In this proceedings of the neutrino2012 conference, possibilities of such <span class="hlt">reactor</span> neutrinos application and current world-wide R&D status are described.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_10");'>10</a></li> <li><a href="#" onclick='return showDiv("page_11");'>11</a></li> <li class="active"><span>12</span></li> <li><a href="#" onclick='return showDiv("page_13");'>13</a></li> <li><a href="#" onclick='return showDiv("page_14");'>14</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_12 --> <div id="page_13" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_11");'>11</a></li> <li><a href="#" onclick='return showDiv("page_12");'>12</a></li> <li class="active"><span>13</span></li> <li><a href="#" onclick='return showDiv("page_14");'>14</a></li> <li><a href="#" onclick='return showDiv("page_15");'>15</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="241"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1096956','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1096956"><span>Design options for a bunsen <span class="hlt">reactor</span>.</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Moore, Robert Charles</p> <p>2013-10-01</p> <p>This work is being performed for Matt Channon Consulting as part of the Sandia National Laboratories New Mexico Small Business Assistance Program (NMSBA). Matt Channon Consulting has requested Sandia's assistance in the design of a chemical Bunsen <span class="hlt">reactor</span> for the reaction of SO2, I2 and H2O to produce H2SO4 and HI with a SO2 feed rate to the <span class="hlt">reactor</span> of 50 kg/hour. Based on this value, an assumed <span class="hlt">reactor</span> efficiency of 33%, and kinetic data from the literature, a plug flow <span class="hlt">reactor</span> approximately 1%E2%80%9D diameter and and 12 inches long would be needed to meet the specification of the project.more » Because the Bunsen reaction is exothermic, heat in the amount of approximately 128,000 kJ/hr would need to be removed using a cooling jacket placed around the tubular <span class="hlt">reactor</span>. The available literature information on Bunsen <span class="hlt">reactor</span> design and operation, certain support equipment needed for process operation and a design that meet the specification of Matt Channon Consulting are presented.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19720004950','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19720004950"><span>Dynamics of heat-pipe <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Niederauer, G. F.</p> <p>1971-01-01</p> <p>A split-core heat pipe <span class="hlt">reactor</span>, fueled with either U(233)C or U(235)C in a tungsten cermet and cooled by 7-Li-W heat pipes, was examined for the effects of the heat pipes on <span class="hlt">reactor</span> while trying to safely absorb large reactivity inputs through inherent shutdown mechanisms. Limits on ramp reactivity inputs due to fuel melting temperature and heat pipe wall heat flux were mapped for the <span class="hlt">reactor</span> in both startup and at-power operating modes.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4019685','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4019685"><span>NEUTRONIC <span class="hlt">REACTOR</span> BURIAL ASSEMBLY</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Treshow, M.</p> <p>1961-05-01</p> <p>A burial assembly is shown whereby an entire <span class="hlt">reactor</span> core may be encased with lead shielding, withdrawn from the <span class="hlt">reactor</span> site and buried. This is made possible by a five-piece interlocking arrangement that may be easily put together by remote control with no aligning of bolt holes or other such close adjustments being necessary.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/7206028','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/7206028"><span><span class="hlt">Reactor</span> core isolation cooling system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Cooke, F.E.</p> <p>1992-12-08</p> <p>A <span class="hlt">reactor</span> core isolation cooling system includes a <span class="hlt">reactor</span> pressure vessel containing a <span class="hlt">reactor</span> core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In operation, steam from the pressure vessel powers the turbine which in turn powers the pump to pump makeup water from a pool to the feedwater line into the pressure vessel for maintaining water level over the <span class="hlt">reactor</span> core. Steam discharged from the turbine is channeled to the isolation condenser and is condensed therein. The resulting heat is discharged into the isolation pool and vented to the atmosphere outside the containment vessel for removing heat therefrom. 1 figure.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/868582','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/868582"><span><span class="hlt">Reactor</span> core isolation cooling system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Cooke, Franklin E.</p> <p>1992-01-01</p> <p>A <span class="hlt">reactor</span> core isolation cooling system includes a <span class="hlt">reactor</span> pressure vessel containing a <span class="hlt">reactor</span> core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In operation, steam from the pressure vessel powers the turbine which in turn powers the pump to pump makeup water from a pool to the feedwater line into the pressure vessel for maintaining water level over the <span class="hlt">reactor</span> core. Steam discharged from the turbine is channeled to the isolation condenser and is condensed therein. The resulting heat is discharged into the isolation pool and vented to the atmosphere outside the containment vessel for removing heat therefrom.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/10110893','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/10110893"><span>Nuclear <span class="hlt">Reactors</span> and Technology</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Cason, D.L.; Hicks, S.C.</p> <p>1992-01-01</p> <p>This publication Nuclear <span class="hlt">Reactors</span> and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear <span class="hlt">reactors</span> and technology, including all aspects of power <span class="hlt">reactors</span>, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests inmore » NRT and other citations to information on nuclear <span class="hlt">reactors</span> back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/644252-sleeping-reactor-irradiations-shutdown-reactor-determination-short-lived-activation-products','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/644252-sleeping-reactor-irradiations-shutdown-reactor-determination-short-lived-activation-products"><span>``Sleeping <span class="hlt">reactor</span>`` irradiations: Shutdown <span class="hlt">reactor</span> determination of short-lived activation products</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Jerde, E.A.; Glasgow, D.C.</p> <p>1998-09-01</p> <p>At the High-Flux Isotope <span class="hlt">Reactor</span> (HFIR) at the Oak Ridge National Laboratory, the principal irradiation system has a thermal neutron flux ({phi}) of {approximately} 4 {times} 10{sup 14} n/cm{sup 2} {center_dot} s, permitting the detection of elements via irradiation of 60 s or less. Irradiations of 6 or 7 s are acceptable for detection of elements with half-lives of as little as 30 min. However, important elements such as Al, Mg, Ti, and V have half-lives of only a few minutes. At HFIR, these can be determined with irradiation times of {approximately} 6 s, but the requirement of immediate countingmore » leads to increased exposure to the high activity produced by irradiation in the high flux. In addition, pneumatic system timing uncertainties (about {+-} 0.5 s) make irradiations of < 6 s less reliable. Therefore, the determination of these ultra-short-lived species in mixed matrices has not generally been made at HFIR. The authors have found that very short lived activation products can be produced easily during the period after <span class="hlt">reactor</span> shutdown (SCRAM), but prior to the removal of spent fuel elements. During this 24- to 36-h period (dubbed the ``sleeping <span class="hlt">reactor</span>``), neutrons are produced in the beryllium reflector by the reaction {sup 9}Be({gamma},n){sup 8}Be, the gamma rays principally originating in the spent fuel. Upon <span class="hlt">reactor</span> SCRAM, the flux drops to {approximately} 1 {times} 10{sup 10} n/cm{sup 2} {center_dot} s within 1 h. By the time the fuel elements are removed, the flux has dropped to {approximately} 6 {times} 10{sup 8}. Such fluxes are ideal for the determination of short-lived elements such as Al, Ti, Mg, and V. An important feature of the sleeping <span class="hlt">reactor</span> is a flux that is not constant.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4836804','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4836804"><span>DENSITY CONTROL IN A <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Marshall, J. Jr.</p> <p>1961-10-24</p> <p>A <span class="hlt">reactor</span> is described in which natural-uranium bodies are located in parallel channels which extend through the graphite mass in a regular lattice. The graphite mass has additional channels that are out of the lattice and contain no uranium. These additional channels decrease in number per unit volume of graphite from the center of the <span class="hlt">reactor</span> to the exterior and have the effect of reducing the density of the graphite more at the center than at the exterior, thereby spreading neutron activity throughout the <span class="hlt">reactor</span>. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/4753868','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/4753868"><span>Experiences in utilization of research <span class="hlt">reactors</span> in Yugoslavia</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Copic, M.; Gabrovsek, Z.; Pop-Jordanov, J.</p> <p>1971-06-15</p> <p>The nuclear institutes in Yugoslavia possess three research <span class="hlt">reactors</span>. Since 1958, two heavy-water <span class="hlt">reactors</span> have been in operation at the 'Boris Kidric' Institute, a zero-power <span class="hlt">reactor</span> RB and a 6. 5-MW <span class="hlt">reactor</span> RA. At the Jozef Stefan Institute, a 250-kW TRIGA Mark II <span class="hlt">reactor</span> has been operating since 1966. All <span class="hlt">reactors</span> are equipped with the necessary experimental facilities. The main activities based on these <span class="hlt">reactors</span> are: (1) fundamental research in solid-state and nuclear physics; (2) R and D activities related to nuclear power program; and (3) radioisotope production. In fundamental physics, inelastic neutron scattering and diffraction phenomena are studied bymore » means of the neutron beam tubes and applied to investigations of the structures of solids and liquids. Valuable results are also obtained in n - γ reaction studies. Experiments connected with the fuel -element development program, owing to the characteristics of the existing <span class="hlt">reactors</span>, are limited to determination of the fuel element parameters, to studies on the purity of uranium, and to a small number of capsule irradiations. All three <span class="hlt">reactors</span> are also used for the verification of different methods applied in the analysis of power <span class="hlt">reactors</span>, particularly concerning neutron flux distributions, the optimization of <span class="hlt">reactor</span> core configurations and the shielding effects. An appreciable irradiation space in the <span class="hlt">reactors</span> is reserved for isotope production. Fruitful international co-operation has been established in all these activities, on the basis of either bilateral or multilateral arrangements. The paper gives a critical analysis of the utilization of research <span class="hlt">reactors</span> in a developing country such as Yugoslavia. The investments in and the operational costs of research <span class="hlt">reactors</span> are compared with the benefits obtained in different areas of <span class="hlt">reactor</span> application. The impact on the general scientific, technological and educational level in the country is also considered. In particular, an attempt is made ro</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/22175876','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/22175876"><span>High-rate treatment of molasses wastewater by combination of an acidification <span class="hlt">reactor</span> and a USSB <span class="hlt">reactor</span>.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Onodera, Takashi; Sase, Shinya; Choeisai, Pairaya; Yoochatchaval, Wilasinee; Sumino, Haruhiko; Yamaguchi, Takashi; Ebie, Yoshitaka; Xu, Kaiqin; Tomioka, Noriko; Syutsubo, Kazuaki</p> <p>2011-01-01</p> <p>A combination of an acidification <span class="hlt">reactor</span> and an up-flow staged sludge bed (USSB) <span class="hlt">reactor</span> was applied for treatment of molasses wastewater containing a large amount of organic compounds and sulfate. The USSB <span class="hlt">reactor</span> had three gas-solid separators (GSS) along the height of the <span class="hlt">reactor</span>. The combined system was continuously operated at mesophilic temperature over 400 days. In the acidification <span class="hlt">reactor</span>, acid formation and sulfate reduction were effectively carried out. The sugars contained in the influent wastewater were mostly acidified into acetate, propionate, and n-butyrate. In addition, 10-30% of influent sulfur was removed from the acidification <span class="hlt">reactor</span> by means of sulfate reduction followed by stripping of hydrogen sulfide. The USSB achieved a high organic loading rate (OLR) of 30 kgCOD m(-3) day(-1) with 82% COD removal. Vigorous biogas production was observed at a rate of 15 Nm(3) biogas m(-3) <span class="hlt">reactor</span> day(-1). The produced biogas, including hydrogen sulfide, was removed from the wastewater mostly via the GSS. The GSS provided a moderate superficial biogas flux and low sulfide concentration in the sludge bed, resulting in the prevention of sludge washout and sulfide inhibition of methanogens. By advantages of this feature, the USSB may have been responsible for achieving sufficient retention (approximately 60 gVSS L(-1)) of the granular sludge with high methanogenic activity (0.88 gCOD gVSS(-1) day(-1) for acetate and as high as 2.6 gCOD gVSS(-1) day(-1) for H(2)/CO(2)). Analysis of the microbial community revealed that sugar-degrading acid-forming bacteria proliferated in the sludge of the USSB as well as the acidification <span class="hlt">reactor</span> at high OLR conditions.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1378332','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1378332"><span>Review of Transient Testing of Fast <span class="hlt">Reactor</span> Fuels in the Transient <span class="hlt">REActor</span> Test Facility (TREAT)</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Jensen, C.; Wachs, D.; Carmack, J.</p> <p></p> <p>The restart of the Transient <span class="hlt">REActor</span> Test (TREAT) facility provides a unique opportunity to engage the fast <span class="hlt">reactor</span> fuels community to reinitiate in-pile experimental safety studies. Historically, the TREAT facility played a critical role in characterizing the behavior of both metal and oxide fast <span class="hlt">reactor</span> fuels under off-normal conditions, irradiating hundreds of fuel pins to support fast <span class="hlt">reactor</span> fuel development programs. The resulting test data has provided validation for a multitude of fuel performance and severe accident analysis computer codes. This paper will provide a review of the historical database of TREAT experiments including experiment design, instrumentation, test objectives, andmore » salient findings. Additionally, the paper will provide an introduction to the current and future experiment plans of the U.S. transient testing program at TREAT.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/544402','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/544402"><span>Thermal-hydraulic interfacing code modules for CANDU <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Liu, W.S.; Gold, M.; Sills, H.</p> <p>1997-07-01</p> <p>The approach for CANDU <span class="hlt">reactor</span> safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU <span class="hlt">reactors</span>, the procedure of coupling the thermal-hydraulics, <span class="hlt">reactor</span> physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of <span class="hlt">reactors</span> in the areas of <span class="hlt">reactor</span> safety analysis.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/932072-characteristics-dose-levels-spent-reactor-fuels','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/932072-characteristics-dose-levels-spent-reactor-fuels"><span>Characteristics and Dose Levels for Spent <span class="hlt">Reactor</span> Fuels</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Coates, Cameron W</p> <p>2007-01-01</p> <p>Current guidance considers highly radioactive special nuclear materials to be those materials that, unshielded, emit a radiation dose [rate] measured at 1 m which exceeds 100 rem/h. Smaller, less massive fuel assemblies from research <span class="hlt">reactors</span> can present a challenge from the point of view of self protection because of their size (lower dose, easier to handle) and the desirability of higher enrichments; however, a follow-on study to cross-compare dose trends of research <span class="hlt">reactors</span> and power <span class="hlt">reactors</span> was deemed useful to confirm/verify these trends. This paper summarizes the characteristics and dose levels of spent <span class="hlt">reactor</span> fuels for both research <span class="hlt">reactors</span> andmore » power <span class="hlt">reactors</span> and extends previous studies aimed at quantifying expected dose rates from research <span class="hlt">reactor</span> fuels worldwide.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/870492','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/870492"><span>Dynamic bed <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Stormo, Keith E.</p> <p>1996-07-02</p> <p>A dynamic bed <span class="hlt">reactor</span> is disclosed in which a compressible open cell foam matrix is periodically compressed and expanded to move a liquid or fluid through the matrix. In preferred embodiments, the matrix contains an active material such as an enzyme, biological cell, chelating agent, oligonucleotide, adsorbent or other material that acts upon the liquid or fluid passing through the matrix. The active material may be physically immobilized in the matrix, or attached by covalent or ionic bonds. Microbeads, substantially all of which have diameters less than 50 microns, can be used to immobilize the active material in the matrix and further improve <span class="hlt">reactor</span> efficiency. A particularly preferred matrix is made of open cell polyurethane foam, which adsorbs pollutants such as polychlorophenol or o-nitrophenol. The <span class="hlt">reactors</span> of the present invention allow unidirectional non-laminar flow through the matrix, and promote intimate exposure of liquid reactants to active agents such as microorganisms immobilized in the matrix.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4128821','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4128821"><span>BOILER-SUPERHEATED <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Heckman, T.P.</p> <p>1961-05-01</p> <p>A nuclear power <span class="hlt">reactor</span> of the type in which a liquid moderator-coolant is transformed by nuclear heating into a vapor that may be used to drive a turbo- generator is described. The core of this <span class="hlt">reactor</span> comprises a plurality of freely suspended tubular fuel elements, called fuel element trains, within which nonboiling pressurized liquid moderator-coolant is preheated and sprayed through orifices in the walls of the trains against the outer walls thereof to be converted into vapor. Passage of the vapor ovcr other unwetted portions of the outside of the fuel elements causes the steam to be superheated. The moderatorcoolant within the fuel elements remains in the liqUid state, and that between the fuel elements remains substantiaily in the vapor state. A unique liquid neutron-absorber control system is used. Advantages expected from the <span class="hlt">reactor</span> design include reduced fuel element failure, increased stability of operation, direct response to power demand, and circulation of a minimum amount of liquid moderatorcoolant. (A.G.W.)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6947380-trench-fast-reactor-design-using-microcomputer','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/6947380-trench-fast-reactor-design-using-microcomputer"><span>Trench fast <span class="hlt">reactor</span> design using the microcomputer</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Rohach, A.F.; Sankoorikal, J.T.; Schmidt, R.R.</p> <p>1987-01-01</p> <p>This project is a study of alternative liquid-metal-cooled fast power <span class="hlt">reactor</span> system concepts. Specifically, an unconventional primary system is being conceptually designed and evaluated. The project design is based primarily on microcomputer analysis through the use of computational modules. The <span class="hlt">reactor</span> system concept is a long, narrow pool with a long, narrow <span class="hlt">reactor</span> called a trench-type pool <span class="hlt">reactor</span> in it. The <span class="hlt">reactor</span> consists of five core-blanket modules in a line. Specific power is to be modest, permitting long fuel residence time. Two fuel cycles are currently being considered. The <span class="hlt">reactor</span> design philosophy is that of the inherently safe concept. Thismore » requires transient analysis dependent on reactivity coefficients: prompt fuel, including Doppler and expansion, fuel expansion, sodium temperature and void, and core expansion. Conceptual <span class="hlt">reactor</span> design is done on a microcomputer. A part of the trench <span class="hlt">reactor</span> project is to develop a microcomputer-based system that can be used by the user for scoping studies and design. Current development includes the neutronics and fuel management aspects of the design. Thermal-hydraulic analysis and economics are currently being incorporated into the microcomputer system. The system is menu-driven including preparation of program input data and of output data for displays in graphics form.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/865168','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/865168"><span>Rapid starting methanol <span class="hlt">reactor</span> system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Chludzinski, Paul J.; Dantowitz, Philip; McElroy, James F.</p> <p>1984-01-01</p> <p>The invention relates to a methanol-to-hydrogen cracking <span class="hlt">reactor</span> for use with a fuel cell vehicular power plant. The system is particularly designed for rapid start-up of the catalytic methanol cracking <span class="hlt">reactor</span> after an extended shut-down period, i.e., after the vehicular fuel cell power plant has been inoperative overnight. Rapid system start-up is accomplished by a combination of direct and indirect heating of the cracking catalyst. Initially, liquid methanol is burned with a stoichiometric or slightly lean air mixture in the combustion chamber of the <span class="hlt">reactor</span> assembly. The hot combustion gas travels down a flue gas chamber in heat exchange relationship with the catalytic cracking chamber transferring heat across the catalyst chamber wall to heat the catalyst indirectly. The combustion gas is then diverted back through the catalyst bed to heat the catalyst pellets directly. When the cracking <span class="hlt">reactor</span> temperature reaches operating temperature, methanol combustion is stopped and a hot gas valve is switched to route the flue gas overboard, with methanol being fed directly to the catalytic cracking <span class="hlt">reactor</span>. Thereafter, the burner operates on excess hydrogen from the fuel cells.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/563636','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/563636"><span>Combustion synthesis continuous flow <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Maupin, G.D.; Chick, L.A.; Kurosky, R.P.</p> <p>1998-01-06</p> <p>The present invention is a <span class="hlt">reactor</span> for combustion synthesis of inorganic powders. The <span class="hlt">reactor</span> includes a reaction vessel having a length and a first end and a second end. The reaction vessel further has a solution inlet and a carrier gas inlet. The <span class="hlt">reactor</span> further has a heater for heating both the solution and the carrier gas. In a preferred embodiment, the reaction vessel is heated and the solution is in contact with the heated reaction vessel. It is further preferred that the reaction vessel be cylindrical and that the carrier gas is introduced tangentially into the reaction vessel so that the solution flows helically along the interior wall of the reaction vessel. As the solution evaporates and combustion produces inorganic material powder, the carrier gas entrains the powder and carries it out of the <span class="hlt">reactor</span>. 10 figs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/871305','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/871305"><span>Combustion synthesis continuous flow <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Maupin, Gary D.; Chick, Lawrence A.; Kurosky, Randal P.</p> <p>1998-01-01</p> <p>The present invention is a <span class="hlt">reactor</span> for combustion synthesis of inorganic powders. The <span class="hlt">reactor</span> includes a reaction vessel having a length and a first end and a second end. The reaction vessel further has a solution inlet and a carrier gas inlet. The <span class="hlt">reactor</span> further has a heater for heating both the solution and the carrier gas. In a preferred embodiment, the reaction vessel is heated and the solution is in contact with the heated reaction vessel. It is further preferred that the reaction vessel be cylindrical and that the carrier gas is introduced tangentially into the reaction vessel so that the solution flows helically along the interior wall of the reaction vessel. As the solution evaporates and combustion produces inorganic material powder, the carrier gas entrains the powder and carries it out of the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4261944','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4261944"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wade, E.J.</p> <p>1958-09-16</p> <p>This patent relates to a reflector means for a neutronic <span class="hlt">reactor</span>. A reflector comprised of a plurality of vertically movable beryllium control members is provided surrounding the sides of the <span class="hlt">reactor</span> core. An absorber of fast neutrons comprised of natural uramum surrounds the reflector. An absorber of slow neutrons surrounds the absorber of fast neutrons and is formed of a plurality of beryllium blocks having natural uranium members distributcd therethrough. in addition, a movable body is positioned directly below the core and is comprised of a beryllium reflector and an absorbing member attached to the botiom thereof, the absorbing member containing a substance selected from the goup consisting of natural urantum and Th/sup 232/.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_11");'>11</a></li> <li><a href="#" onclick='return showDiv("page_12");'>12</a></li> <li class="active"><span>13</span></li> <li><a href="#" onclick='return showDiv("page_14");'>14</a></li> <li><a href="#" onclick='return showDiv("page_15");'>15</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_13 --> <div id="page_14" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_12");'>12</a></li> <li><a href="#" onclick='return showDiv("page_13");'>13</a></li> <li class="active"><span>14</span></li> <li><a href="#" onclick='return showDiv("page_15");'>15</a></li> <li><a href="#" onclick='return showDiv("page_16");'>16</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="261"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1342850','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1342850"><span>Fuel Fabrication and Nuclear <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Karpius, Peter Joseph</p> <p>2017-02-02</p> <p>The uranium from the enrichment plant is still in the form of UF 6. UF 6 is not suitable for use in a <span class="hlt">reactor</span> due to its highly corrosive chemistry as well as its phase diagram. UF 6 is converted into UO 2 fuel pellets, which are in turn placed in fuel rods and assemblies. <span class="hlt">Reactor</span> designs are variable in moderators, coolants, fuel, performance etc.The dream of energy ‘too-cheap to meter’ is no more, and now the nuclear power industry is pushing ahead with advanced <span class="hlt">reactor</span> designs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/6350642','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/6350642"><span>TREAT <span class="hlt">Reactor</span> Control and Protection System</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Lipinski, W.C.; Brookshier, W.K.; Burrows, D.R.</p> <p>1985-01-01</p> <p>The main control algorithm of the Transient <span class="hlt">Reactor</span> Test Facility (TREAT) Automatic <span class="hlt">Reactor</span> Control System (ARCS) resides in Read Only Memory (ROM) and only experiment specific parameters are input via keyboard entry. Prior to executing an experiment, the software and hardware of the control computer is tested by a closed loop real-time simulation. Two computers with parallel processing are used for the <span class="hlt">reactor</span> simulation and another computer is used for simulation of the control rod system. A monitor computer, used as a redundant diverse <span class="hlt">reactor</span> protection channel, uses more conservative setpoints and reduces challenges to the <span class="hlt">Reactor</span> Trip System (RTS).more » The RTS consists of triplicated hardwired channels with one out of three logic. The RTS is automatically tested by a digital Dedicated Microprocessor Tester (DMT) prior to the execution of an experiment. 6 refs., 5 figs., 1 tab.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4674745','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4674745"><span>REFLECTOR FOR NEUTRONIC <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Fraas, A.P.</p> <p>1963-08-01</p> <p>A reflector for nuclear <span class="hlt">reactors</span> that comprises an assembly of closely packed graphite rods disposed with their major axes substantially perpendicular to the interface between the <span class="hlt">reactor</span> core and the reflector is described. Each graphite rod is round in transverse cross section at (at least) its interface end and is provided, at that end, with a coaxial, inwardly tapering hole. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4030720','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4030720"><span>MERCHANT MARINE SHIP <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Mumm, J.F.; North, D.C. Jr.; Rock, H.R.; Geston, D.K.</p> <p>1961-05-01</p> <p>A nuclear <span class="hlt">reactor</span> is described for use in a merchant marine ship. The <span class="hlt">reactor</span> is of pressurized light water cooled and moderated design in which three passes of the water through the core in successive regions of low, intermediate, and high heat generation and downflow in a fuel region are made. The foregoing design makes a compact <span class="hlt">reactor</span> construction with extended core life. The core has an egg-crate lattice containing the fuel elements confined between a lower flow baffle and upper grid plate, with the latter serving also as part of a turn- around manifold from which the entire coolant is distributed into the outer fuel elements for the second pass through the core. The inner fuel elements are cooled in the third pass.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/4013878','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/4013878"><span>Merchant Marine Ship <span class="hlt">Reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Sankovich, M. F.; Mumm, J. F.; North, Jr, D. C.; Rock, H. R.; Gestson, D. K.</p> <p>1961-05-01</p> <p>A nuclear <span class="hlt">reactor</span> for use in a merchant marine ship is described. The <span class="hlt">reactor</span> is of pressurized, light water cooled and moderated design in which three passes of the water through the core in successive regions of low, intermediate, and high heat generation and downflow in a fuel region are made. The design makes a compact <span class="hlt">reactor</span> construction with extended core life. The core has an egg-crate lattice containing the fuel elements that are confined between a lower flow baffle and upper grid plate, with the latter serving also as part of a turn- around manifold from which the entire coolant is distributed into the outer fuel elements for the second pass through the core. The inner fuel elements are cooled in the third pass. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6613170','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/6613170"><span>Heat dissipating nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hunsbedt, A.; Lazarus, J.D.</p> <p>1985-11-21</p> <p>Disclosed is a nuclear <span class="hlt">reactor</span> containment adapted to retain and cool core debris in the unlikely event of a core meltdown and subsequent breach in the <span class="hlt">reactor</span> vessel. The <span class="hlt">reactor</span> vessel is seated in a cavity which has a thick metal sidewall that is integral with a thick metal basemat at the bottom of the cavity. The basemat extends beyond the perimeter of the cavity sidewall. Underneath the basemat is a porous bed with water pipes and steam pipes running into it. Water is introduced into the bed and converted into steam which is vented to the atmosphere. A plurality of metal pilings in the form of H-beams extend from the metal base plate downwardly and outwardly into the earth.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866147','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866147"><span>Heat dissipating nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hunsbedt, Anstein; Lazarus, Jonathan D.</p> <p>1987-01-01</p> <p>Disclosed is a nuclear <span class="hlt">reactor</span> containment adapted to retain and cool core debris in the unlikely event of a core meltdown and subsequent breach in the <span class="hlt">reactor</span> vessel. The <span class="hlt">reactor</span> vessel is seated in a cavity which has a thick metal sidewall that is integral with a thick metal basemat at the bottom of the cavity. The basemat extends beyond the perimeter of the cavity sidewall. Underneath the basemat is a porous bed with water pipes and steam pipes running into it. Water is introduced into the bed and converted into steam which is vented to the atmosphere. A plurality of metal pilings in the form of H-beams extends from the metal base plate downwardly and outwardly into the earth.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1333822','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1333822"><span>Thermochemical <span class="hlt">reactor</span> systems and methods</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Lipinski, Wojciech; Davidson, Jane Holloway; Chase, Thomas Richard</p> <p>2016-11-29</p> <p>Thermochemical <span class="hlt">reactor</span> systems that may be used to produce a fuel, and methods of using the thermochemical <span class="hlt">reactor</span> systems, utilizing a reactive cylindrical element, an optional energy transfer cylindrical element, an inlet gas management system, and an outlet gas management system.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017AIPA....7e6677R','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017AIPA....7e6677R"><span><span class="hlt">Reactor</span> vibration reduction based on giant magnetostrictive materials</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Rongge, Yan; Weiying, Liu; Yuechao, Wu; Menghua, Duan; Xiaohong, Zhang; Lihua, Zhu; Ling, Weng; Ying, Sun</p> <p>2017-05-01</p> <p>The vibration of <span class="hlt">reactors</span> not only produces noise pollution, but also affects the safe operation of <span class="hlt">reactors</span>. Giant magnetostrictive materials can generate huge expansion and shrinkage deformation in a magnetic field. With the principle of mutual offset between the giant magnetostrictive force produced by the giant magnetostrictive material and the original vibration force of the <span class="hlt">reactor</span>, the vibration of the <span class="hlt">reactor</span> can be reduced. In this paper, magnetization and magnetostriction characteristics in silicon steel and the giant magnetostrictive material are measured, respectively. According to the presented magneto-mechanical coupling model including the electromagnetic force and the magnetostrictive force, <span class="hlt">reactor</span> vibration is calculated. By comparing the vibration of the <span class="hlt">reactor</span> with different inserted materials in the air gaps between the <span class="hlt">reactor</span> cores, the vibration reduction effectiveness of the giant magnetostrictive material is validated.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/5338042','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/5338042"><span>Advanced <span class="hlt">reactor</span> design study. Assessing nonbackfittable concepts for improving uranium utilization in light water <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Fleischman, R.M.; Goldsmith, S.; Newman, D.F.</p> <p>1981-09-01</p> <p>The objective of the Advanced <span class="hlt">Reactor</span> Design Study (ARDS) is to identify and evaluate nonbackfittable concepts for improving uranium utilization in light water <span class="hlt">reactors</span> (LWRs). The results of this study provide a basis for selecting and demonstrating specific nonbackfittable concepts that have good potential for implementation. Lead responsibility for managing the study was assigned to the Pacific Northwest Laboratory (PNL). Nonbackfittable concepts for improving uranium utilization in LWRs on the once-through fuel cycle were selected separately for PWRs and BWRs due to basic differences in the way specific concepts apply to those plants. Nonbackfittable concepts are those that are toomore » costly to incorporate in existing plants, and thus, could only be economically incorporated in new <span class="hlt">reactor</span> designs or plants in very early stages of construction. Essential results of the Advanced <span class="hlt">Reactor</span> Design Study are summarized.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4660204','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4660204"><span>PRESSURIZED WATER <span class="hlt">REACTOR</span> CORE WITH PLUTONIUM BURNUP</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Puechl, K.H.</p> <p>1963-09-24</p> <p>A pressurized water <span class="hlt">reactor</span> is described having a core containing Pu/sup 240/ in which the effective microscopic neutronabsorption cross section of Pu/sup 240/ in unconverted condition decreases as the time of operation of the <span class="hlt">reactor</span> increases, in order to compensate for loss of reactivity resulting from fission product buildup during <span class="hlt">reactor</span> operation. This means serves to improve the efficiency of the <span class="hlt">reactor</span> operation by reducing power losses resulting from control rods and burnable poisons. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6211324','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/6211324"><span>Digital computer operation of a nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Colley, R.W.</p> <p>1982-06-29</p> <p>A method is described for the safe operation of a complex system such as a nuclear <span class="hlt">reactor</span> using a digital computer. The computer is supplied with a data base containing a list of the safe state of the <span class="hlt">reactor</span> and a list of operating instructions for achieving a safe state when the actual state of the <span class="hlt">reactor</span> does not correspond to a listed safe state, the computer selects operating instructions to return the <span class="hlt">reactor</span> to a safe state.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/865086','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/865086"><span>Digital computer operation of a nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Colley, Robert W.</p> <p>1984-01-01</p> <p>A method is described for the safe operation of a complex system such as a nuclear <span class="hlt">reactor</span> using a digital computer. The computer is supplied with a data base containing a list of the safe state of the <span class="hlt">reactor</span> and a list of operating instructions for achieving a safe state when the actual state of the <span class="hlt">reactor</span> does not correspond to a listed safe state, the computer selects operating instructions to return the <span class="hlt">reactor</span> to a safe state.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/868680','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/868680"><span>Liquid metal cooled nuclear <span class="hlt">reactor</span> plant system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hunsbedt, Anstein; Boardman, Charles E.</p> <p>1993-01-01</p> <p>A liquid metal cooled nuclear <span class="hlt">reactor</span> having a passive cooling system for removing residual heat resulting for fuel decay during <span class="hlt">reactor</span> shutdown, or heat produced during a mishap. The <span class="hlt">reactor</span> system is enhanced with sealing means for excluding external air from contact with the liquid metal coolant leaking from the <span class="hlt">reactor</span> vessel during an accident. The invention also includes a silo structure which resists attack by leaking liquid metal coolant, and an added unique cooling means.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4019503','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4019503"><span>SYSTEM FOR UNLOADING <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Rand, A.C. Jr.</p> <p>1961-05-01</p> <p>An unloading device for individual vertical fuel channels in a nuclear <span class="hlt">reactor</span> is shown. The channels are arranged in parallel rows and underneath each is a separate supporting block on which the fuel in the channel rests. The blocks are raounted in contiguous rows on an array of parallel pairs of tracks over the bottom of the <span class="hlt">reactor</span>. Oblong hollows in the blocks form a continuous passageway through the middle of the row of blocks on each pair of tracks. At the end of each passageway is a horizontal grappling rod with a T- or L extension at the end next to the <span class="hlt">reactor</span> of a length to permit it to pass through the oblong passageway in one position, but when rotated ninety degrees the head will strike one of the longer sides of the oblong hollow of one of the blocks. The grappling rod is actuated by a controllable reciprocating and rotating device which extends it beyond any individual block desired, rotates it and retracts it far enough to permit the fuel in the vertical channel above the block to fall into a handling tank below the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1436452','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1436452"><span>Phenomena Important in Molten Salt <span class="hlt">Reactor</span> Simulations</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Diamond, David J.; Brown, Nicholas R.; Denning, Richard</p> <p></p> <p>The U.S. Nuclear Regulatory Commission (NRC) is preparing for the future licensing of advanced <span class="hlt">reactors</span> that will be very different from current light water <span class="hlt">reactors</span>. Part of the NRC preparation strategy is to identify the simulation tools that will be used for confirmatory safety analysis of normal operation and abnormal situations in those <span class="hlt">reactors</span>. This report advances that strategy for <span class="hlt">reactors</span> that will use molten salts (MSRs). This includes <span class="hlt">reactors</span> with the fuel within the salt as well as <span class="hlt">reactors</span> using solid fuel. Although both types are discussed in this report, the emphasis is on those <span class="hlt">reactors</span> with liquid fuelmore » because of the perception that solid-fuel MSRs will be significantly easier to simulate. These liquid-fuel <span class="hlt">reactors</span> include thermal and fast neutron spectrum alternatives. The specific designs discussed in the report are a subset of many designs being considered in the U.S. and elsewhere but they are considered the most likely to submit information to the NRC in the near future. The objective herein, is to understand the design of proposed molten salt <span class="hlt">reactors</span>, how they will operate under normal or transient/accident conditions, and what will be the corresponding modeling needs of simulation tools that consider neutronics, heat transfer, fluid dynamics, and material composition changes in the molten salt. These tools will enable the NRC to eventually carry out confirmatory analyses that examine the validity and accuracy of applicant’s calculations and help determine the margin of safety in plant design.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/863319','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/863319"><span>Nuclear propulsion apparatus with alternate <span class="hlt">reactor</span> segments</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Szekely, Thomas</p> <p>1979-04-03</p> <p>1. Nuclear propulsion apparatus comprising: A. means for compressing incoming air; B. nuclear fission <span class="hlt">reactor</span> means for heating said air; C. means for expanding a portion of the heated air to drive said compressing means; D. said nuclear fission <span class="hlt">reactor</span> means being divided into a plurality of radially extending segments; E. means for directing a portion of the compressed air for heating through alternate segments of said <span class="hlt">reactor</span> means and another portion of the compressed air for heating through the remaining segments of said <span class="hlt">reactor</span> means; and F. means for further expanding the heated air from said drive means and the remaining heated air from said <span class="hlt">reactor</span> means through nozzle means to effect reactive thrust on said apparatus.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4027625','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4027625"><span>CALANDRIA TYPE SODIUM GRAPHITE <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Peterson, R.M.; Mahlmeister, J.E.; Vaughn, N.E.; Sanders, W.J.; Williams, A.C.</p> <p>1964-02-11</p> <p>A sodium graphite power <span class="hlt">reactor</span> in which the unclad graphite moderator and fuel elements are contained within a core tank is described. The core tank is submersed in sodium within the <span class="hlt">reactor</span> vessel. Extending longitudinally through the core thnk are process tubes with fuel elements positioned therein. A bellows sealing means allows axial expansion and construction of the tubes. Within the core tank, a leakage plenum is located below the graphite, and above the graphite is a gas space. A vent line regulates the gas pressure in the space, and another line removes sodium from the plenum. The sodium coolant flows from the lower <span class="hlt">reactor</span> vessel through the annular space between the fuel elements and process tubes and out into the <span class="hlt">reactor</span> vessel space above the core tank. From there, the heated coolant is drawn off through an outlet line and sent to the heat exchange. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/FR-2013-11-29/pdf/2013-28699.pdf','FEDREG'); return false;" href="https://www.gpo.gov/fdsys/pkg/FR-2013-11-29/pdf/2013-28699.pdf"><span>78 FR 71675 - Update of the Office of Nuclear <span class="hlt">Reactor</span> Regulation's Electronic Operating <span class="hlt">Reactor</span> Correspondence</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collection.action?collectionCode=FR">Federal Register 2010, 2011, 2012, 2013, 2014</a></p> <p></p> <p>2013-11-29</p> <p>... correspondence to addressees and subscribers through a computer-based email distribution system. Since then, the... Electronic Operating <span class="hlt">Reactor</span> Correspondence The U.S. Nuclear Regulatory Commission (NRC) is issuing this... available operating <span class="hlt">reactor</span> licensing correspondence, effective December 9, 2013. Official agency records...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4111739','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4111739"><span>METHOD AND APPARATUS FOR CONTROLLING DIRECT-CYCLE NEUTRONIC <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Reed, G.A.</p> <p>1961-01-10</p> <p>A control arrangement is offered for a boiling-water <span class="hlt">reactor</span>. Boric acid is maintained in the water in the <span class="hlt">reactor</span> and the amount in the <span class="hlt">reactor</span> is controlled by continuously removing a portion of the water from the <span class="hlt">reactor</span>, concentrating the boric acid by evaporating the water therefrom, returning a controlled amount of the acid to the <span class="hlt">reactor</span>, and simultaneously controlling the water level by varying the rate of spent steam return to the <span class="hlt">reactor</span>.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_12");'>12</a></li> <li><a href="#" onclick='return showDiv("page_13");'>13</a></li> <li class="active"><span>14</span></li> <li><a href="#" onclick='return showDiv("page_15");'>15</a></li> <li><a href="#" onclick='return showDiv("page_16");'>16</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_14 --> <div id="page_15" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_13");'>13</a></li> <li><a href="#" onclick='return showDiv("page_14");'>14</a></li> <li class="active"><span>15</span></li> <li><a href="#" onclick='return showDiv("page_16");'>16</a></li> <li><a href="#" onclick='return showDiv("page_17");'>17</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="281"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/17970519','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/17970519"><span>A comparison of the technological effectiveness of dairy wastewater treatment in anaerobic UASB <span class="hlt">reactor</span> and anaerobic <span class="hlt">reactor</span> with an innovative design.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Jedrzejewska-Cicinska, M; Kozak, K; Krzemieniewski, M</p> <p>2007-10-01</p> <p>The present research was an investigation of the influence of an innovative design of <span class="hlt">reactor</span> filled with polyethylene (PE) granulate on model dairy wastewater treatment efficiency under anaerobic conditions compared to that obtained in a typical UASB <span class="hlt">reactor</span>. The experiment was conducted at laboratory scale. An innovative <span class="hlt">reactor</span> was designed with the reaction chamber inclined 30 degrees in relation to the ground with upward waste flow and was filled with PE granular material. Raw model dairy wastewater was fed to two anaerobic <span class="hlt">reactors</span> of different design at the organic loading rate of 4 kg COD m(-3)d(-1). Throughout the experiment, a higher removal efficiency of organic compounds was observed in the <span class="hlt">reactor</span> with an innovative design and it was higher by 7.1% on average than in the UASB <span class="hlt">reactor</span>. The total suspended solids was lower in the wastewater treated in the anaerobic <span class="hlt">reactor</span> with the innovative design. Applying a PE granulated filling in the chamber of the innovative <span class="hlt">reactor</span> contributed to an even distribution of sludge biomass in the <span class="hlt">reactor</span>, reducing washout of anaerobic sludge biomass from the reaction chamber and giving a higher organic compounds removal efficiency.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4261844','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4261844"><span>MEANS FOR SHIELDING AND COOLING <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wigner, E.P.; Ohlinger, L.A.; Young, G.J.; Weinberg, A.M.</p> <p>1959-02-10</p> <p><span class="hlt">Reactors</span> of the water-cooled type and a means for shielding such a rcactor to protect operating personnel from harmful radiation are discussed. In this <span class="hlt">reactor</span> coolant tubes which contain the fissionable material extend vertically through a mass of moderator. Liquid coolant enters through the bottom of the coolant tubes and passes upwardly over the fissionable material. A shield tank is disposed over the top of the <span class="hlt">reactor</span> and communicates through its bottom with the upper end of the coolant tubes. A hydrocarbon shielding fluid floats on the coolant within the shield tank. With this arrangements the upper face of the <span class="hlt">reactor</span> can be opened to the atmosphere through the two superimposed liquid layers. A principal feature of the invention is that in the event radioactive fission products enter thc coolant stream. imposed layer of hydrocarbon reduces the intense radioactivity introduced into the layer over the <span class="hlt">reactors</span> and permits removal of the offending fuel material by personnel shielded by the uncontaminated hydrocarbon layer.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2015RScI...86l3503H','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2015RScI...86l3503H"><span>Plasma nitriding monitoring <span class="hlt">reactor</span>: A model <span class="hlt">reactor</span> for studying plasma nitriding processes using an active screen</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Hamann, S.; Börner, K.; Burlacov, I.; Spies, H.-J.; Strämke, M.; Strämke, S.; Röpcke, J.</p> <p>2015-12-01</p> <p>A laboratory scale plasma nitriding monitoring <span class="hlt">reactor</span> (PLANIMOR) has been designed to study the basics of active screen plasma nitriding (ASPN) processes. PLANIMOR consists of a tube <span class="hlt">reactor</span> vessel, made of borosilicate glass, enabling optical emission spectroscopy (OES) and infrared absorption spectroscopy. The linear setup of the electrode system of the <span class="hlt">reactor</span> has the advantages to apply the diagnostic approaches on each part of the plasma process, separately. Furthermore, possible changes of the electrical field and of the heat generation, as they could appear in down-scaled cylindrical ASPN <span class="hlt">reactors</span>, are avoided. PLANIMOR has been used for the nitriding of steel samples, achieving similar results as in an industrial scale ASPN <span class="hlt">reactor</span>. A compact spectrometer using an external cavity quantum cascade laser combined with an optical multi-pass cell has been applied for the detection of molecular reaction products. This allowed the determination of the concentrations of four stable molecular species (CH4, C2H2, HCN, and NH3). With the help of OES, the rotational temperature of the screen plasma could be determined.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.osti.gov/sciencecinema/biblio/1132838','SCIGOVIMAGE-SCICINEMA'); return false;" href="http://www.osti.gov/sciencecinema/biblio/1132838"><span>Small <span class="hlt">Reactor</span> for Deep Space Exploration</span></a></p> <p><a target="_blank" href="http://www.osti.gov/sciencecinema/">ScienceCinema</a></p> <p>none,</p> <p>2018-06-06</p> <p>This is the first demonstration of a space nuclear <span class="hlt">reactor</span> system to produce electricity in the United States since 1965, and an experiment demonstrated the first use of a heat pipe to cool a small nuclear <span class="hlt">reactor</span> and then harvest the heat to power a Stirling engine at the Nevada National Security Site's Device Assembly Facility confirms basic nuclear <span class="hlt">reactor</span> physics and heat transfer for a simple, reliable space power system.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6373454-investigation-report-reactor-mischarging-incident','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/6373454-investigation-report-reactor-mischarging-incident"><span>Investigation report: H <span class="hlt">Reactor</span> mischarging incident</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Vinther, A.P.</p> <p>1964-05-01</p> <p>All cold <span class="hlt">reactor</span> start-up procedures require the vertical safety rods (VSR) to be withdrawn in pairs with specific waiting periods between each pair withdrawal. This rod withdrawal procedure will assure an early and safe detection of <span class="hlt">reactor</span> criticality should <span class="hlt">reactor</span> reactivity conditions be different than predicted so that proper corrective actions can be taken. During the paired VSR removal of H <span class="hlt">reactor</span> on April 17, 1964, while preparing for <span class="hlt">reactor</span> start-up, an extremely low level rising period was detected with six VSR's still in the <span class="hlt">reactor</span>. The withdrawn VSR's were promptly re-inserted. During the next several days other process difficultiesmore » were encountered. H Processing personnel began investigating the possibility that a number of process tubes might have been mischarged; one shift's charging effort appeared to be suspect as longitudinal peaking appeared nearly twice as severe as normal in the distorted region. Following verification of a charging error in the suspect group of 171 tubes, that group of tubes was discharged and recharged with the proper charge make-up. On April 24, during VSR removal for start-up, low level criticality was detected with three VSR's still in the unit. The VSR's were re-inserted and Operational Physics analysis requested. Following installation of additional poisoning, the Operational Physics analysis uncovered a reactivity prediction error related to the prior operation with the skewed flux distribution. However, in this case, as on April 17, the procedural paired VSR withdrawal provided safe detection of the criticality condition in adequate time to take prompt corrective action. A successful <span class="hlt">reactor</span> start-up was then achieved later on April 24, and <span class="hlt">reactor</span> operation has been normal since that time. 4 figs.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017JPhCS.934a2004G','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017JPhCS.934a2004G"><span>Neutrino scattering and the <span class="hlt">reactor</span> antineutrino anomaly</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Garcés, Estela; Cañas, Blanca; Miranda, Omar; Parada, Alexander</p> <p>2017-12-01</p> <p>Low energy threshold <span class="hlt">reactor</span> experiments have the potential to give insight into the light sterile neutrino signal provided by the <span class="hlt">reactor</span> antineutrino anomaly and the gallium anomaly. In this work we analyze short baseline <span class="hlt">reactor</span> experiments that detect by elastic neutrino electron scattering in the context of a light sterile neutrino signal. We also analyze the sensitivity of experimental proposals of coherent elastic neutrino nucleus scattering (CENNS) detectors in order to exclude or confirm the sterile neutrino signal with <span class="hlt">reactor</span> antineutrinos.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19770066054&hterms=cycles+power+gases&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D10%26Ntt%3Dcycles%2Bpower%2Bgases','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19770066054&hterms=cycles+power+gases&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D10%26Ntt%3Dcycles%2Bpower%2Bgases"><span>Gaseous fuel <span class="hlt">reactors</span> for power systems</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Kendall, J. S.; Rodgers, R. J.</p> <p>1977-01-01</p> <p>Gaseous-fuel nuclear <span class="hlt">reactors</span> have significant advantages as energy sources for closed-cycle power systems. The advantages arise from the removal of temperature limits associated with conventional <span class="hlt">reactor</span> fuel elements, the wide variety of methods of extracting energy from fissioning gases, and inherent low fissile and fission product in-core inventory due to continuous fuel reprocessing. Example power cycles and their general performance characteristics are discussed. Efficiencies of gaseous fuel <span class="hlt">reactor</span> systems are shown to be high with resulting minimal environmental effects. A technical overview of the NASA-funded research program in gaseous fuel <span class="hlt">reactors</span> is described and results of recent tests of uranium hexafluoride (UF6)-fueled critical assemblies are presented.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/20050207458','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/20050207458"><span>Heat Pipe <span class="hlt">Reactor</span> Dynamic Response Tests: SAFE-100 <span class="hlt">Reactor</span> Core Prototype</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Bragg-Sitton, Shannon M.</p> <p>2005-01-01</p> <p>The SAFE-I00a test article at the NASA Marshall Space Flight Center was used to simulate a variety of potential <span class="hlt">reactor</span> transients; the SAFEl00a is a resistively heated, stainless-steel heat-pipe (HP)-<span class="hlt">reactor</span> core segment, coupled to a gas-flow heat exchanger (HX). For these transients the core power was controlled by a point kinetics model with reactivity feedback based on core average temperature; the neutron generation time and the temperature feedback coefficient are provided as model inputs. This type of non-nuclear test is expected to provide reasonable approximation of <span class="hlt">reactor</span> transient behavior because reactivity feedback is very simple in a compact fast <span class="hlt">reactor</span> (simple, negative, and relatively monotonic temperature feedback, caused mostly by thermal expansion) and calculations show there are no significant reactivity effects associated with fluid in the HP (the worth of the entire inventory of Na in the core is .<el, so fluid movement and temperature changes will cause very minor effects). In previous SAFE-100 tests, the point kinetics model was based on core thermal expansion via deflection measurements. It was found that core deflection was a strung function of how the SAFE-100 modules were fabricated and assembled (in terms of straightness, gaps, and other tolerances). To remove the added variable of how this particular core expands as compared to a different concept, it was decided to use a temperature based feedback model (based on several thermocouples placed throughout the core).</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/pages/biblio/1330747-antineutrino-monitoring-thorium-reactors','SCIGOV-DOEP'); return false;" href="https://www.osti.gov/pages/biblio/1330747-antineutrino-monitoring-thorium-reactors"><span>Antineutrino monitoring of thorium <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/pages">DOE PAGES</a></p> <p>Akindele, Oluwatomi A.; Bernstein, Adam; Norman, Eric B.</p> <p>2016-09-30</p> <p>Various groups have demonstrated that antineutrino monitoring can be successful in assessing the plutonium content in water-cooled nuclear <span class="hlt">reactors</span> for nonproliferation applications. New <span class="hlt">reactor</span> designs and concepts incorporate nontraditional fuel types and chemistry. Understanding how these properties affect the antineutrino emission from a <span class="hlt">reactor</span> can extend the applicability of antineutrino monitoring. Thorium molten salt <span class="hlt">reactors</span> breed 233U, that if diverted constitute a direct use material as defined by the International Atomic Energy Agency (IAEA). The antineutrino spectrum from the fission of 233U has been estimated for the first time, and the feasibility of detecting the diversion of 8 kg ofmore » 233U, within a 30 day timeliness goal has been evaluated. The antineutrino emission from a thorium <span class="hlt">reactor</span> operating under normal conditions is compared to a diversion scenario by evaluating the daily antineutrino count rate and the energy spectrum of the detected antineutrinos at a 25 m standoff. It was found that the diversion of a significant quantity of 233U could not be detected within the current IAEA timeliness detection goal using either tests. In conclusion, a rate-time based analysis exceeded the timeliness goal by 23 days, while a spectral based analysis exceeds this goal by 31 days.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2016JAP...120l4902A','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2016JAP...120l4902A"><span>Antineutrino monitoring of thorium <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Akindele, Oluwatomi A.; Bernstein, Adam; Norman, Eric B.</p> <p>2016-09-01</p> <p>Various groups have demonstrated that antineutrino monitoring can be successful in assessing the plutonium content in water-cooled nuclear <span class="hlt">reactors</span> for nonproliferation applications. New <span class="hlt">reactor</span> designs and concepts incorporate nontraditional fuel types and chemistry. Understanding how these properties affect the antineutrino emission from a <span class="hlt">reactor</span> can extend the applicability of antineutrino monitoring. Thorium molten salt <span class="hlt">reactors</span> breed 233U, that if diverted constitute a direct use material as defined by the International Atomic Energy Agency (IAEA). The antineutrino spectrum from the fission of 233U has been estimated for the first time, and the feasibility of detecting the diversion of 8 kg of 233U, within a 30 day timeliness goal has been evaluated. The antineutrino emission from a thorium <span class="hlt">reactor</span> operating under normal conditions is compared to a diversion scenario by evaluating the daily antineutrino count rate and the energy spectrum of the detected antineutrinos at a 25 m standoff. It was found that the diversion of a significant quantity of 233U could not be detected within the current IAEA timeliness detection goal using either tests. A rate-time based analysis exceeded the timeliness goal by 23 days, while a spectral based analysis exceeds this goal by 31 days.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.dtic.mil/docs/citations/ADA285943','DTIC-ST'); return false;" href="http://www.dtic.mil/docs/citations/ADA285943"><span>Northern Sea Route and <span class="hlt">Icebreaking</span> Technology</span></a></p> <p><a target="_blank" href="http://www.dtic.mil/">DTIC Science & Technology</a></p> <p></p> <p>1994-06-01</p> <p>waterlines at the extreme forward end, extended beam, a low stem angle with an ice-clearing forefoot , and a high flare angle below the water- line. The ice...world. Reports of protests and labor strikes , stemming from poor wages sectors of the economy. The Gross and living conditions, are common. With</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/1992snpw.conf..279B','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/1992snpw.conf..279B"><span>A novel plant protection strategy for transient <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Bhattacharyya, Samit K.; Lipinski, Walter C.; Hanan, Nelson A.</p> <p></p> <p>The present plant protection system (PPS) has been defined for use in the TREAT-upgrade (TU) <span class="hlt">reactor</span> for controlled transient operation of <span class="hlt">reactor</span>-fuel behavior testing under simulated <span class="hlt">reactor</span>-accident conditions. A PPS with energy-dependent trip set points lowered worst-case clad temperatures by as much as 180 K, relative to the use of conventional fixed-level trip set points. The multilayered multilevel protection strategy represents the state-of-the-art in terrestrial transient <span class="hlt">reactor</span> protection systems, and should be applicable to multi-MW space <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4256074','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4256074"><span><span class="hlt">REACTOR</span> MONITORING</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Bugbee, S.J.; Hanson, V.F.; Babcock, D.F.</p> <p>1959-02-01</p> <p>A neutron density inonitoring means for <span class="hlt">reactors</span> is described. According to this invention a tunnel is provided beneath and spaced from the active portion of the <span class="hlt">reactor</span> and extends beyond the opposite faces of the activc portion. Neutron beam holes are provided between the active portion and the tunnel and open into the tunnel near the middle thereof. A carriage operates back and forth in the tunnel and is adapted to convey a neutron detector, such as an ion chamber, and position it beneath one of the neutron beam holes. This arrangement affords convenient access of neutron density measuring instruments to a location wherein direct measurement of neutron density within the piles can be made and at the same time affords ample protection to operating personnel.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4196869','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4196869"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Grebe, J.J.</p> <p>1959-12-15</p> <p>A <span class="hlt">reactor</span> which is particularly adapted tu serve as a heat source for a nuclear powered alrcraft or rocket is described. The core of this <span class="hlt">reactor</span> consists of a porous refractory modera;or body which is impregnated with fissionable nuclei. The core is designed so that its surface forms tapered inlet and outlet ducts which are separated by the porous moderator body. In operation a gaseous working fluid is circulated through the inlet ducts to the surface of the moderator, enters and passes through the porous body, and is heated therein. The hot gas emerges into the outlet ducts and is available to provide thrust. The principle advantage is that tremendous quantities of gas can be quickly heated without suffering an excessive pressure drop.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2011AGUFMPA23A1752L','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2011AGUFMPA23A1752L"><span>Breaking the Ice: Strategies for Future European Research in the Polar Oceans - The AURORA BOREALIS Concept</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Lembke-Jene, L.; Biebow, N.; Wolff-Boenisch, B.; Thiede, J.; European Research Icebreaker Consortium</p> <p>2011-12-01</p> <p>Research vessels dedicated to work in polar ice-covered waters have only rarely been built. Their history began with Fritjof Nansen's FRAM, which he used for his famous first crossing of the Arctic Ocean 1893-1896. She served as example for the first generation of polar research vessels, at their time being modern instruments planned with foresight. Ice breaker technology has developed substantially since then. However, it took almost 80 years until this technical advance also reached polar research, when the Russian AKADEMIK FEDEROV, the German POLARSTERN, the Swedish ODEN and the USCG Cutter HEALY were built. All of these house modern laboratories, are <span class="hlt">ice-breakers</span> capable to move into the deep-Arctic during the summer time and represent the second generation of dedicated polar research vessels. Still, the increasing demand in polar marine research capacities by societies that call for action to better understand climate change, especially in the high latitudes is not matched by adequate facilities and resources. Today, no <span class="hlt">icebreaker</span> platform exists that is permanently available to the international science community for year-round expeditions into the central Arctic Ocean or heavily ice-infested waters of the polar Southern Ocean around Antarctica. The AURORA BOREALIS concept plans for a heavy research <span class="hlt">icebreaker</span>, which will enable polar scientists around the world to launch international research expeditions into the central Arctic Ocean and the Antarctic continental shelf seas autonomously during all seasons of the year. The European Research <span class="hlt">Icebreaker</span> Consortium - AURORA BOREALIS (ERICON-AB) was established in 2008 to plan the scientific, governance, financial, and legal frameworks needed for the construction and operation of this first multi-nationally owned and operated research <span class="hlt">icebreaker</span> and polar scientific drilling platform. By collaborating together and sharing common infrastructures it is envisioned that European nations make a major contribution to</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://images.nasa.gov/#/details-GRC-1970-C-00860.html','SCIGOVIMAGE-NASA'); return false;" href="https://images.nasa.gov/#/details-GRC-1970-C-00860.html"><span>Operators in the Plum Brook <span class="hlt">Reactor</span> Facility Control Room</span></a></p> <p><a target="_blank" href="https://images.nasa.gov/">NASA Image and Video Library</a></p> <p></p> <p>1970-03-21</p> <p>Donald Rhodes, left, and Clyde Greer, right, monitor the operation of the National Aeronautics and Space Administration’s (NASA) Plum Brook <span class="hlt">Reactor</span> Facility from the control room. The 60-megawatt test <span class="hlt">reactor</span>, NASA’s only <span class="hlt">reactor</span>, was the eighth largest test <span class="hlt">reactor</span> in the world. The facility was built by the Lewis Research Center in the late 1950s to study the effects of radiation on different materials that could be used to construct nuclear propulsion systems for aircraft or rockets. The <span class="hlt">reactor</span> went critical for the first time in 1961. For the next two years, two operators were on duty 24 hours per day working on the fission process until the <span class="hlt">reactor</span> reached its full-power level in 1963. <span class="hlt">Reactor</span> Operators were responsible for monitoring and controlling the <span class="hlt">reactor</span> systems. Once the <span class="hlt">reactor</span> was running under normal operating conditions, the work was relatively uneventful. Normally the <span class="hlt">reactor</span> was kept at a designated power level within certain limits. Occasionally the operators had to increase the power for a certain test. The shift supervisor and several different people would get together and discuss the change before boosting the power. All operators were required to maintain a <span class="hlt">Reactor</span> Operator License from the Atomic Energy Commission. The license included six months of training, an eight-hour written exam, a four-hour walkaround, and testing on the <span class="hlt">reactor</span> controls.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2011-title9-vol1/pdf/CFR-2011-title9-vol1-sec78-31.pdf','CFR2011'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2011-title9-vol1/pdf/CFR-2011-title9-vol1-sec78-31.pdf"><span>9 CFR 78.31 - Brucellosis <span class="hlt">reactor</span> swine.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2011&page.go=Go">Code of Federal Regulations, 2011 CFR</a></p> <p></p> <p>2011-01-01</p> <p>... 9 Animals and Animal Products 1 2011-01-01 2011-01-01 false Brucellosis <span class="hlt">reactor</span> swine. 78.31... Restrictions on Interstate Movement of Swine Because of Brucellosis § 78.31 Brucellosis <span class="hlt">reactor</span> swine. (a) Destination. Brucellosis <span class="hlt">reactor</span> swine may be moved interstate only for immediate slaughter as follows: (1...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2011-title9-vol1/pdf/CFR-2011-title9-vol1-sec78-22.pdf','CFR2011'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2011-title9-vol1/pdf/CFR-2011-title9-vol1-sec78-22.pdf"><span>9 CFR 78.22 - Brucellosis <span class="hlt">reactor</span> bison.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2011&page.go=Go">Code of Federal Regulations, 2011 CFR</a></p> <p></p> <p>2011-01-01</p> <p>... 9 Animals and Animal Products 1 2011-01-01 2011-01-01 false Brucellosis <span class="hlt">reactor</span> bison. 78.22... Restrictions on Interstate Movement of Bison Because of Brucellosis § 78.22 Brucellosis <span class="hlt">reactor</span> bison. (a) Destination. Brucellosis <span class="hlt">reactor</span> bison may be moved interstate only for immediate slaughter as follows: (1...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2010-title9-vol1/pdf/CFR-2010-title9-vol1-sec78-31.pdf','CFR'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2010-title9-vol1/pdf/CFR-2010-title9-vol1-sec78-31.pdf"><span>9 CFR 78.31 - Brucellosis <span class="hlt">reactor</span> swine.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2010&page.go=Go">Code of Federal Regulations, 2010 CFR</a></p> <p></p> <p>2010-01-01</p> <p>... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Brucellosis <span class="hlt">reactor</span> swine. 78.31... Restrictions on Interstate Movement of Swine Because of Brucellosis § 78.31 Brucellosis <span class="hlt">reactor</span> swine. (a) Destination. Brucellosis <span class="hlt">reactor</span> swine may be moved interstate only for immediate slaughter as follows: (1...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2011-title9-vol1/pdf/CFR-2011-title9-vol1-sec78-7.pdf','CFR2011'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2011-title9-vol1/pdf/CFR-2011-title9-vol1-sec78-7.pdf"><span>9 CFR 78.7 - Brucellosis <span class="hlt">reactor</span> cattle.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2011&page.go=Go">Code of Federal Regulations, 2011 CFR</a></p> <p></p> <p>2011-01-01</p> <p>... 9 Animals and Animal Products 1 2011-01-01 2011-01-01 false Brucellosis <span class="hlt">reactor</span> cattle. 78.7... Restrictions on Interstate Movement of Cattle Because of Brucellosis § 78.7 Brucellosis <span class="hlt">reactor</span> cattle. (a) Destination. Brucellosis <span class="hlt">reactor</span> cattle may be moved interstate only for immediate slaughter as follows: (1...</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_13");'>13</a></li> <li><a href="#" onclick='return showDiv("page_14");'>14</a></li> <li class="active"><span>15</span></li> <li><a href="#" onclick='return showDiv("page_16");'>16</a></li> <li><a href="#" onclick='return showDiv("page_17");'>17</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_15 --> <div id="page_16" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_14");'>14</a></li> <li><a href="#" onclick='return showDiv("page_15");'>15</a></li> <li class="active"><span>16</span></li> <li><a href="#" onclick='return showDiv("page_17");'>17</a></li> <li><a href="#" onclick='return showDiv("page_18");'>18</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="301"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2010-title9-vol1/pdf/CFR-2010-title9-vol1-sec78-7.pdf','CFR'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2010-title9-vol1/pdf/CFR-2010-title9-vol1-sec78-7.pdf"><span>9 CFR 78.7 - Brucellosis <span class="hlt">reactor</span> cattle.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2010&page.go=Go">Code of Federal Regulations, 2010 CFR</a></p> <p></p> <p>2010-01-01</p> <p>... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Brucellosis <span class="hlt">reactor</span> cattle. 78.7... Restrictions on Interstate Movement of Cattle Because of Brucellosis § 78.7 Brucellosis <span class="hlt">reactor</span> cattle. (a) Destination. Brucellosis <span class="hlt">reactor</span> cattle may be moved interstate only for immediate slaughter as follows: (1...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2010-title9-vol1/pdf/CFR-2010-title9-vol1-sec78-22.pdf','CFR'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2010-title9-vol1/pdf/CFR-2010-title9-vol1-sec78-22.pdf"><span>9 CFR 78.22 - Brucellosis <span class="hlt">reactor</span> bison.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2010&page.go=Go">Code of Federal Regulations, 2010 CFR</a></p> <p></p> <p>2010-01-01</p> <p>... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Brucellosis <span class="hlt">reactor</span> bison. 78.22... Restrictions on Interstate Movement of Bison Because of Brucellosis § 78.22 Brucellosis <span class="hlt">reactor</span> bison. (a) Destination. Brucellosis <span class="hlt">reactor</span> bison may be moved interstate only for immediate slaughter as follows: (1...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2012-title9-vol1/pdf/CFR-2012-title9-vol1-sec78-31.pdf','CFR2012'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2012-title9-vol1/pdf/CFR-2012-title9-vol1-sec78-31.pdf"><span>9 CFR 78.31 - Brucellosis <span class="hlt">reactor</span> swine.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2012&page.go=Go">Code of Federal Regulations, 2012 CFR</a></p> <p></p> <p>2012-01-01</p> <p>... 9 Animals and Animal Products 1 2012-01-01 2012-01-01 false Brucellosis <span class="hlt">reactor</span> swine. 78.31... Restrictions on Interstate Movement of Swine Because of Brucellosis § 78.31 Brucellosis <span class="hlt">reactor</span> swine. (a) Destination. Brucellosis <span class="hlt">reactor</span> swine may be moved interstate only for immediate slaughter as follows: (1...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2013-title9-vol1/pdf/CFR-2013-title9-vol1-sec78-31.pdf','CFR2013'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2013-title9-vol1/pdf/CFR-2013-title9-vol1-sec78-31.pdf"><span>9 CFR 78.31 - Brucellosis <span class="hlt">reactor</span> swine.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2013&page.go=Go">Code of Federal Regulations, 2013 CFR</a></p> <p></p> <p>2013-01-01</p> <p>... 9 Animals and Animal Products 1 2013-01-01 2013-01-01 false Brucellosis <span class="hlt">reactor</span> swine. 78.31... Restrictions on Interstate Movement of Swine Because of Brucellosis § 78.31 Brucellosis <span class="hlt">reactor</span> swine. (a) Destination. Brucellosis <span class="hlt">reactor</span> swine may be moved interstate only for immediate slaughter as follows: (1...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2014-title9-vol1/pdf/CFR-2014-title9-vol1-sec78-31.pdf','CFR2014'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2014-title9-vol1/pdf/CFR-2014-title9-vol1-sec78-31.pdf"><span>9 CFR 78.31 - Brucellosis <span class="hlt">reactor</span> swine.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2014&page.go=Go">Code of Federal Regulations, 2014 CFR</a></p> <p></p> <p>2014-01-01</p> <p>... 9 Animals and Animal Products 1 2014-01-01 2014-01-01 false Brucellosis <span class="hlt">reactor</span> swine. 78.31... Restrictions on Interstate Movement of Swine Because of Brucellosis § 78.31 Brucellosis <span class="hlt">reactor</span> swine. (a) Destination. Brucellosis <span class="hlt">reactor</span> swine may be moved interstate only for immediate slaughter as follows: (1...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/863782','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/863782"><span><span class="hlt">Reactor</span> apparatus</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Echtler, J. Paul</p> <p>1981-01-01</p> <p>A <span class="hlt">reactor</span> apparatus for hydrocracking a polynuclear aromatic hydrocarbonaceous feedstock to produce lighter hydrocarbon fuels by contacting the hydrocarbonaceous feedstock with hydrogen in the presence of a molten metal halide catalyst.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1418836','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1418836"><span>Seismic attenuation system for a nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Liszkai, Tamas; Cadell, Seth</p> <p></p> <p>A system for attenuating seismic forces includes a <span class="hlt">reactor</span> pressure vessel containing nuclear fuel and a containment vessel that houses the <span class="hlt">reactor</span> pressure vessel. Both the <span class="hlt">reactor</span> pressure vessel and the containment vessel include a bottom head. Additionally, the system includes a base support to contact a support surface on which the containment vessel is positioned in a substantially vertical orientation. An attenuation device is located between the bottom head of the <span class="hlt">reactor</span> pressure vessel and the bottom head of the containment vessel. Seismic forces that travel from the base support to the <span class="hlt">reactor</span> pressure vessel via the containment vesselmore » are attenuated by the attenuation device in a direction that is substantially lateral to the vertical orientation of the containment vessel.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6635354','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/6635354"><span>Reactivity control assembly for nuclear <span class="hlt">reactor</span>. [LMFBR</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Bollinger, L.R.</p> <p>1982-03-17</p> <p>This invention, which resulted from a contact with the United States Department of Energy, relates to a control mechanism for a nuclear <span class="hlt">reactor</span> and, more particularly, to an assembly for selectively shifting different numbers of reactivity modifying rods into and out of the core of a nuclear <span class="hlt">reactor</span>. It has been proposed heretofore to control the reactivity of a breeder <span class="hlt">reactor</span> by varying the depth of insertion of control rods (e.g., rods containing a fertile material such as ThO/sub 2/) in the core of the <span class="hlt">reactor</span>, thereby varying the amount of neutron-thermalizing coolant and the amount of neutron-capturing material in the core. This invention relates to a mechanism which can advantageously be used in this type of <span class="hlt">reactor</span> control system.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19720010194','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19720010194"><span>NASA-EPA automotive thermal <span class="hlt">reactor</span> technology program</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Blankenship, C. P.; Hibbard, R. R.</p> <p>1972-01-01</p> <p>The status of the NASA-EPA automotive thermal <span class="hlt">reactor</span> technology program is summarized. This program is concerned primarily with materials evaluation, <span class="hlt">reactor</span> design, and combustion kinetics. From engine dynamometer tests of candidate metals and coatings, two ferritic iron alloys (GE 1541 and Armco 18-SR) and a nickel-base alloy (Inconel 601) offer promise for <span class="hlt">reactor</span> use. None of the coatings evaluated warrant further consideration. Development studies on a ceramic thermal <span class="hlt">reactor</span> appear promising based on initial vehicle road tests. A chemical kinetic study has shown that gas temperatures of at least 900 K to 1000 K are required for the effective cleanup of carbon monoxide and hydrocarbons, but that higher temperatures require shorter combustion times and thus may permit smaller <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4164314','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4164314"><span>SUPERHEATING IN A BOILING WATER <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Treshow, M.</p> <p>1960-05-31</p> <p>A boiling-water <span class="hlt">reactor</span> is described in which the steam developed in the <span class="hlt">reactor</span> is superheated in the <span class="hlt">reactor</span>. This is accomplished by providing means for separating the steam from the water and passing the steam over a surface of the fissionable material which is not in contact with the water. Specifically water is boiled on the outside of tubular fuel elements and the steam is superheated on the inside of the fuel elements.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/863914','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/863914"><span>Nuclear <span class="hlt">reactor</span> shield including magnesium oxide</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Rouse, Carl A.; Simnad, Massoud T.</p> <p>1981-01-01</p> <p>An improvement in nuclear <span class="hlt">reactor</span> shielding of a type used in <span class="hlt">reactor</span> applications involving significant amounts of fast neutron flux, the <span class="hlt">reactor</span> shielding including means providing structural support, neutron moderator material, neutron absorber material and other components as described below, wherein at least a portion of the neutron moderator material is magnesium in the form of magnesium oxide either alone or in combination with other moderator materials such as graphite and iron.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5445106','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/5445106"><span>Fission control system for nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Conley, G.H.; Estes, G.P.</p> <p></p> <p>Control system for nuclear <span class="hlt">reactor</span> comprises a first set of reactivity modifying rods fixed in a <span class="hlt">reactor</span> core with their upper ends stepped in height across the core, and a second set of reactivity modifying rods movable vertically within the <span class="hlt">reactor</span> core and having their lower ends stepped to correspond with the stepped arrangement of the first set of rods, pairs of the rods of the first and second sets being in coaxial alignment.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/20976574','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/20976574"><span><span class="hlt">Reactors</span> are indispensable for radioisotope production.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Mushtaq, Ahmad</p> <p>2010-12-01</p> <p>Radioisotopes can be produced by <span class="hlt">reactors</span> and accelerators. For certain isotopes there could be an advantage to a certain production method. However, nowadays many reports suggest, that useful isotopes needed in medicine, industry and research could be produced efficiently and dependence on <span class="hlt">reactors</span> using enriched U-235 may be eliminated. In my view <span class="hlt">reactors</span> and accelerators will continue to play their role side by side in the supply of suitable and economical sources of isotopes.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4296373','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4296373"><span>METHOD OF OPERATING NUCLEAR <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Untermyer, S.</p> <p>1958-10-14</p> <p>A method is presented for obtaining enhanced utilization of natural uranium in heavy water moderated nuclear <span class="hlt">reactors</span> by charging the <span class="hlt">reactor</span> with an equal number of fuel elements formed of natural uranium and of fuel elements formed of uranium depleted in U/sup 235/ to the extent that the combination will just support a chain reaction. The <span class="hlt">reactor</span> is operated until the rate of burnup of plutonium equals its rate of production, the fuel elements are processed to recover plutonium, the depleted uranium is discarded, and the remaining uranium is formed into fuel elements. These fuel elements are charged into a <span class="hlt">reactor</span> along with an equal number of fuel elements formed of uranium depleted in U/sup 235/ to the extent that the combination will just support a chain reaction, and reuse of the uranium is continued as aforesaid until it wlll no longer support a chain reaction when combined with an equal quantity of natural uranium.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2011honc.book.2663A','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2011honc.book.2663A"><span>Developments and Tendencies in Fission <span class="hlt">Reactor</span> Concepts</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Adamov, E. O.; Fuji-Ie, Y.</p> <p></p> <p>This chapter describes, in two parts, new-generation nuclear energy systems that are required to be in harmony with nature and to make full use of nuclear resources. The issues of transmutation and containment of radioactive waste will also be addressed. After a short introduction to the first part, Sect. 58.1.2 will detail the requirements these systems must satisfy on the basic premise of peaceful use of nuclear energy. The expected designs themselves are described in Sect. 58.1.3. The subsequent sections discuss various types of advanced <span class="hlt">reactor</span> systems. Section 58.1.4 deals with the light water <span class="hlt">reactor</span> (LWR) whose performance is still expected to improve, which would extend its application in the future. The supercritical-water-cooled <span class="hlt">reactor</span> (SCWR) will also be shortly discussed. Section 58.1.5 is mainly on the high temperature gas-cooled <span class="hlt">reactor</span> (HTGR), which offers efficient and multipurpose use of nuclear energy. The gas-cooled fast <span class="hlt">reactor</span> (GFR) is also included. Section 58.1.6 focuses on the sodium-cooled fast <span class="hlt">reactor</span> (SFR) as a promising concept for advanced nuclear <span class="hlt">reactors</span>, which may help both to achieve expansion of energy sources and environmental protection thus contributing to the sustainable development of mankind. The molten-salt <span class="hlt">reactor</span> (MSR) is shortly described in Sect. 58.1.7. The second part of the chapter deals with <span class="hlt">reactor</span> systems of a new generation, which are now found at the research and development (R&D) stage and in the medium term of 20-30 years can shape up as reliable, economically efficient, and environmentally friendly energy sources. They are viewed as technologies of cardinal importance, capable of resolving the problems of fuel resources, minimizing the quantities of generated radioactive waste and the environmental impacts, and strengthening the regime of nonproliferation of the materials suitable for nuclear weapons production. Particular attention has been given to naturally safe fast <span class="hlt">reactors</span> with a closed fuel cycle (CFC</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4222512','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4222512"><span>NEUTRON DENSITY CONTROL IN A NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Young, G.J.</p> <p>1959-06-30</p> <p>The method and means for controlling the neutron density in a nuclear <span class="hlt">reactor</span> is described. It describes the method and means for flattening the neutron density distribution curve across the <span class="hlt">reactor</span> by spacing the absorbing control members to varying depths in the central region closer to the center than to the periphery of the active portion of the <span class="hlt">reactor</span> to provide a smaller neutron reproduction ratio in the region wherein the members are inserted, than in the remainder of the <span class="hlt">reactor</span> thereby increasing the over-all potential power output.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/22535255-dismantling-nuclear-research-reactor-thetis','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/22535255-dismantling-nuclear-research-reactor-thetis"><span>Dismantling the nuclear research <span class="hlt">reactor</span> Thetis</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Michiels, P.</p> <p></p> <p>The research <span class="hlt">reactor</span> Thetis, in service since 1967 and stopped in 2003, is part of the laboratories of the institution of nuclear science of the University of Ghent. The <span class="hlt">reactor</span>, of the pool-type, was used as a neutron-source for the production of radio-isotopes and for activation analyses. The <span class="hlt">reactor</span> is situated in a water pool with inner diameter of 3 m. and a depth of 7.5 m. The <span class="hlt">reactor</span> core is situated 5.3 m under water level. Besides the <span class="hlt">reactor</span>, the pool contains pneumatic loops, handling tools, graphite blocks for neutron moderation and other experimental equipment. The building houses storagemore » rooms for fissile material and sources, a pneumatic circuit for transportation of samples, primary and secondary cooling circuits, water cleaning resin circuits, a ventilation system and other necessary devices. Because of the experimental character of the <span class="hlt">reactor</span>, laboratories with glove boxes and other tools were needed and are included in the dismantling program. The building is in 3 levels with a crawl-space. The ground-floor contains the ventilation installation, the purification circuits with tanks, cooling circuits and pneumatic transport system. On the first floor, around the <span class="hlt">reactor</span> hall, the control-room, visiting area, end-station for pneumatic transport, waste-storage room, fuel storage room and the labs are located. The second floor contains a few laboratories and end stations of the two high speed transfer tubes. The lowest level of the pool is situated under ground level. The <span class="hlt">reactor</span> has been operated at a power of 150 kW and had a max operating power of 250 kW. Belgoprocess has been selected to decommission the <span class="hlt">reactor</span>, the labs, storage halls and associated circuits to free release the building for conventional reuse and for the removal of all its internals as legal defined. Besides the dose-rate risk and contamination risk, there is also an asbestos risk of contamination. During construction of the installation, asbestos-containing materials</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/10135614','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/10135614"><span>Nuclear <span class="hlt">reactors</span> built, being built, or planned, 1991</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Simpson, B.</p> <p>1992-07-01</p> <p>This document contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1991. The book is divided into three major sections: Section 1 consists of a <span class="hlt">reactor</span> locator map and <span class="hlt">reactor</span> tables; Section 2 includes nuclear <span class="hlt">reactors</span> that are operating, being built, or planned; and Section 3 includes <span class="hlt">reactors</span> that have been shut down permanently or dismantled. Sections 2 and 3 contain the following classification of <span class="hlt">reactors</span>: Civilian, Production, Military, Export, and Critical Assembly. Export <span class="hlt">reactor</span> refers to a <span class="hlt">reactor</span> for which the principal nuclear contractor ismore » an American company -- working either independently or in cooperation with a foreign company (Part 4, in each section). Critical assembly refers to an assembly of fuel and assembly of fuel and moderator that requires an external source of neutrons to initiate and maintain fission. A critical assembly is used for experimental measurements (Part 5).« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2012NuPhS.229..101B','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2012NuPhS.229..101B"><span><span class="hlt">Reactor</span> Monitoring with Antineutrinos - A Progress Report</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Bernstein, Adam</p> <p>2012-08-01</p> <p>The <span class="hlt">Reactor</span> Safeguards regime is the name given to a set of protocols and technologies used to monitor the consumption and production of fissile materials in nuclear <span class="hlt">reactors</span>. The Safeguards regime is administered by the International Atomic Energy Agency (IAEA), and is an essential component of the global Treaty on Nuclear Nonproliferation, recently renewed by its 189 remaining signators. (The 190th, North Korea, withdrew from the Treaty in 2003). Beginning in Russia in the 1980s, a number of researchers worldwide have experimentally demonstrated the potential of cubic meter scale antineutrino detectors for non-intrusive real-time monitoring of fissile inventories and power output of <span class="hlt">reactors</span>. The detectors built so far have operated tens of meters from a <span class="hlt">reactor</span> core, outside of the containment dome, largely unattended and with remote data acquisition for an entire 1.5 year <span class="hlt">reactor</span> cycle, and have achieved levels of sensitivity to fissile content of potential interest for the IAEA safeguards regime. In this article, I will describe the unique advantages of antineutrino detectors for cooperative monitoring, consider the prospects and benefits of increasing the range of detectability for small <span class="hlt">reactors</span>, and provide a partial survey of ongoing global research aimed at improving near-field and far field monitoring and discovery of nuclear <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4013735-critical-experiment-tank-cet-reactor-hazards-summary','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/4013735-critical-experiment-tank-cet-reactor-hazards-summary"><span>CRITICAL EXPERIMENT TANK (CET) <span class="hlt">REACTOR</span> HAZARDS SUMMARY</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Becar, N.J.; Kunze, J.F.; Pincock, G..D.</p> <p>1961-03-31</p> <p>The Critical Experiment Tank (CET) <span class="hlt">reactor</span> assembly, the associated systems, and the Low Power Test Facility in which the <span class="hlt">reactor</span> is to be operated are described. An evaluation and summary of the hazards associated with the operation of the CET <span class="hlt">reactor</span> in the LPTF at the ldsho Test Station are also presented. (auth)</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_14");'>14</a></li> <li><a href="#" onclick='return showDiv("page_15");'>15</a></li> <li class="active"><span>16</span></li> <li><a href="#" onclick='return showDiv("page_17");'>17</a></li> <li><a href="#" onclick='return showDiv("page_18");'>18</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_16 --> <div id="page_17" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_15");'>15</a></li> <li><a href="#" onclick='return showDiv("page_16");'>16</a></li> <li class="active"><span>17</span></li> <li><a href="#" onclick='return showDiv("page_18");'>18</a></li> <li><a href="#" onclick='return showDiv("page_19");'>19</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="321"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://eric.ed.gov/?q=chemical+AND+engineering+AND+reactions&pg=6&id=EJ235181','ERIC'); return false;" href="https://eric.ed.gov/?q=chemical+AND+engineering+AND+reactions&pg=6&id=EJ235181"><span>Chemical <span class="hlt">Reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.eric.ed.gov/ERICWebPortal/search/extended.jsp?_pageLabel=advanced">ERIC Educational Resources Information Center</a></p> <p>Kenney, C. N.</p> <p>1980-01-01</p> <p>Describes a course, including content, reading list, and presentation on chemical <span class="hlt">reactors</span> at Cambridge University, England. A brief comparison of chemical engineering education between the United States and England is also given. (JN)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4111740','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4111740"><span>NEUTRONIC <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wigner, E.P.</p> <p>1960-11-22</p> <p>A nuclear <span class="hlt">reactor</span> is described wherein horizontal rods of thermal- neutron-fissionable material are disposed in a body of heavy water and extend through and are supported by spaced parallel walls of graphite.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19910000272&hterms=pyrolysis&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D80%26Ntt%3Dpyrolysis','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19910000272&hterms=pyrolysis&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D80%26Ntt%3Dpyrolysis"><span>Silane-Pyrolysis <span class="hlt">Reactor</span> With Nonuniform Heating</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Iya, Sridhar K.</p> <p>1991-01-01</p> <p>Improved <span class="hlt">reactor</span> serves as last stage in system processing metallurgical-grade silicon feedstock into silicon powder of ultrahigh purity. Silane pyrolized to silicon powder and hydrogen gas via homogeneous decomposition reaction in free space. Features set of individually adjustable electrical heaters and purge flow of hydrogen to improve control of pyrolysis conditions. Power supplied to each heater set in conjunction with flow in <span class="hlt">reactor</span> to obtain desired distribution of temperature as function of position along <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5800136-wpi-reactor-readying-next-generation','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/5800136-wpi-reactor-readying-next-generation"><span>The WPI <span class="hlt">reactor</span>-readying for the next generation</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Bobek, L.M.</p> <p>1993-01-01</p> <p>Built in 1959, the 10-kW open-pool nuclear training <span class="hlt">reactor</span> at Worcester Polytechnic Institute (WPI) was one of the first such facilities in the nation located on a university campus. Since then, the <span class="hlt">reactor</span> and its related facilities have been used to train two generations of nuclear engineers and scientists for the nuclear industry. With the use of nuclear technology playing an increasing role in many segments of the economy, WPI with its nuclear <span class="hlt">reactor</span> facility is committed to continuing its mission of training future nuclear engineers and scientists. The WPI <span class="hlt">reactor</span> includes a 6-in. beam port, graphite thermal column, andmore » in-core sample facility. The <span class="hlt">reactor</span>, housed in an open 8000-gal tank of water, is designed so that the core is readily accessible. Both the control console and the peripheral counting equipment used for student projects and laboratory exercises are located in the <span class="hlt">reactor</span> room. This arrangement provides convenience and flexibility in using the <span class="hlt">reactor</span> for foil activations in neutron flux measurements, diffusion measurements, radioactive decay measurements, and the neutron activation of samples for analysis. In 1988, the <span class="hlt">reactor</span> was successfully converted to low-enriched uranium fuel.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/198276','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/198276"><span>Oxidative coupling of methane using inorganic membrane <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Ma, Y.H.; Moser, W.R.; Dixon, A.G.</p> <p>1995-12-31</p> <p>The goal of this research is to improve the oxidative coupling of methane in a catalytic inorganic membrane <span class="hlt">reactor</span>. A specific target is to achieve conversion of methane to C{sub 2} hydrocarbons at very high selectivity and relatively higher yields than in fixed bed <span class="hlt">reactors</span> by controlling the oxygen supply through the membrane. A membrane <span class="hlt">reactor</span> has the advantage of precisely controlling the rate of delivery of oxygen to the catalyst. This facility permits balancing the rate of oxidation and reduction of the catalyst. In addition, membrane <span class="hlt">reactors</span> minimize the concentration of gas phase oxygen thus reducing non selective gasmore » phase reactions, which are believed to be a main route for formation of CO{sub x} products. Such gas phase reactions are a cause for decreased selectivity in oxidative coupling of methane in conventional flow <span class="hlt">reactors</span>. Membrane <span class="hlt">reactors</span> could also produce higher product yields by providing better distribution of the reactant gases over the catalyst than the conventional plug flow <span class="hlt">reactors</span>. Modeling work which aimed at predicting the observed experimental trends in porous membrane <span class="hlt">reactors</span> was also undertaken in this research program.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866291','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866291"><span>Weld monitor and failure detector for nuclear <span class="hlt">reactor</span> system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Sutton, Jr., Harry G.</p> <p>1987-01-01</p> <p>Critical but inaccessible welds in a nuclear <span class="hlt">reactor</span> system are monitored throughout the life of the <span class="hlt">reactor</span> by providing small aperture means projecting completely through the <span class="hlt">reactor</span> vessel wall and also through the weld or welds to be monitored. The aperture means is normally sealed from the atmosphere within the <span class="hlt">reactor</span>. Any incipient failure or cracking of the weld will cause the environment contained within the <span class="hlt">reactor</span> to pass into the aperture means and thence to the outer surface of the <span class="hlt">reactor</span> vessel where its presence is readily detected.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/863002','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/863002"><span>Nuclear <span class="hlt">reactor</span> apparatus</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wade, Elman E.</p> <p>1978-01-01</p> <p>A lifting, rotating and sealing apparatus for nuclear <span class="hlt">reactors</span> utilizing rotating plugs above the nuclear <span class="hlt">reactor</span> core. This apparatus permits rotation of the plugs to provide under the plug refueling of a nuclear core. It also provides a means by which positive top core holddown can be utilized. Both of these operations are accomplished by means of the apparatus lifting the top core holddown structure off the nuclear core while stationary, and maintaining this structure in its elevated position during plug rotation. During both of these operations, the interface between the rotating member and its supporting member is sealingly maintained.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/868681','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/868681"><span><span class="hlt">Reactor</span> for exothermic reactions</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Smith, Jr., Lawrence A.; Hearn, Dennis; Jones, Jr., Edward M.</p> <p>1993-01-01</p> <p>A liquid phase process for oligomerization of C.sub.4 and C.sub.5 isoolefins or the etherification thereof with C.sub.1 to C.sub.6 alcohols wherein the reactants are contacted in a <span class="hlt">reactor</span> with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120.degree. to 300.degree. F. Wherein the improvement is the operation of the <span class="hlt">reactor</span> at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the <span class="hlt">reactor</span> is controlled.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6061806','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/6061806"><span><span class="hlt">Reactor</span> for exothermic reactions</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Smith, L.A. Jr.; Hearn, D.; Jones, E.M. Jr.</p> <p>1993-03-02</p> <p>A liquid phase process is described for oligomerization of C[sub 4] and C[sub 5] isoolefins or the etherification thereof with C[sub 1] to C[sub 6] alcohols wherein the reactants are contacted in a <span class="hlt">reactor</span> with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120 to 300 F. Wherein the improvement is the operation of the <span class="hlt">reactor</span> at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the <span class="hlt">reactor</span> is controlled.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/984450','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/984450"><span>Optimally moderated nuclear fission <span class="hlt">reactor</span> and fuel source therefor</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ougouag, Abderrafi M [Idaho Falls, ID; Terry, William K [Shelley, ID; Gougar, Hans D [Idaho Falls, ID</p> <p>2008-07-22</p> <p>An improved nuclear fission <span class="hlt">reactor</span> of the continuous fueling type involves determining an asymptotic equilibrium state for the nuclear fission <span class="hlt">reactor</span> and providing the <span class="hlt">reactor</span> with a moderator-to-fuel ratio that is optimally moderated for the asymptotic equilibrium state of the nuclear fission <span class="hlt">reactor</span>; the fuel-to-moderator ratio allowing the nuclear fission <span class="hlt">reactor</span> to be substantially continuously operated in an optimally moderated state.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/22482641-plasma-nitriding-monitoring-reactor-model-reactor-studying-plasma-nitriding-processes-using-active-screen','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/22482641-plasma-nitriding-monitoring-reactor-model-reactor-studying-plasma-nitriding-processes-using-active-screen"><span>Plasma nitriding monitoring <span class="hlt">reactor</span>: A model <span class="hlt">reactor</span> for studying plasma nitriding processes using an active screen</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Hamann, S., E-mail: hamann@inp-greifswald.de; Röpcke, J.; Börner, K.</p> <p>2015-12-15</p> <p>A laboratory scale plasma nitriding monitoring <span class="hlt">reactor</span> (PLANIMOR) has been designed to study the basics of active screen plasma nitriding (ASPN) processes. PLANIMOR consists of a tube <span class="hlt">reactor</span> vessel, made of borosilicate glass, enabling optical emission spectroscopy (OES) and infrared absorption spectroscopy. The linear setup of the electrode system of the <span class="hlt">reactor</span> has the advantages to apply the diagnostic approaches on each part of the plasma process, separately. Furthermore, possible changes of the electrical field and of the heat generation, as they could appear in down-scaled cylindrical ASPN <span class="hlt">reactors</span>, are avoided. PLANIMOR has been used for the nitriding of steelmore » samples, achieving similar results as in an industrial scale ASPN <span class="hlt">reactor</span>. A compact spectrometer using an external cavity quantum cascade laser combined with an optical multi-pass cell has been applied for the detection of molecular reaction products. This allowed the determination of the concentrations of four stable molecular species (CH{sub 4}, C{sub 2}H{sub 2}, HCN, and NH{sub 3}). With the help of OES, the rotational temperature of the screen plasma could be determined.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/865893','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/865893"><span>Lateral restraint assembly for <span class="hlt">reactor</span> core</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Gorholt, Wilhelm; Luci, Raymond K.</p> <p>1986-01-01</p> <p>A restraint assembly for use in restraining lateral movement of a <span class="hlt">reactor</span> core relative to a <span class="hlt">reactor</span> vessel wherein a plurality of restraint assemblies are interposed between the <span class="hlt">reactor</span> core and the <span class="hlt">reactor</span> vessel in circumferentially spaced relation about the core. Each lateral restraint assembly includes a face plate urged against the outer periphery of the core by a plurality of compression springs which enable radial preloading of outer reflector blocks about the core and resist low-level lateral motion of the core. A fixed radial key member cooperates with each face plate in a manner enabling vertical movement of the face plate relative to the key member but restraining movement of the face plate transverse to the key member in a plane transverse to the center axis of the core. In this manner, the key members which have their axes transverse to or subtending acute angles with the direction of a high energy force tending to move the core laterally relative to the <span class="hlt">reactor</span> vessel restrain such lateral movement.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/22212792-core-follow-calculation-ntracer-numerical-reactor-verification-using-power-reactor-measurement-data','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/22212792-core-follow-calculation-ntracer-numerical-reactor-verification-using-power-reactor-measurement-data"><span>Core follow calculation with the nTRACER numerical <span class="hlt">reactor</span> and verification using power <span class="hlt">reactor</span> measurement data</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Jung, Y. S.; Joo, H. G.; Yoon, J. I.</p> <p></p> <p>The nTRACER direct whole core transport code employing the planar MOC solution based 3-D calculation method, the subgroup method for resonance treatment, the Krylov matrix exponential method for depletion, and a subchannel thermal/hydraulic calculation solver was developed for practical high-fidelity simulation of power <span class="hlt">reactors</span>. Its accuracy and performance is verified by comparing with the measurement data obtained for three pressurized water <span class="hlt">reactor</span> cores. It is demonstrated that accurate and detailed multi-physic simulation of power <span class="hlt">reactors</span> is practically realizable without any prior calculations or adjustments. (authors)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/10106698','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/10106698"><span>Laboratory instrumentation modernization at the WPI Nuclear <span class="hlt">Reactor</span> Facility</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Not Available</p> <p>1995-01-01</p> <p>With partial funding from the Department of Energy (DOE) University <span class="hlt">Reactor</span> Instrumentation Program several laboratory instruments utilized by students and researchers at the WPI Nuclear <span class="hlt">Reactor</span> Facility have been upgraded or replaced. Designed and built by General Electric in 1959, the open pool nuclear training <span class="hlt">reactor</span> at WPI was one of the first such facilities in the nation located on a university campus. Devoted to undergraduate use, the <span class="hlt">reactor</span> and its related facilities have been since used to train two generations of nuclear engineers and scientists for the nuclear industry. The low power output of the <span class="hlt">reactor</span> and an ergonomicmore » facility design make it an ideal tool for undergraduate nuclear engineering education and other training. The <span class="hlt">reactor</span>, its control system, and the associate laboratory equipment are all located in the same room. Over the years, several important milestones have taken place at the WPI <span class="hlt">reactor</span>. In 1969, the <span class="hlt">reactor</span> power level was upgraded from 1 kW to 10 kW. The <span class="hlt">reactor`s</span> Nuclear Regulatory Commission operating license was renewed for 20 years in 1983. In 1988, under DOE Grant No. DE-FG07-86ER75271, the <span class="hlt">reactor</span> was converted to low-enriched uranium fuel. In 1992, again with partial funding from DOE (Grant No. DE-FG02-90ER12982), the original control console was replaced.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4307535','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4307535"><span><span class="hlt">REACTOR</span> UNLOADING</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Leverett, M.C.</p> <p>1958-02-18</p> <p>This patent is related to gas cooled <span class="hlt">reactors</span> wherein the fuel elements are disposed in vertical channels extending through the <span class="hlt">reactor</span> core, the cooling gas passing through the channels from the bottom to the top of the core. The invention is a means for unloading the fuel elements from the core and comprises dump values in the form of flat cars mounted on wheels at the bottom of the core structure which support vertical stacks of fuel elements. When the flat cars are moved, either manually or automatically, for normal unloading purposes, or due to a rapid rise in the reproduction ratio within the core, the fuel elements are permtted to fall by gravity out of the core structure thereby reducing the reproduction ratio or stopping the reaction as desired.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/21144201-international-research-reactor-decommissioning-project','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/21144201-international-research-reactor-decommissioning-project"><span>International Research <span class="hlt">Reactor</span> Decommissioning Project</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Leopando, Leonardo; Warnecke, Ernst</p> <p>2008-01-15</p> <p>Many research <span class="hlt">reactors</span> have been or will be shut down and are candidates for decommissioning. Most of the respective countries neither have a decommissioning policy nor the required expertise and funds to effectively implement a decommissioning project. The IAEA established the Research <span class="hlt">Reactor</span> Decommissioning Demonstration Project (R{sup 2}D{sup 2}P) to help answer this need. It was agreed to involve the Philippine Research <span class="hlt">Reactor</span> (PRR-1) as model <span class="hlt">reactor</span> to demonstrate 'hands-on' experience as it is just starting the decommissioning process. Other facilities may be included in the project as they fit into the scope of R{sup 2}D{sup 2}P and complement tomore » the PRR-1 decommissioning activities. The key outcome of the R{sup 2}D{sup 2}P will be the decommissioning of the PRR-1 <span class="hlt">reactor</span>. On the way to this final goal the preparation of safety related documents (i.e., decommissioning plan, environmental impact assessment, safety analysis report, health and safety plan, cost estimate, etc.) and the licensing process as well as the actual dismantling activities could provide a model to other countries involved in the project. It is expected that the R{sup 2}D{sup 2}P would initiate activities related to planning and funding of decommissioning activities in the participating countries if that has not yet been done.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/26029199','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/26029199"><span>Simplifying microbial electrosynthesis <span class="hlt">reactor</span> design.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Giddings, Cloelle G S; Nevin, Kelly P; Woodward, Trevor; Lovley, Derek R; Butler, Caitlyn S</p> <p>2015-01-01</p> <p>Microbial electrosynthesis, an artificial form of photosynthesis, can efficiently convert carbon dioxide into organic commodities; however, this process has only previously been demonstrated in <span class="hlt">reactors</span> that have features likely to be a barrier to scale-up. Therefore, the possibility of simplifying <span class="hlt">reactor</span> design by both eliminating potentiostatic control of the cathode and removing the membrane separating the anode and cathode was investigated with biofilms of Sporomusa ovata. S. ovata reduces carbon dioxide to acetate and acts as the microbial catalyst for plain graphite stick cathodes as the electron donor. In traditional 'H-cell' <span class="hlt">reactors</span>, where the anode and cathode chambers were separated with a proton-selective membrane, the rates and columbic efficiencies of microbial electrosynthesis remained high when electron delivery at the cathode was powered with a direct current power source rather than with a potentiostat-poised cathode utilized in previous studies. A membrane-less <span class="hlt">reactor</span> with a direct-current power source with the cathode and anode positioned to avoid oxygen exposure at the cathode, retained high rates of acetate production as well as high columbic and energetic efficiencies. The finding that microbial electrosynthesis is feasible without a membrane separating the anode from the cathode, coupled with a direct current power source supplying the energy for electron delivery, is expected to greatly simplify future <span class="hlt">reactor</span> design and lower construction costs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4704362','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4704362"><span>SIMPLIFIED SODIUM GRAPHITE <span class="hlt">REACTOR</span> SYSTEM</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Dickinson, R.W.</p> <p>1963-03-01</p> <p>This patent relates to a nuclear power <span class="hlt">reactor</span> comprising a <span class="hlt">reactor</span> vessel, shielding means positioned at the top of said vessel, means sealing said <span class="hlt">reactor</span> vessel to said shielding means, said vessel containing a quantity of sodium, a core tank, unclad graphite moderator disposed in said tank, means including a plurality of process tubes traversing said tank for isolating said graphite from said sodium, fuel elements positioned in said process tubes, said core tank being supported in spaced relation to the walls and bottom of said <span class="hlt">reactor</span> vessel and below the level of said sodium, neutron shielding means positioned adjacent said core tank between said core tank and the walls of said vessel, said neutron shielding means defining an annuiar volume adjacent the inside wall of said <span class="hlt">reactor</span> vessel, inlet plenum means below said core tank for providing a passage between said annular volume and said process tubes, heat exchanger means removably supported from the first-named shielding means and positioned in said annular volume, and means for circulating said sodium over said neutron shielding means down through said heat exchanger, across said inlet plenum and upward through said process tubes, said last-named means including electromagnetic pumps located outside said vessel and supported on said vessel wall between said heat exchanger means and said inlet plenum means. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4799044','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4799044"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Sherman, J.; Sharbaugh, J.E.; Fauth, W.L. Jr.; Palladino, N.J.; DeHuff, P.G.</p> <p>1962-10-23</p> <p>A nuclear <span class="hlt">reactor</span> incorporating seed and blanket assemblies is designed. Means are provided for obtaining samples of the coolant from the blanket assemblies and for varying the flow of coolant through the blanket assemblies. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/27108375','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/27108375"><span>Numerical study of the effects of lamp configuration and <span class="hlt">reactor</span> wall roughness in an open channel water disinfection UV <span class="hlt">reactor</span>.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Sultan, Tipu</p> <p>2016-07-01</p> <p>This article describes the assessment of a numerical procedure used to determine the UV lamp configuration and surface roughness effects on an open channel water disinfection UV <span class="hlt">reactor</span>. The performance of the open channel water disinfection UV <span class="hlt">reactor</span> was numerically analyzed on the basis of the performance indictor reduction equivalent dose (RED). The RED values were calculated as a function of the Reynolds number to monitor the performance. The flow through the open channel UV <span class="hlt">reactor</span> was modelled using a k-ε model with scalable wall function, a discrete ordinate (DO) model for fluence rate calculation, a volume of fluid (VOF) model to locate the unknown free surface, a discrete phase model (DPM) to track the pathogen transport, and a modified law of the wall to incorporate the <span class="hlt">reactor</span> wall roughness effects. The performance analysis was carried out using commercial CFD software (ANSYS Fluent 15.0). Four case studies were analyzed based on open channel UV <span class="hlt">reactor</span> type (horizontal and vertical) and lamp configuration (parallel and staggered). The results show that lamp configuration can play an important role in the performance of an open channel water disinfection UV <span class="hlt">reactor</span>. The effects of the <span class="hlt">reactor</span> wall roughness were Reynolds number dependent. The proposed methodology is useful for performance optimization of an open channel water disinfection UV <span class="hlt">reactor</span>. Copyright © 2016 Elsevier Ltd. All rights reserved.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_15");'>15</a></li> <li><a href="#" onclick='return showDiv("page_16");'>16</a></li> <li class="active"><span>17</span></li> <li><a href="#" onclick='return showDiv("page_18");'>18</a></li> <li><a href="#" onclick='return showDiv("page_19");'>19</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_17 --> <div id="page_18" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_16");'>16</a></li> <li><a href="#" onclick='return showDiv("page_17");'>17</a></li> <li class="active"><span>18</span></li> <li><a href="#" onclick='return showDiv("page_19");'>19</a></li> <li><a href="#" onclick='return showDiv("page_20");'>20</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="341"> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2018JCrGr.489...68G','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2018JCrGr.489...68G"><span>Numerical Simulations of a 96-rod Polysilicon CVD <span class="hlt">Reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Guoqiang, Tang; Cong, Chen; Yifang, Cai; Bing, Zong; Yanguo, Cai; Tihu, Wang</p> <p>2018-05-01</p> <p>With the rapid development of the photovoltaic industry, pressurized Siemens belljar-type polysilicon CVD <span class="hlt">reactors</span> have been enlarged from 24 rods to 96 rods in less than 10 years aimed at much greater single-<span class="hlt">reactor</span> productivity. A CFD model of an industry-scale 96-rod CVD <span class="hlt">reactor</span> was established to study the internal temperature distribution and the flow field of the <span class="hlt">reactor</span>. Numerical simulations were carried out and compared with actual growth results from a real CVD <span class="hlt">reactor</span>. Factors affecting polysilicon depositions such as inlet gas injections, flow field, and temperature distribution in the CVD <span class="hlt">reactor</span> are studied.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/pages/biblio/1329365-assessing-pretreatment-reactor-scaling-through-empirical-analysis','SCIGOV-DOEP'); return false;" href="https://www.osti.gov/pages/biblio/1329365-assessing-pretreatment-reactor-scaling-through-empirical-analysis"><span>Assessing pretreatment <span class="hlt">reactor</span> scaling through empirical analysis</span></a></p> <p><a target="_blank" href="http://www.osti.gov/pages">DOE PAGES</a></p> <p>Lischeske, James J.; Crawford, Nathan C.; Kuhn, Erik; ...</p> <p>2016-10-10</p> <p>Pretreatment is a critical step in the biochemical conversion of lignocellulosic biomass to fuels and chemicals. Due to the complexity of the physicochemical transformations involved, predictively scaling up technology from bench- to pilot-scale is difficult. This study examines how pretreatment effectiveness under nominally similar reaction conditions is influenced by pretreatment <span class="hlt">reactor</span> design and scale using four different pretreatment reaction systems ranging from a 3 g batch <span class="hlt">reactor</span> to a 10 dry-ton/d continuous <span class="hlt">reactor</span>. The <span class="hlt">reactor</span> systems examined were an Automated Solvent Extractor (ASE), Steam Explosion <span class="hlt">Reactor</span> (SER), ZipperClave(R) <span class="hlt">reactor</span> (ZCR), and Large Continuous Horizontal-Screw <span class="hlt">Reactor</span> (LHR). To our knowledge, thismore » is the first such study performed on pretreatment <span class="hlt">reactors</span> across a range of reaction conditions (time and temperature) and at different <span class="hlt">reactor</span> scales. The comparative pretreatment performance results obtained for each <span class="hlt">reactor</span> system were used to develop response surface models for total xylose yield after pretreatment and total sugar yield after pretreatment followed by enzymatic hydrolysis. Near- and very-near-optimal regions were defined as the set of conditions that the model identified as producing yields within one and two standard deviations of the optimum yield. Optimal conditions identified in the smallest-scale system (the ASE) were within the near-optimal region of the largest scale <span class="hlt">reactor</span> system evaluated. A reaction severity factor modeling approach was shown to inadequately describe the optimal conditions in the ASE, incorrectly identifying a large set of sub-optimal conditions (as defined by the RSM) as optimal. The maximum total sugar yields for the ASE and LHR were 95%, while 89% was the optimum observed in the ZipperClave. The optimum condition identified using the automated and less costly to operate ASE system was within the very-near-optimal space for the total xylose yield of both the ZCR and the LHR, and</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1329365','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1329365"><span>Assessing pretreatment <span class="hlt">reactor</span> scaling through empirical analysis</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Lischeske, James J.; Crawford, Nathan C.; Kuhn, Erik</p> <p></p> <p>Pretreatment is a critical step in the biochemical conversion of lignocellulosic biomass to fuels and chemicals. Due to the complexity of the physicochemical transformations involved, predictively scaling up technology from bench- to pilot-scale is difficult. This study examines how pretreatment effectiveness under nominally similar reaction conditions is influenced by pretreatment <span class="hlt">reactor</span> design and scale using four different pretreatment reaction systems ranging from a 3 g batch <span class="hlt">reactor</span> to a 10 dry-ton/d continuous <span class="hlt">reactor</span>. The <span class="hlt">reactor</span> systems examined were an Automated Solvent Extractor (ASE), Steam Explosion <span class="hlt">Reactor</span> (SER), ZipperClave(R) <span class="hlt">reactor</span> (ZCR), and Large Continuous Horizontal-Screw <span class="hlt">Reactor</span> (LHR). To our knowledge, thismore » is the first such study performed on pretreatment <span class="hlt">reactors</span> across a range of reaction conditions (time and temperature) and at different <span class="hlt">reactor</span> scales. The comparative pretreatment performance results obtained for each <span class="hlt">reactor</span> system were used to develop response surface models for total xylose yield after pretreatment and total sugar yield after pretreatment followed by enzymatic hydrolysis. Near- and very-near-optimal regions were defined as the set of conditions that the model identified as producing yields within one and two standard deviations of the optimum yield. Optimal conditions identified in the smallest-scale system (the ASE) were within the near-optimal region of the largest scale <span class="hlt">reactor</span> system evaluated. A reaction severity factor modeling approach was shown to inadequately describe the optimal conditions in the ASE, incorrectly identifying a large set of sub-optimal conditions (as defined by the RSM) as optimal. The maximum total sugar yields for the ASE and LHR were 95%, while 89% was the optimum observed in the ZipperClave. The optimum condition identified using the automated and less costly to operate ASE system was within the very-near-optimal space for the total xylose yield of both the ZCR and the LHR, and</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017ITNS...64..844A','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017ITNS...64..844A"><span>Measurement and Analysis of Structural Integrity of <span class="hlt">Reactor</span> Core Support Structure in Pressurized Water <span class="hlt">Reactor</span> (PWR) Plant</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Ansari, Saleem A.; Haroon, Muhammad; Rashid, Atif; Kazmi, Zafar</p> <p>2017-02-01</p> <p>Extensive calculation and measurements of flow-induced vibrations (FIV) of <span class="hlt">reactor</span> internals were made in a PWR plant to assess the structural integrity of <span class="hlt">reactor</span> core support structure against coolant flow. The work was done to meet the requirements of the Fukushima Response Action Plan (FRAP) for enhancement of <span class="hlt">reactor</span> safety, and the regulatory guide RG-1.20. For the core surveillance measurements the <span class="hlt">Reactor</span> Internals Vibration Monitoring System (IVMS) has been developed based on detailed neutron noise analysis of the flux signals from the four ex-core neutron detectors. The natural frequencies, displacement and mode shapes of the <span class="hlt">reactor</span> core barrel (CB) motion were determined with the help of IVMS. The random pressure fluctuations in <span class="hlt">reactor</span> coolant flow due to turbulence force have been identified as the predominant cause of beam-mode deflection of CB. The dynamic FIV calculations were also made to supplement the core surveillance measurements. The calculational package employed the computational fluid dynamics, mode shape analysis, calculation of power spectral densities of flow & pressure fields and the structural response to random flow excitation forces. The dynamic loads and stiffness of the Hold-Down Spring that keeps the core structure in position against upward coolant thrust were also determined by noise measurements. Also, the boron concentration in primary coolant at any time of the core cycle has been determined with the IVMS.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1374499','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1374499"><span>Vibro-acoustic Imaging at the Breazeale <span class="hlt">Reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Smith, James Arthur; Jewell, James Keith; Lee, James Edwin</p> <p>2016-09-01</p> <p>The INL is developing Vibro-acoustic imaging technology to characterize microstructure in fuels and materials in spent fuel pools and within <span class="hlt">reactor</span> vessels. A vibro-acoustic development laboratory has been established at the INL. The progress in developing the vibro-acoustic technology at the INL is the focus of this report. A successful technology demonstration was performed in a working TRIGA research <span class="hlt">reactor</span>. Vibro-acoustic imaging was performed in the <span class="hlt">reactor</span> pool of the Breazeale <span class="hlt">reactor</span> in late September of 2015. A confocal transducer driven at a nominal 3 MHz was used to collect the 60 kHz differential beat frequency induced in a spentmore » TRIGA fuel rod and empty gamma tube located in the main <span class="hlt">reactor</span> water pool. Data was collected and analyzed with the INLDAS data acquisition software using a short time Fourier transform.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5053870','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/5053870"><span>Boiling water neutronic <span class="hlt">reactor</span> incorporating a process inherent safety design</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Forsberg, C.W.</p> <p>1985-02-19</p> <p>A boiling-water <span class="hlt">reactor</span> core is positioned within a prestressed concrete <span class="hlt">reactor</span> vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the <span class="hlt">reactor</span> core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (nonborated) water for cooling during normal operation and cool highly borated water for emergency cooling and <span class="hlt">reactor</span> shutdown are separated by an insulated wall during normal <span class="hlt">reactor</span> operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the <span class="hlt">reactor</span> vessel. Means are provided for balancing the pressure of the two water volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the <span class="hlt">reactor</span> core region, for detecting the onset of excessive power to coolant flow conditions in the <span class="hlt">reactor</span> core and for detecting low water levels of <span class="hlt">reactor</span> coolant. Cool borated water is permitted to flow into the <span class="hlt">reactor</span> core when low <span class="hlt">reactor</span> coolant levels or excessive power to coolant flow conditions are encountered.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866254','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866254"><span>Boiling water neutronic <span class="hlt">reactor</span> incorporating a process inherent safety design</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Forsberg, Charles W.</p> <p>1987-01-01</p> <p>A boiling-water <span class="hlt">reactor</span> core is positioned within a prestressed concrete <span class="hlt">reactor</span> vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the <span class="hlt">reactor</span> core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (non-borated) water for cooling during normal operation and cool highly borated water for emergency cooling and <span class="hlt">reactor</span> shutdown are separated by an insulated wall during normal <span class="hlt">reactor</span> operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the <span class="hlt">reactor</span> vessel. Means are provided for balancing the pressure of the two volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the <span class="hlt">reactor</span> core region, for detecting the onset of excessive power to coolant flow conditions in the <span class="hlt">reactor</span> core and for detecting low water levels of <span class="hlt">reactor</span> coolant. Cool borated water is permitted to flow into the <span class="hlt">reactor</span> core when low <span class="hlt">reactor</span> coolant levels or excessive power to coolant flow conditions are encountered.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/865757','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/865757"><span>Control system for a small fission <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Burelbach, James P.; Kann, William J.; Saiveau, James G.</p> <p>1986-01-01</p> <p>A system for controlling the reactivity of a small fission <span class="hlt">reactor</span> includes an elongated, flexible hollow tube in the general form of a helical coiled spring axially positioned around and outside of the <span class="hlt">reactor</span> vessel in an annular space between the <span class="hlt">reactor</span> vessel and a surrounding cylindrical-shaped neutron reflector. A neutron absorbing material is provided within the hollow tube with the rate of the reaction controlled by the extension and compression of the hollow tube, e.g., extension of the tube increases reactivity while its compression reduces reactivity, in varying the amount of neutron absorbing material disposed between the <span class="hlt">reactor</span> vessel and the neutron reflector. Conventional mechanical displacement means may be employed to control the coil density of the hollow tube as desired. In another embodiment, a plurality of flexible hollow tubes each containing a neutron absorber are positioned adjacent to one another in spaced relation around the periphery of the <span class="hlt">reactor</span> vessel and inside the outer neutron reflector with reactivity controlled by the extension and compression of all or some of the coiled hollow tubes. Yet another embodiment of the invention envisions the neutron reflector in the form of an expandable coil spring positioned in an annular space between the <span class="hlt">reactor</span> vessel and an outer neutron absorbing structure for controlling the neutron flux reflected back into the <span class="hlt">reactor</span> vessel.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2007JNuM..371..281M','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2007JNuM..371..281M"><span>Fuel development for gas-cooled fast <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Meyer, M. K.; Fielding, R.; Gan, J.</p> <p>2007-09-01</p> <p>The Generation IV Gas-cooled Fast <span class="hlt">Reactor</span> (GFR) concept is proposed to combine the advantages of high-temperature gas-cooled <span class="hlt">reactors</span> (such as efficient direct conversion with a gas turbine and the potential for application of high-temperature process heat), with the sustainability advantages that are possible with a fast-spectrum <span class="hlt">reactor</span>. The latter include the ability to fission all transuranics and the potential for breeding. The GFR is part of a consistent set of gas-cooled <span class="hlt">reactors</span> that includes a medium-term Pebble Bed Modular <span class="hlt">Reactor</span> (PBMR)-like concept, or concepts based on the Gas Turbine Modular Helium <span class="hlt">Reactor</span> (GT-MHR), and specialized concepts such as the Very High-Temperature <span class="hlt">Reactor</span> (VHTR), as well as actinide burning concepts [A Technology Roadmap for Generation IV Nuclear Energy Systems, US DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, December 2002]. To achieve the necessary high power density and the ability to retain fission gas at high temperature, the primary fuel concept proposed for testing in the United States is dispersion coated fuel particles in a ceramic matrix. Alternative fuel concepts considered in the US and internationally include coated particle beds, ceramic clad fuel pins, and novel ceramic 'honeycomb' structures. Both mixed carbide and mixed nitride-based solid solutions are considered as fuel phases.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/54632','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/54632"><span>Health physics aspects of advanced <span class="hlt">reactor</span> licensing reviews</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Hinson, C.S.</p> <p>1995-03-01</p> <p>The last Construction Permit to be issued by the U.S. Nuclear Regulatory Commission (NRC) for a U.S. light water <span class="hlt">reactor</span> (LWR) was granted in the late 1970s. In 1989 the NRC issued 10 CFR Part 52 which is intended to serve as a framework for the licensing of future <span class="hlt">reactor</span> designs. The NRC is currently reviewing four different future on {open_quotes}next-generation{close_quotes} <span class="hlt">reactor</span> designs. Two of these designs are classified as evolutionary designs (modified versions of current generation LWRs) and two are advanced designs (<span class="hlt">reactors</span> incorporating simplified designs and passive means for accident mitigation). These {open_quotes}next-generation{close_quotes} <span class="hlt">reactor</span> designs incorporate many innovativemore » design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these <span class="hlt">reactors</span> does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} <span class="hlt">reactor</span> designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these <span class="hlt">reactors</span> does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} <span class="hlt">reactor</span> designs currently being reviewed by the NRC.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/655502-effects-imperfect-mixing-low-density-polyethylene-reactor-dynamics','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/655502-effects-imperfect-mixing-low-density-polyethylene-reactor-dynamics"><span>Effects of imperfect mixing on low-density polyethylene <span class="hlt">reactor</span> dynamics</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Villa, C.M.; Dihora, J.O.; Ray, W.H.</p> <p>1998-07-01</p> <p>Earlier work considered the effect of feed conditions and controller configuration on the runaway behavior of LDPE autoclave <span class="hlt">reactors</span> assuming a perfectly mixed <span class="hlt">reactor</span>. This study provides additional insight on the dynamics of such <span class="hlt">reactors</span> by using an imperfectly mixed <span class="hlt">reactor</span> model and bifurcation analysis to show the changes in the stability region when there is imperfect macroscale mixing. The presence of imperfect mixing substantially increases the range of stable operation of the <span class="hlt">reactor</span> and makes the process much easier to control than for a perfectly mixed <span class="hlt">reactor</span>. The results of model analysis and simulations are used to identify somemore » of the conditions that lead to unstable <span class="hlt">reactor</span> behavior and to suggest ways to avoid <span class="hlt">reactor</span> runaway or <span class="hlt">reactor</span> extinction during grade transitions and other process operation disturbances.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/97110','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/97110"><span>Nuclear <span class="hlt">reactors</span> built, being built, or planned, 1994</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>NONE</p> <p>1995-07-01</p> <p>This document contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1994. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE; from the US Nuclear Regulatory Commission (NRC); from the US <span class="hlt">reactor</span> manufacturers who are the principal nuclear contractors for foreign <span class="hlt">reactor</span> locations; from US and foreign embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: a commercial <span class="hlt">reactor</span> locator map and tables of the characteristicmore » and statistical data that follow; a table of abbreviations; tables of data for <span class="hlt">reactors</span> operating, being built, or planned; and tables of data for <span class="hlt">reactors</span> that have been shut down permanently or dismantled. The <span class="hlt">reactors</span> are subdivided into the following parts: Civilian, Production, Military, Export, and Critical Assembly. Export <span class="hlt">reactor</span> refers to a <span class="hlt">reactor</span> for which the principal nuclear contractor is a US company -- working either independently or in cooperation with a foreign company (Part 4). Critical assembly refers to an assembly of fuel and moderator that requires an external source of neutrons to initiate and maintain fission. A critical assembly is used for experimental measurements (Part 5).« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/373892','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/373892"><span>Nuclear <span class="hlt">reactors</span> built, being built, or planned: 1995</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>NONE</p> <p>1996-08-01</p> <p>This report contains unclassified information about facilities built, being built, or planned in the US for domestic use or export as of December 31, 1995. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE; from the US Nuclear Regulatory Commission (NRC); from the US <span class="hlt">reactor</span> manufacturers who are the principal nuclear contractors for foreign <span class="hlt">reactor</span> locations; from US and foreign embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: (1) a commercial <span class="hlt">reactor</span> locator map and tables of the characteristicmore » and statistical data that follow; a table of abbreviations; (2) tables of data for <span class="hlt">reactors</span> operating, being built, or planned; and (3) tables of data for <span class="hlt">reactors</span> that have been shut down permanently or dismantled. The <span class="hlt">reactors</span> are subdivided into the following parts: Civilian, Production, Military, Export, and Critical Assembly. Export <span class="hlt">reactor</span> refers to a <span class="hlt">reactor</span> for which the principal nuclear contractor is a US company--working either independently or in cooperation with a foreign company (Part 4). Critical assembly refers to an assembly of fuel and moderator that requires an external source of neutrons to initiate and maintain fission. A critical assembly is used for experimental measurements (Part 5).« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/6146915','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/6146915"><span>Modifications to the NRAD <span class="hlt">Reactor</span>, 1977 to present</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Weeks, A.A.; Pruett, D.P.; Heidel, C.C.</p> <p>1986-01-01</p> <p>Argonne National Laboratory-West, operated by the University of Chicago, is located near Idaho Falls, ID, on the Idaho National Engineering laboratory Site. ANL-West performs work in support of the Liquid Metal Fast Breeder <span class="hlt">Reactor</span> Program (LMFBR) sponsored by the United States Department of Energy. The NRAD <span class="hlt">reactor</span> is located at the Argonne Site within the Hot Fuel Examination Facility/North, a large hot cell facility where both non-destructive and destructive examinations are performed on highly irradiated <span class="hlt">reactor</span> fuels and materials in support of the LMFBR program. The NRAD facility utilizes a 250-kW TRIGA <span class="hlt">reactor</span> and is completely dedicated to neutron radiographymore » and the development of radiography techniques. Criticality was first achieved at the NRAD <span class="hlt">reactor</span> in October of 1977. Since that time, a number of modifications have been implemented to improve operational efficiency and radiography production. This paper describes the modifications and changes that significantly improved operational efficiency and reliability of the <span class="hlt">reactor</span> and the essential auxiliary <span class="hlt">reactor</span> systems.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1175802','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1175802"><span>Integrated reformer and shift <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Bentley, Jeffrey M.; Clawson, Lawrence G.; Mitchell, William L.; Dorson, Matthew H.</p> <p>2006-06-27</p> <p>A hydrocarbon fuel reformer for producing diatomic hydrogen gas is disclosed. The reformer includes a first reaction vessel, a shift <span class="hlt">reactor</span> vessel annularly disposed about the first reaction vessel, including a first shift <span class="hlt">reactor</span> zone, and a first helical tube disposed within the first shift <span class="hlt">reactor</span> zone having an inlet end communicating with a water supply source. The water supply source is preferably adapted to supply liquid-phase water to the first helical tube at flow conditions sufficient to ensure discharge of liquid-phase and steam-phase water from an outlet end of the first helical tube. The reformer may further include a first catalyst bed disposed in the first shift <span class="hlt">reactor</span> zone, having a low-temperature shift catalyst in contact with the first helical tube. The catalyst bed includes a plurality of coil sections disposed in coaxial relation to other coil sections and to the central longitudinal axis of the reformer, each coil section extending between the first and second ends, and each coil section being in direct fluid communication with at least one other coil section.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://images.nasa.gov/#/details-GRC-1961-C-55813.html','SCIGOVIMAGE-NASA'); return false;" href="https://images.nasa.gov/#/details-GRC-1961-C-55813.html"><span>Plum Brook <span class="hlt">Reactor</span> Facility Control Room during Facility Startup</span></a></p> <p><a target="_blank" href="https://images.nasa.gov/">NASA Image and Video Library</a></p> <p></p> <p>1961-02-21</p> <p>Operators test the National Aeronautics and Space Administration’s (NASA) Plum Brook <span class="hlt">Reactor</span> Facility systems in the months leading up to its actual operation. The “<span class="hlt">Reactor</span> On” signs are illuminated but the <span class="hlt">reactor</span> core was not yet ready for chain reactions. Just a couple weeks after this photograph, Plum Brook Station held a media open house to unveil the 60-megawatt test <span class="hlt">reactor</span> near Sandusky, Ohio. More than 60 members of the print media and radio and television news services met at the site to talk with community leaders and representatives from NASA and Atomic Energy Commission. The Plum Brook <span class="hlt">reactor</span> went critical for the first time on the evening of June 14, 1961. It was not until April 1963 that the <span class="hlt">reactor</span> reached its full potential of 60 megawatts. The <span class="hlt">reactor</span> control room, located on the second floor of the facility, was run by licensed operators. The operators manually operated the shim rods which adjusted the chain reaction in the <span class="hlt">reactor</span> core. The regulating rods could partially or completely shut down the <span class="hlt">reactor</span>. The control room also housed remote area monitoring panels and other monitoring equipment that allowed operators to monitor radiation sensors located throughout the facility and to scram the <span class="hlt">reactor</span> instantly if necessary. The color of the indicator lights corresponded with the elevation of the detectors in the various buildings. The <span class="hlt">reactor</span> could also shut itself down automatically if the monitors detected any sudden irregularities.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19730001840','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19730001840"><span>Exploratory evaluation of ceramics for automobile thermal <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Stone, P. L.; Blankenship, C. P.</p> <p>1972-01-01</p> <p>An exploratory evaluation of ceramics for automobile thermal <span class="hlt">reactors</span> was conducted. Potential ceramic materials were evaluated in several <span class="hlt">reactor</span> designs using both engine dynamometer and vehicle road tests. Silicon carbide contained in a corrugated metal support structure exhibited the best performance lasting over 800 hours in engine dynamometer tests and over 15,000 miles (24,200 km) of vehicle road tests. <span class="hlt">Reactors</span> containing glass-ceramic components did not perform as well as silicon carbide. But the glass-ceramics still offer good potential for <span class="hlt">reactor</span> use. The results of this study are considered to be a reasonable demonstration of the potential use of ceramics in thermal <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4261888','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4261888"><span>NUCLEAR <span class="hlt">REACTOR</span> UNLOADING APPARATUS</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Leverett, M.C.; Howe, J.P.</p> <p>1959-01-20</p> <p>An unloading device is described for a heterogeneous <span class="hlt">reactor</span> of the type wherein the fuel elements are in the form of cylindrical slugs and are disposed in horizontal coolant tubes which traverse the <span class="hlt">reactor</span> core, coolant fluid being circulated through the tubes. The coolant tubes have at least two inwardly protruding ribs from their lower surfaces to support the slugs in spaced relationship to the inside walls of the tubes. The unloading device consists of a ribbon-like extractor member insertable into the coolant tubes in the space between the ribs and adapted to slide under the fuel slugs thereby raising them off of the ribs and forming a slideway for removing them from the <span class="hlt">reactor</span>. The fuel slugs are ejected by being forced out of the tubes by incoming new fuel slugs or by a push rod insentable through the inlet end of the fuel tubes.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/14735530','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/14735530"><span>Chemistry in microstructured <span class="hlt">reactors</span>.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Jähnisch, Klaus; Hessel, Volker; Löwe, Holger; Baerns, Manfred</p> <p>2004-01-16</p> <p>The application of microstructured <span class="hlt">reactors</span> in the chemical process industry has gained significant importance in recent years. Companies that offer not only microstructured <span class="hlt">reactors</span>, but also entire chemical process plants and services relating to them, are already in existence. In addition, many institutes and universities are active within this field, and process-engineering-oriented reviews and a specialized book are available. Microstructured systems can be applied with particular success in the investigation of highly exothermic and fast reactions. Often the presence of temperature-induced side reactions can be significantly reduced through isothermal operations. Although microstructured reaction techniques have been shown to optimize many synthetic procedures, they have not yet received the attention they deserve in organic chemistry. For this reason, this Review aims to address this by providing an overview of the chemistry in microstructured <span class="hlt">reactors</span>, grouped into liquid-phase, gas-phase, and gas-liquid reactions.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4072150-preliminary-hazards-summary-report-vallecitos-superheat-reactor','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/4072150-preliminary-hazards-summary-report-vallecitos-superheat-reactor"><span>PRELIMINARY HAZARDS SUMMARY REPORT FOR THE VALLECITOS SUPERHEAT <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Murray, J.L.</p> <p>1961-02-01</p> <p>BS>The Vallecitos Superheat <span class="hlt">Reactor</span> (VSR) is a light-watermoderated, thermal-spectrum <span class="hlt">reactor</span>, cooled by a combination of moderator boiling and forced convection cooling with saturated steam. The <span class="hlt">reactor</span> core consists of 32 fuel hurdles containing 5300 lb of UO/sub 2/ enriched in U/sub 235/ to 3.6%. The fuel elements are arranged in individual process tubes that direct the cooling steam flow and separate the steam from the water moderator. The <span class="hlt">reactor</span> vessel is designed for 1250 psig and operates at 960 to 1000 psig. With the <span class="hlt">reactor</span> operating at 12.5 Mw(t), the maximum fuel cladding temperature is 1250 deg F and themore » cooling steam is superheated to an average temperature of about 810 deg F at 905 psig. Nu clear operation of the <span class="hlt">reactor</span> is controlled by 12 control rods, actuated by drives mounted on the bottom of the <span class="hlt">reactor</span> vessel. The water moderator recirculates inside the <span class="hlt">reactor</span> vessel and through the core region by natural convection. Inherent safety features of the <span class="hlt">reactor</span> include the negative core reactivity effects upon heating the UO/sub 2/ fuel (Doppler effect), upon increasing the temperature or void content of the moderator in the operating condition, and upon unflooding the fuel process tubes in the hot condition. Snfety features designed into the <span class="hlt">reactor</span> and plant systems include a system of sensors and devices to detect petentially unsafe operating conditions and to initiate automatically the appropriate countermeasures, a set of fast and reliable control rods for scramming the <span class="hlt">reactor</span> if a potentially unsafe condition occurs, a manually-actuated liquid neutron poison system, and an emergency cooling system to provide continued steam flow through the <span class="hlt">reactor</span> core in the event the <span class="hlt">reactor</span> becomes isolated from either its normal source of steam supply or discharge. The release of radioactivity to unrestricted areas is maintained within permissible limits by monitoring the radioactivity of wastes and controlling their release. The <span class="hlt">reactor</span> and</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_16");'>16</a></li> <li><a href="#" onclick='return showDiv("page_17");'>17</a></li> <li class="active"><span>18</span></li> <li><a href="#" onclick='return showDiv("page_19");'>19</a></li> <li><a href="#" onclick='return showDiv("page_20");'>20</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_18 --> <div id="page_19" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_17");'>17</a></li> <li><a href="#" onclick='return showDiv("page_18");'>18</a></li> <li class="active"><span>19</span></li> <li><a href="#" onclick='return showDiv("page_20");'>20</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="361"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1015249','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1015249"><span>Nuclear <span class="hlt">reactor</span> downcomer flow deflector</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Gilmore, Charles B [Greensburg, PA; Altman, David A [Pittsburgh, PA; Singleton, Norman R [Murrysville, PA</p> <p>2011-02-15</p> <p>A nuclear <span class="hlt">reactor</span> having a coolant flow deflector secured to a <span class="hlt">reactor</span> core barrel in line with a coolant inlet nozzle. The flow deflector redirects incoming coolant down an annulus between the core barrel and the <span class="hlt">reactor</span> vessel. The deflector has a main body with a front side facing the fluid inlet nozzle and a rear side facing the core barrel. The rear side of the main body has at least one protrusion secured to the core barrel so that a gap exists between the rear side of the main body adjacent the protrusion and the core barrel. Preferably, the protrusion is a relief that circumscribes the rear side of the main body.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19750056105&hterms=nuclear+reactors&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D40%26Ntt%3Dnuclear%2Breactors','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19750056105&hterms=nuclear+reactors&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D40%26Ntt%3Dnuclear%2Breactors"><span>Gaseous fuel nuclear <span class="hlt">reactor</span> research</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Schwenk, F. C.; Thom, K.</p> <p>1975-01-01</p> <p>Gaseous-fuel nuclear <span class="hlt">reactors</span> are described; their distinguishing feature is the use of fissile fuels in a gaseous or plasma state, thereby breaking the barrier of temperature imposed by solid-fuel elements. This property creates a <span class="hlt">reactor</span> heat source that may be able to heat the propellant of a rocket engine to 10,000 or 20,000 K. At this temperature level, gas-core <span class="hlt">reactors</span> would provide the breakthrough in propulsion needed to open the entire solar system to manned and unmanned spacecraft. The possibility of fuel recycling makes possible efficiencies of up to 65% and nuclear safety at reduced cost, as well as high-thrust propulsion capabilities with specific impulse up to 5000 sec.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19920001885','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19920001885"><span>Fission fragment assisted <span class="hlt">reactor</span> concept for space propulsion: Foil <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Wright, Steven A.</p> <p>1991-01-01</p> <p>The concept is to fabricate a <span class="hlt">reactor</span> using thin films or foils of uranium, uranium oxide and then to coat them on substrates. These coatings would be made so thin as to allow the escaping fission fragments to directly heat a hydrogen propellant. The idea was studied of direct gas heating and direct gas pumping in a nuclear pumped laser program. Fission fragments were used to pump lasers. In this concept two substrates are placed opposite each other. The internal faces are coated with thin foil of uranium oxide. A few of the advantages of this technology are listed. In general, however, it is felt that if one look at all solid core nuclear thermal rockets or nuclear thermal propulsion methods, one is going to find that they all pretty much look the same. It is felt that this <span class="hlt">reactor</span> has higher potential reliability. It has low structural operating temperatures, very short burn times, with graceful failure modes, and it has reduced potential for energetic accidents. Going to a design like this would take the NTP community part way to some of the very advanced engine designs, such as the gas core <span class="hlt">reactor</span>, but with reduced risk because of the much lower temperatures.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2011-title40-vol11/pdf/CFR-2011-title40-vol11-sec63-1406.pdf','CFR2011'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2011-title40-vol11/pdf/CFR-2011-title40-vol11-sec63-1406.pdf"><span>40 CFR 63.1406 - <span class="hlt">Reactor</span> batch process vent provisions.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2011&page.go=Go">Code of Federal Regulations, 2011 CFR</a></p> <p></p> <p>2011-07-01</p> <p>... 40 Protection of Environment 11 2011-07-01 2011-07-01 false <span class="hlt">Reactor</span> batch process vent provisions... § 63.1406 <span class="hlt">Reactor</span> batch process vent provisions. (a) Emission standards. Owners or operators of <span class="hlt">reactor</span>... <span class="hlt">reactor</span> batch process vent located at a new affected source shall control organic HAP emissions by...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2010-title40-vol11/pdf/CFR-2010-title40-vol11-sec63-1406.pdf','CFR'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2010-title40-vol11/pdf/CFR-2010-title40-vol11-sec63-1406.pdf"><span>40 CFR 63.1406 - <span class="hlt">Reactor</span> batch process vent provisions.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2010&page.go=Go">Code of Federal Regulations, 2010 CFR</a></p> <p></p> <p>2010-07-01</p> <p>... 40 Protection of Environment 11 2010-07-01 2010-07-01 true <span class="hlt">Reactor</span> batch process vent provisions... § 63.1406 <span class="hlt">Reactor</span> batch process vent provisions. (a) Emission standards. Owners or operators of <span class="hlt">reactor</span>... <span class="hlt">reactor</span> batch process vent located at a new affected source shall control organic HAP emissions by...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19780002918','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19780002918"><span>Analysis of the Gas Core Actinide Transmutation <span class="hlt">Reactor</span> (GCATR)</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Clement, J. D.; Rust, J. H.</p> <p>1977-01-01</p> <p>Design power plant studies were carried out for two applications of the plasma core <span class="hlt">reactor</span>: (1) As a breeder <span class="hlt">reactor</span>, (2) As a <span class="hlt">reactor</span> able to transmute actinides effectively. In addition to the above applications the <span class="hlt">reactor</span> produced electrical power with a high efficiency. A <span class="hlt">reactor</span> subsystem was designed for each of the two applications. For the breeder <span class="hlt">reactor</span>, neutronics calculations were carried out for a U-233 plasma core with a molten salt breeding blanket. A <span class="hlt">reactor</span> was designed with a low critical mass (less than a few hundred kilograms U-233) and a breeding ratio of 1.01. The plasma core actinide transmutation <span class="hlt">reactor</span> was designed to transmute the nuclear waste from conventional LWR's. The spent fuel is reprocessed during which 100% of Np, Am, Cm, and higher actinides are separated from the other components. These actinides are then manufactured as oxides into zirconium clad fuel rods and charged as fuel assemblies in the reflector region of the plasma core actinide transmutation <span class="hlt">reactor</span>. In the equilibrium cycle, about 7% of the actinides are directly fissioned away, while about 31% are removed by reprocessing.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/pages/biblio/1253240-reactor-production-thorium','SCIGOV-DOEP'); return false;" href="https://www.osti.gov/pages/biblio/1253240-reactor-production-thorium"><span><span class="hlt">Reactor</span> production of Thorium-229</span></a></p> <p><a target="_blank" href="http://www.osti.gov/pages">DOE PAGES</a></p> <p>Boll, Rose Ann; Murphy, Karen E.; Denton, David L.; ...</p> <p>2016-05-03</p> <p>Limited availability of 229Th for clinical applications of 213Bi necessitates investigation of alternative production routes. In <span class="hlt">reactor</span> production, 229Th is produced from neutron transmutation of 226Ra, 228Ra, 227Ac and 228Th. Here, we evaluate irradiations of 226Ra, 228Ra, and 227Ac targets at the ORNL High Flux Isotope <span class="hlt">Reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4321415','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4321415"><span>NEUTRONIC <span class="hlt">REACTOR</span> SYSTEM</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Daniels, F.</p> <p>1957-10-15</p> <p>Gas-cooled solid-moderator type <span class="hlt">reactors</span> wherein the fissionable fuel and moderator materials are each in the form of solid pebbles, or discrete particles, and are substantially homogeneously mixed in the proper proportion and placed within the core of the <span class="hlt">reactor</span> are described. The shape of these discrete particles must be such that voids are present between them when mixed together. Helium enters the bottom of the core and passes through the voids between the fuel and moderator particles to absorb the heat generated by the chain reaction. The hot helium gas is drawn off the top of the core and may be passed through a heat exchanger to produce steam.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://cfpub.epa.gov/si/si_public_record_report.cfm?dirEntryId=248928&Lab=NCER&keyword=Experimental+AND+design&actType=&TIMSType=+&TIMSSubTypeID=&DEID=&epaNumber=&ntisID=&archiveStatus=Both&ombCat=Any&dateBeginCreated=&dateEndCreated=&dateBeginPublishedPresented=&dateEndPublishedPresented=&dateBeginUpdated=&dateEndUpdated=&dateBeginCompleted=&dateEndCompleted=&personID=&role=Any&journalID=&publisherID=&sortBy=revisionDate&count=50','EPA-EIMS'); return false;" href="https://cfpub.epa.gov/si/si_public_record_report.cfm?dirEntryId=248928&Lab=NCER&keyword=Experimental+AND+design&actType=&TIMSType=+&TIMSSubTypeID=&DEID=&epaNumber=&ntisID=&archiveStatus=Both&ombCat=Any&dateBeginCreated=&dateEndCreated=&dateBeginPublishedPresented=&dateEndPublishedPresented=&dateBeginUpdated=&dateEndUpdated=&dateBeginCompleted=&dateEndCompleted=&personID=&role=Any&journalID=&publisherID=&sortBy=revisionDate&count=50"><span>RACEWAY <span class="hlt">REACTOR</span> FOR MICROALGAL BIODIESEL PRODUCTION</span></a></p> <p><a target="_blank" href="http://oaspub.epa.gov/eims/query.page">EPA Science Inventory</a></p> <p></p> <p></p> <p><p>The proposed mathematical model incorporating mass transfer, hydraulics, carbonate/aquatic chemistry, biokinetics, biology and <span class="hlt">reactor</span> design will be calibrated and validated using the data to be generated from the experiments. The practical feasibility of the proposed <span class="hlt">reactor</span>...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/865239','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/865239"><span>Reactivity control assembly for nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Bollinger, Lawrence R.</p> <p>1984-01-01</p> <p>Reactivity control assembly for nuclear <span class="hlt">reactor</span> comprises supports stacked above <span class="hlt">reactor</span> core for holding control rods. Couplers associated with the supports and a vertically movable drive shaft have lugs at their lower ends for engagement with the supports.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/22277238','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/22277238"><span>Automatic <span class="hlt">reactor</span> model synthesis with genetic programming.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Dürrenmatt, David J; Gujer, Willi</p> <p>2012-01-01</p> <p>Successful modeling of wastewater treatment plant (WWTP) processes requires an accurate description of the plant hydraulics. Common methods such as tracer experiments are difficult and costly and thus have limited applicability in practice; engineers are often forced to rely on their experience only. An implementation of grammar-based genetic programming with an encoding to represent hydraulic <span class="hlt">reactor</span> models as program trees should fill this gap: The encoding enables the algorithm to construct arbitrary <span class="hlt">reactor</span> models compatible with common software used for WWTP modeling by linking building blocks, such as continuous stirred-tank <span class="hlt">reactors</span>. Discharge measurements and influent and effluent concentrations are the only required inputs. As shown in a synthetic example, the technique can be used to identify a set of <span class="hlt">reactor</span> models that perform equally well. Instead of being guided by experience, the most suitable model can now be chosen by the engineer from the set. In a second example, temperature measurements at the influent and effluent of a primary clarifier are used to generate a <span class="hlt">reactor</span> model. A virtual tracer experiment performed on the <span class="hlt">reactor</span> model has good agreement with a tracer experiment performed on-site.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/567627','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/567627"><span>Supply of enriched uranium for research <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Mueller, H.</p> <p>1997-08-01</p> <p>Since the RERTR-meeting In Newport/USA in 1990 the author delivered a series of papers in connection with the fuel cycle for research <span class="hlt">reactors</span> dealing with its front-end. In these papers the author underlined the need for unified specifications for enriched uranium metal suitable for the production of fuel elements and made proposals with regard to the re-use of in Europe reprocessed highly enriched uranium. With regard to the fuel cycle of research <span class="hlt">reactors</span> the research <span class="hlt">reactor</span> community was since 1989 more concentrating on the problems of its back-end since the USA stopped the acceptance of spent research <span class="hlt">reactor</span> fuel onmore » December 31, 1988. Now, since it is apparent that these back-end problem have been solved by AEA`s ability to reprocess and the preparedness of the USA to again accept physically spent research <span class="hlt">reactor</span> fuel the author is focusing with this paper again on the front-end of the fuel cycle on the question whether there is at all a safe supply of low and high enriched uranium for research <span class="hlt">reactors</span> in the future.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/10164111','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/10164111"><span>Top shield temperatures, C and K <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Agar, J.D.</p> <p>1964-12-28</p> <p>A modification program is now in progress at the C and K <span class="hlt">Reactors</span> consisting of an extensive renovation of the graphite channels in the vertical safety rod ststems. The present VSR channels are being enlarged by a graphite coring operation and channel sleeves will be installed in the larger channels. One problem associated with the coring operation is the danger of damaging top thermal shield cooling tubes located close to the VSR channels to such an extent that these tubes will have to be removed from service. If such a condition should exist at one or a number of locationsmore » in the top shield of the <span class="hlt">reactors</span> after <span class="hlt">reactor</span> startup, the question remains -- what would the resulting temperatures be of the various components of the top shields? This study was initiated to determine temperature distributions in the top shield complex at the C and K <span class="hlt">Reactors</span> for various top thermal shield coolant system conditions. Since the top thermal shield cooling system at C <span class="hlt">Reactor</span> is different than those at the K <span class="hlt">Reactors</span>, the study was conducted separately for the two different systems.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://pubs.usgs.gov/fs/2012/3093/pdf/fs2012-3093.pdf','USGSPUBS'); return false;" href="https://pubs.usgs.gov/fs/2012/3093/pdf/fs2012-3093.pdf"><span>The U.S. Geological Survey's TRIGA® <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://pubs.er.usgs.gov/pubs/index.jsp?view=adv">USGS Publications Warehouse</a></p> <p>DeBey, Timothy M.; Roy, Brycen R.; Brady, Sally R.</p> <p>2012-01-01</p> <p>The U.S. Geological Survey (USGS) operates a low-enriched uranium-fueled, pool-type <span class="hlt">reactor</span> located at the Federal Center in Denver, Colorado. The mission of the Geological Survey TRIGA® <span class="hlt">Reactor</span> (GSTR) is to support USGS science by providing information on geologic, plant, and animal specimens to advance methods and techniques unique to nuclear <span class="hlt">reactors</span>. The <span class="hlt">reactor</span> facility is supported by programs across the USGS and is organizationally under the Associate Director for Energy and Minerals, and Environmental Health. The GSTR is the only facility in the United States capable of performing automated delayed neutron analyses for detecting fissile and fissionable isotopes. Samples from around the world are submitted to the USGS for analysis using the <span class="hlt">reactor</span> facility. Qualitative and quantitative elemental analyses, spatial elemental analyses, and geochronology are performed. Few research <span class="hlt">reactor</span> facilities in the United States are equipped to handle the large number of samples processed at the GSTR. Historically, more than 450,000 sample irradiations have been performed at the USGS facility. Providing impartial scientific information to resource managers, planners, and other interested parties throughout the world is an integral part of the research effort of the USGS.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19720053969&hterms=Mayo&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAuthor-Name%26N%3D0%26No%3D20%26Ntt%3DMayo%252C%2BE','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19720053969&hterms=Mayo&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAuthor-Name%26N%3D0%26No%3D20%26Ntt%3DMayo%252C%2BE"><span>A small, 1400 K, <span class="hlt">reactor</span> for Brayton space power systems.</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Lantz, E.; Mayo, W.</p> <p>1972-01-01</p> <p>An investigation was conducted to determine minimum dimensions and minimum weight obtainable in a design for a <span class="hlt">reactor</span> using uranium-233 nitride or plutonium-239 nitride as fuel. Such a <span class="hlt">reactor</span> had been considered by Krasner et al. (1971). Present space power status is discussed, together with questions of <span class="hlt">reactor</span> design and power distribution in the <span class="hlt">reactor</span>. The characteristics of various <span class="hlt">reactor</span> types are compared, giving attention also to a zirconium hydride <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/863304','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/863304"><span>Nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wade, Elman E.</p> <p>1979-01-01</p> <p>A nuclear <span class="hlt">reactor</span> including two rotatable plugs and a positive top core holddown structure. The top core holddown structure is divided into two parts: a small core cover, and a large core cover. The small core cover, and the upper internals associated therewith, are attached to the small rotating plug, and the large core cover, with its associated upper internals, is attached to the large rotating plug. By so splitting the core holddown structures, under-the-plug refueling is accomplished without the necessity of enlarging the <span class="hlt">reactor</span> pressure vessel to provide a storage space for the core holddown structure during refueling. Additionally, the small and large rotating plugs, and their associated core covers, are arranged such that the separation of the two core covers to permit rotation is accomplished without the installation of complex lifting mechanisms.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1163969','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1163969"><span>Scanning tunneling microscope assembly, <span class="hlt">reactor</span>, and system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Tao, Feng; Salmeron, Miquel; Somorjai, Gabor A</p> <p>2014-11-18</p> <p>An embodiment of a scanning tunneling microscope (STM) <span class="hlt">reactor</span> includes a pressure vessel, an STM assembly, and three spring coupling objects. The pressure vessel includes a sealable port, an interior, and an exterior. An embodiment of an STM system includes a vacuum chamber, an STM <span class="hlt">reactor</span>, and three springs. The three springs couple the STM <span class="hlt">reactor</span> to the vacuum chamber and are operable to suspend the scanning tunneling microscope <span class="hlt">reactor</span> within the interior of the vacuum chamber during operation of the STM <span class="hlt">reactor</span>. An embodiment of an STM assembly includes a coarse displacement arrangement, a piezoelectric fine displacement scanning tube coupled to the coarse displacement arrangement, and a receiver. The piezoelectric fine displacement scanning tube is coupled to the coarse displacement arrangement. The receiver is coupled to the piezoelectric scanning tube and is operable to receive a tip holder, and the tip holder is operable to receive a tip.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/FR-2010-04-22/pdf/2010-9299.pdf','FEDREG'); return false;" href="https://www.gpo.gov/fdsys/pkg/FR-2010-04-22/pdf/2010-9299.pdf"><span>75 FR 21046 - Advisory Committee on <span class="hlt">Reactor</span> Safeguards</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collection.action?collectionCode=FR">Federal Register 2010, 2011, 2012, 2013, 2014</a></p> <p></p> <p>2010-04-22</p> <p>... NUCLEAR REGULATORY COMMISSION Advisory Committee on <span class="hlt">Reactor</span> Safeguards In accordance with the... on <span class="hlt">Reactor</span> Safeguards (ACRS) will hold a meeting on May 6-8, 2010, 11545 Rockville Pike, Rockville....: Boiling Water <span class="hlt">Reactor</span> (BWR) Owners Group (BWROG) Topical Report NEDC-33347P, ``Containment Overpressure...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6592715','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/6592715"><span>Heat dissipating nuclear <span class="hlt">reactor</span> with metal liner</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Gluekler, E.L.; Hunsbedt, A.; Lazarus, J.D.</p> <p>1985-11-21</p> <p>A nuclear <span class="hlt">reactor</span> containment including a <span class="hlt">reactor</span> vessel disposed within a cavity with capability for complete inherent decay heat removal in the earth and surrounded by a cast steel containment member which surrounds the vessel is described in this disclosure. The member has a thick basemat in contact with metal pilings. The basemat rests on a bed of porous particulate material, into which water is fed to produce steam which is vented to the atmosphere. There is a gap between the <span class="hlt">reactor</span> vessel and the steel containment member. The containment member holds any sodium or core debris escaping from the <span class="hlt">reactor</span> vessel if the core melts and breaches the vessel.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4712978','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4712978"><span>BOILING SLURRY <span class="hlt">REACTOR</span> AND METHOD FO CONTROL</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Petrick, M.; Marchaterre, J.F.</p> <p>1963-05-01</p> <p>The control of a boiling slurry nuclear <span class="hlt">reactor</span> is described. The <span class="hlt">reactor</span> consists of a vertical tube having an enlarged portion, a steam drum at the top of the vertical tube, and at least one downcomer connecting the steam drum and the bottom of the vertical tube, the <span class="hlt">reactor</span> being filled with a slurry of fissionabie material in water of such concentration that the enlarged portion of the vertical tube contains a critical mass. The slurry boils in the vertical tube and circulates upwardly therein and downwardly in the downcomer. To control the <span class="hlt">reactor</span> by controlling the circulation of the slurry, a gas is introduced into the downcomer. (AEC)</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_17");'>17</a></li> <li><a href="#" onclick='return showDiv("page_18");'>18</a></li> <li class="active"><span>19</span></li> <li><a href="#" onclick='return showDiv("page_20");'>20</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_19 --> <div id="page_20" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_18");'>18</a></li> <li><a href="#" onclick='return showDiv("page_19");'>19</a></li> <li class="active"><span>20</span></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="381"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866184','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866184"><span>Heat dissipating nuclear <span class="hlt">reactor</span> with metal liner</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Gluekler, Emil L.; Hunsbedt, Anstein; Lazarus, Jonathan D.</p> <p>1987-01-01</p> <p>Disclosed is a nuclear <span class="hlt">reactor</span> containment including a <span class="hlt">reactor</span> vessel disposed within a cavity with capability for complete inherent decay heat removal in the earth and surrounded by a cast steel containment member which surrounds the vessel. The member has a thick basemat in contact with metal pilings. The basemat rests on a bed of porous particulate material, into which water is fed to produce steam which is vented to the atmosphere. There is a gap between the <span class="hlt">reactor</span> vessel and the steel containment member. The containment member holds any sodium or core debris escaping from the <span class="hlt">reactor</span> vessel if the core melts and breaches the vessel.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866212','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866212"><span>Solid tags for identifying failed <span class="hlt">reactor</span> components</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Bunch, Wilbur L.; Schenter, Robert E.</p> <p>1987-01-01</p> <p>A solid tag material which generates stable detectable, identifiable, and measurable isotopic gases on exposure to a neutron flux to be placed in a nuclear <span class="hlt">reactor</span> component, particularly a fuel element, in order to identify the <span class="hlt">reactor</span> component in event of its failure. Several tag materials consisting of salts which generate a multiplicity of gaseous isotopes in predetermined ratios are used to identify different <span class="hlt">reactor</span> components.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4108333','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4108333"><span>NEUTRONIC <span class="hlt">REACTOR</span> CONTROL ELEMENT</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Newson, H.W.</p> <p>1960-09-13</p> <p>A novel composite neutronic <span class="hlt">reactor</span> control element is offered. The element comprises a multiplicity of sections arranged in end-to-end relationship, each of the sections having a markedly different neutron-reactive characteristic. For example, a three-section control element could contain absorber, moderator, and fuel sections. By moving such an element longitudinally through a <span class="hlt">reactor</span> core, reactivity is decreased by the absorber, increased slightly by the moderator, or increased substantially by the fuel. Thus, control over a wide reactivity range is provided.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1364524','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1364524"><span>Advanced Demonstration and Test <span class="hlt">Reactor</span> Options Study</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Petti, David Andrew; Hill, R.; Gehin, J.</p> <p></p> <p>Global efforts to address climate change will require large-scale decarbonization of energy production in the United States and elsewhere. Nuclear power already provides 20% of electricity production in the United States (U.S.) and is increasing in countries undergoing rapid growth around the world. Because reliable, grid-stabilizing, low emission electricity generation, energy security, and energy resource diversity will be increasingly valued, nuclear power’s share of electricity production has a potential to grow. In addition, there are non electricity applications (e.g., process heat, desalination, hydrogen production) that could be better served by advanced nuclear systems. Thus, the timely development, demonstration, and commercializationmore » of advanced nuclear <span class="hlt">reactors</span> could diversify the nuclear technologies available and offer attractive technology options to expand the impact of nuclear energy for electricity generation and non-electricity missions. The purpose of this planning study is to provide transparent and defensible technology options for a test and/or demonstration <span class="hlt">reactor(s</span>) to be built to support public policy, innovation and long term commercialization within the context of the Department of Energy’s (DOE’s) broader commitment to pursuing an “all of the above” clean energy strategy and associated time lines. This planning study includes identification of the key features and timing needed for advanced test or demonstration <span class="hlt">reactors</span> to support research, development, and technology demonstration leading to the commercialization of power plants built upon these advanced <span class="hlt">reactor</span> platforms. This planning study is consistent with the Congressional language contained within the fiscal year 2015 appropriation that directed the DOE to conduct a planning study to evaluate “advanced <span class="hlt">reactor</span> technology options, capabilities, and requirements within the context of national needs and public policy to support innovation in nuclear energy</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1366488','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1366488"><span>Target-fueled nuclear <span class="hlt">reactor</span> for medical isotope production</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Coats, Richard L.; Parma, Edward J.</p> <p></p> <p>A small, low-enriched, passively safe, low-power nuclear <span class="hlt">reactor</span> comprises a core of target and fuel pins that can be processed to produce the medical isotope .sup.99Mo and other fission product isotopes. The fuel for the <span class="hlt">reactor</span> and the targets for the .sup.99Mo production are the same. The fuel can be low enriched uranium oxide, enriched to less than 20% .sup.235U. The <span class="hlt">reactor</span> power level can be 1 to 2 MW. The <span class="hlt">reactor</span> is passively safe and maintains negative reactivity coefficients. The total radionuclide inventory in the <span class="hlt">reactor</span> core is minimized since the fuel/target pins are removed and processed after 7more » to 21 days.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1329531','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1329531"><span>Nuclear Energy Enabling Technologies (NEET) <span class="hlt">Reactor</span> Materials: News for the <span class="hlt">Reactor</span> Materials Crosscut, May 2016</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Maloy, Stuart Andrew</p> <p></p> <p>In this newsletter for Nuclear Energy Enabling Technologies (NEET) <span class="hlt">Reactor</span> Materials, pages 1-3 cover highlights from the DOE-NE (Nuclear Energy) programs, pages 4-6 cover determining the stress-strain response of ion-irradiated metallic materials via spherical nanoindentation, and pages 7-8 cover theoretical approaches to understanding long-term materials behavior in light water <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/FR-2012-10-02/pdf/2012-24221.pdf','FEDREG'); return false;" href="https://www.gpo.gov/fdsys/pkg/FR-2012-10-02/pdf/2012-24221.pdf"><span>77 FR 60039 - Non-Power <span class="hlt">Reactor</span> License Renewal</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collection.action?collectionCode=FR">Federal Register 2010, 2011, 2012, 2013, 2014</a></p> <p></p> <p>2012-10-02</p> <p>... NUCLEAR REGULATORY COMMISSION 10 CFR Part 50 [NRC-2011-0087] RIN 3150-AI96 Non-Power <span class="hlt">Reactor</span>... the final regulatory basis for rulemaking to streamline non-power <span class="hlt">reactor</span> license renewal. This final... <span class="hlt">Reactor</span> (RTR) License Renewal Process. This contemplated rulemaking also recommends conforming changes to...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/FR-2010-02-23/pdf/2010-3489.pdf','FEDREG'); return false;" href="https://www.gpo.gov/fdsys/pkg/FR-2010-02-23/pdf/2010-3489.pdf"><span>75 FR 8154 - Advisory Committee on <span class="hlt">Reactor</span> Safeguards</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collection.action?collectionCode=FR">Federal Register 2010, 2011, 2012, 2013, 2014</a></p> <p></p> <p>2010-02-23</p> <p>... NUCLEAR REGULATORY COMMISSION Advisory Committee on <span class="hlt">Reactor</span> Safeguards In accordance with the... on <span class="hlt">Reactor</span> Safeguards (ACRS) will hold a meeting on March 4-6, 2010, 11545 Rockville Pike, Rockville....-12 p.m.: New Advanced <span class="hlt">Reactor</span> Designs (Open)--The Committee will hear presentations by and hold...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/FR-2012-06-29/pdf/2012-16115.pdf','FEDREG'); return false;" href="https://www.gpo.gov/fdsys/pkg/FR-2012-06-29/pdf/2012-16115.pdf"><span>77 FR 38742 - Non-Power <span class="hlt">Reactor</span> License Renewal</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collection.action?collectionCode=FR">Federal Register 2010, 2011, 2012, 2013, 2014</a></p> <p></p> <p>2012-06-29</p> <p>...-0087] RIN 3150-AI96 Non-Power <span class="hlt">Reactor</span> License Renewal AGENCY: Nuclear Regulatory Commission. ACTION... <span class="hlt">reactors</span>. This contemplated rulemaking would also make conforming changes to address technical issues in existing non-power <span class="hlt">reactor</span> regulations. The NRC is seeking input from the public, licensees, certificate...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2018MS%26E..334a2070Y','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2018MS%26E..334a2070Y"><span>Evaluation of power density on the bioethanol production using mesoscale oscillatory baffled <span class="hlt">reactor</span> and stirred tank <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Yussof, H. W.; Bahri, S. S.; Mazlan, N. A.</p> <p>2018-03-01</p> <p>A recent development in oscillatory baffled <span class="hlt">reactor</span> technology is down-scaling the <span class="hlt">reactor</span>, so that it can be used for production of small-scale bioproduct. In the present study, a mesoscale oscillatory baffled <span class="hlt">reactor</span> (MOBR) with central baffle system was developed. The <span class="hlt">reactor</span> performance of the MOBR was compared with conventional stirred tank <span class="hlt">reactor</span> (STR) to evaluate the performance of bioethanol fermentation using Saccharomyces cerevisiae. Evaluation was made at similar power density of 24.21, 57.38, 112.35 and 193.67 Wm-3 by varying frequency (f), amplitude (xo) and agitation speed (rpm). It was found that the MOBR improved the mixing intensity resulted in lower glucose concentration (0.988 gL-1) and higher bioethanol concentration (38.98 gL-1) after 12 hours fermentation at power density of 193.67 Wm-3. Based on the results, the bioethanol yield obtained using MOBR was 39% higher than the maximum achieved in STR. Bioethanol production using MOBR proved to be feasible as it is not only able to compete with conventional STR but also offers advantages of straight-forward scale-up, whereas it is complicated and difficult in STR. Overall, MOBR offers great prospective over the conventional STR.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4169532','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4169532"><span>NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Fermi, E.</p> <p>1960-04-01</p> <p>A nuclear <span class="hlt">reactor</span> is described consisting of blocks of graphite arranged in layers, natural uranium bodies disposed in holes in alternate layers of graphite blocks, and coolant tubes disposed in the layers of graphite blocks which do not contain uranium.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4153568','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4153568"><span>NUCLEAR <span class="hlt">REACTOR</span> CORE DESIGN</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Mahlmeister, J.E.; Peck, W.S.; Haberer, W.V.; Williams, A.C.</p> <p>1960-03-22</p> <p>An improved core design for a sodium-cooled, graphitemoderated nuclear <span class="hlt">reactor</span> is described. The improved <span class="hlt">reactor</span> core comprises a number of blocks of moderator material, each block being in the shape of a regular prism. A number of channels, extending the length of each block, are disposed around the periphery. When several blocks are placed in contact to form the <span class="hlt">reactor</span> core, the channels in adjacent blocks correspond with each other to form closed conduits extending the length of the core. Fuel element clusters are disposed in these closed conduits, and liquid coolant is forced through the annulus between the fuel cluster and the inner surface of the conduit. In a preferred embodiment of the invention, the moderator blocks are in the form of hexagonal prisms with longitudinal channels cut into the corners of the hexagon. The main advantage of an "edge-loaded" moderator block is that fewer thermal neutrons are absorbed by the moderator cladding, as compared with a conventional centrally loaded moderator block.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/865840','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/865840"><span>Nuclear <span class="hlt">reactor</span> safety device</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hutter, Ernest</p> <p>1986-01-01</p> <p>A safety device is disclosed for use in a nuclear <span class="hlt">reactor</span> for axially repositioning a control rod with respect to the <span class="hlt">reactor</span> core in the event of an upward thermal excursion. Such safety device comprises a laminated helical ribbon configured as a tube-like helical coil having contiguous helical turns with slidably abutting edges. The helical coil is disclosed as a portion of a drive member connected axially to the control rod. The laminated ribbon is formed of outer and inner laminae. The material of the outer lamina has a greater thermal coefficient of expansion than the material of the inner lamina. In the event of an upward thermal excursion, the laminated helical coil curls inwardly to a smaller diameter. Such inward curling causes the total length of the helical coil to increase by a substantial increment, so that the control rod is axially repositioned by a corresponding amount to reduce the power output of the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1346072','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1346072"><span>Thermal swing <span class="hlt">reactor</span> including a multi-flight auger</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ermanoski, Ivan</p> <p>2017-03-07</p> <p>A thermal swing <span class="hlt">reactor</span> including a multi-flight auger and methods for solar thermochemical reactions are disclosed. The <span class="hlt">reactor</span> includes a multi-flight auger having different helix portions having different pitch. Embodiments of <span class="hlt">reactors</span> include at least two distinct <span class="hlt">reactor</span> portions between which there is at least a pressure differential. In embodiments, reactive particles are exchanged between portions during a reaction cycle to thermally reduce the particles at first conditions and oxidize the particles at second conditions to produce chemical work from heat.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4823243','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4823243"><span>SPRING DRIVEN ACTUATING MECHANISM FOR NUCLEAR <span class="hlt">REACTOR</span> CONTROL</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Bevilacqua, F.; Uecker, D.F.; Groh, E.F.</p> <p>1962-01-23</p> <p>l962. rod in a nuclear <span class="hlt">reactor</span> to shut it down. The control rod or an extension thereof is wound on a drum as it is withdrawn from the <span class="hlt">reactor</span>. When an emergency occurs requiring the <span class="hlt">reactor</span> to be shut down, the drum is released so as to be free to rotate, and the tendency of the control rod or its extension coiled on the drum to straighten itself is used for quickly returning the control rod to the <span class="hlt">reactor</span>. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://eric.ed.gov/?q=Digestive&pg=5&id=EJ560111','ERIC'); return false;" href="https://eric.ed.gov/?q=Digestive&pg=5&id=EJ560111"><span>Animal Guts as Ideal <span class="hlt">Reactors</span>: An Open-Ended Project for a Course in Kinetics and <span class="hlt">Reactor</span> Design.</span></a></p> <p><a target="_blank" href="http://www.eric.ed.gov/ERICWebPortal/search/extended.jsp?_pageLabel=advanced">ERIC Educational Resources Information Center</a></p> <p>Carlson, Eric D.; Gast, Alice P.</p> <p>1998-01-01</p> <p>Presents an open-ended project tailored for a senior kinetics and <span class="hlt">reactor</span> design course in which basic <span class="hlt">reactor</span> design equations are used to model the digestive systems of several animals. Describes the assignment as well as the results. (DDR)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19930004812','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19930004812"><span>Plasma <span class="hlt">reactor</span> waste management systems</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Ness, Robert O., Jr.; Rindt, John R.; Ness, Sumitra R.</p> <p>1992-01-01</p> <p>The University of North Dakota is developing a plasma <span class="hlt">reactor</span> system for use in closed-loop processing that includes biological, materials, manufacturing, and waste processing. Direct-current, high-frequency, or microwave discharges will be used to produce plasmas for the treatment of materials. The plasma <span class="hlt">reactors</span> offer several advantages over other systems, including low operating temperatures, low operating pressures, mechanical simplicity, and relatively safe operation. Human fecal material, sunflowers, oats, soybeans, and plastic were oxidized in a batch plasma <span class="hlt">reactor</span>. Over 98 percent of the organic material was converted to gaseous products. The solids were then analyzed and a large amount of water and acid-soluble materials were detected. These materials could possibly be used as nutrients for biological systems.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/864128','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/864128"><span><span class="hlt">Reactor</span> control rod timing system</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Wu, Peter T. K.</p> <p>1982-01-01</p> <p>A fluid driven jet-edge whistle timing system for control rods of a nuclear <span class="hlt">reactor</span> for producing real-time detection of the timing of each control rod in its scram operation. An important parameter in <span class="hlt">reactor</span> safety, particularly for liquid metal fast breeder <span class="hlt">reactors</span> (LMFBR), is the time deviation between the time the control rod is released and the time the rod actually reaches the down position. The whistle has a nearly pure tone signal with center frequency (above 100 kHz) far above the frequency band in which the energy of the background noise is concentrated. Each control rod can be fitted with a whistle with a different frequency so that there is no ambiguity in differentiating the signal from each control rod.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/5991942','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/5991942"><span><span class="hlt">Reactor</span> application of an improved bundle divertor</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Yang, T.F.; Ruck, G.W.; Lee, A.Y.</p> <p>1978-11-01</p> <p>A Bundle Divertor was chosen as the impurity control and plasma exhaust system for the beam driven Demonstration Tokamak Hybrid <span class="hlt">Reactor</span> - DTHR. In the context of a preconceptual design study of the <span class="hlt">reactor</span> and associated facility a bundle divertor concept was developed and integrated into the <span class="hlt">reactor</span> system. The overall system was found feasible and scalable for <span class="hlt">reactors</span> with intermediate torodial field strengths on axis. The important design characteristics are: the overall average current density of the divertor coils is 0.73 kA for each tesla of toroidal field on axis; the divertor windings are made from super-conducting cables supportedmore » by steel structures and are designed to be maintainable; the particle collection assembly and auxiliary cryosorption vacuum pump are dual systems designed such that they can be reactivated alterntively to allow for continuous <span class="hlt">reactor</span> operation; and the power requirement for energizing and operating the divertor is about 5 MW.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2018IJMPS..4660001O','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2018IJMPS..4660001O"><span>Neutrino Physics with Nuclear <span class="hlt">Reactors</span>: An Overview</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Ochoa-Ricoux, J. P.</p> <p></p> <p>Nuclear <span class="hlt">reactors</span> provide an excellent environment for studying neutrinos and continue to play a critical role in unveiling the secrets of these elusive particles. A rich experimental program with <span class="hlt">reactor</span> antineutrinos is currently ongoing, and leads the way in precision measurements of several oscillation parameters and in searching for new physics, such as the existence of light sterile neutrinos. Ongoing experiments have also been able to measure the flux and spectral shape of <span class="hlt">reactor</span> antineutrinos with unprecedented statistics and as a function of core fuel evolution, uncovering anomalies that will lead to new physics and/or to an improved understanding of antineutrino emission from nuclear <span class="hlt">reactors</span>. The future looks bright, with an aggressive program of next generation <span class="hlt">reactor</span> neutrino experiments that will go after some of the biggest open questions in the field. This includes the JUNO experiment, the largest liquid scintillator detector ever constructed which will push the limits of this detection technology.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_18");'>18</a></li> <li><a href="#" onclick='return showDiv("page_19");'>19</a></li> <li class="active"><span>20</span></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_20 --> <div id="page_21" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_19");'>19</a></li> <li><a href="#" onclick='return showDiv("page_20");'>20</a></li> <li class="active"><span>21</span></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li><a href="#" onclick='return showDiv("page_23");'>23</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="401"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/10141005','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/10141005"><span>Nuclear <span class="hlt">reactors</span> built, being built, or planned 1993</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Not Available</p> <p>1993-08-01</p> <p>Nuclear <span class="hlt">Reactors</span> Built, Being Built, or Planned contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1993. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE; from the US Nuclear Regulatory Commission (NRC); from the US <span class="hlt">reactor</span> manufacturers who are the principal nuclear embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: (1) a commercial <span class="hlt">reactor</span> locator map and tables of the characteristic and statistical datamore » that follow; a table of abbreviations; (2) tables of data for <span class="hlt">reactors</span> operating, being built, or planned; and (3) tables of data for <span class="hlt">reactors</span> that have been shut down permanently or dismantled. The <span class="hlt">reactors</span> are subdivided into the following parts: civilian, production, military, export, and critical assembly.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1338953','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1338953"><span>Plasma spark discharge <span class="hlt">reactor</span> and durable electrode</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Cho, Young I.; Cho, Daniel J.; Fridman, Alexander; Kim, Hyoungsup</p> <p>2017-01-10</p> <p>A plasma spark discharge <span class="hlt">reactor</span> for treating water. The plasma spark discharge <span class="hlt">reactor</span> comprises a HV electrode with a head and ground electrode that surrounds at least a portion of the HV electrode. A passage for gas may pass through the <span class="hlt">reactor</span> to a location proximate to the head to provide controlled formation of gas bubbles in order to facilitate the plasma spark discharge in a liquid environment.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19880024610&hterms=SNAP-10a&qs=N%3D0%26Ntk%3DAll%26Ntx%3Dmode%2Bmatchall%26Ntt%3DSNAP-10a','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19880024610&hterms=SNAP-10a&qs=N%3D0%26Ntk%3DAll%26Ntx%3Dmode%2Bmatchall%26Ntt%3DSNAP-10a"><span>Small <span class="hlt">reactor</span> power system for space application</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Shirbacheh, M.</p> <p>1987-01-01</p> <p>A development history and comparative performance capability evaluation is presented for spacecraft nuclear powerplant Small <span class="hlt">Reactor</span> Power System alternatives. The choice of power conversion technology depends on the <span class="hlt">reactor</span>'s operating temperature; thermionic, thermoelectric, organic Rankine, and Alkali metal thermoelectric conversion are the primary power conversion subsystem technology alternatives. A tabulation is presented for such spacecraft nuclear <span class="hlt">reactor</span> test histories as those of SNAP-10A, SP-100, and NERVA.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/958974-dismantlement-tsf-snap-reactor-assembly','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/958974-dismantlement-tsf-snap-reactor-assembly"><span>Dismantlement of the TSF-SNAP <span class="hlt">Reactor</span> Assembly</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Peretz, Fred J</p> <p>2009-01-01</p> <p>This paper describes the dismantlement of the Tower Shielding Facility (TSF)?Systems for Nuclear Auxiliary Power (SNAP) <span class="hlt">reactor</span>, a SNAP-10A <span class="hlt">reactor</span> used to validate radiation source terms and shield performance models at Oak Ridge National Laboratory (ORNL) from 1967 through 1973. After shutdown, it was placed in storage at the Y-12 National Security Complex (Y-12), eventually falling under the auspices of the Highly Enriched Uranium (HEU) Disposition Program. To facilitate downblending of the HEU present in the fuel elements, the TSF-SNAP was moved to ORNL on June 24, 2006. The <span class="hlt">reactor</span> assembly was removed from its packaging, inspected, and the sodium-potassiummore » (NaK) coolant was drained. A superheated steam process was used to chemically react the residual NaK inside the <span class="hlt">reactor</span> assembly. The heat exchanger assembly was removed from the top of the <span class="hlt">reactor</span> vessel, and the criticality safety sleeve was exchanged for a new safety sleeve that allowed for the removal of the vessel lid. A chain-mounted tubing cutter was used to separate the lid from the vessel, and the 36 fuel elements were removed and packaged in four U.S. Department of Transportation 2R/6M containers. The fuel elements were returned to Y-12 on July 13, 2006. The return of the fuel elements and disposal of all other <span class="hlt">reactor</span> materials accomplished the formal objectives of the dismantlement project. In addition, a project model was established for the handling of a fully fueled liquid-metal?cooled <span class="hlt">reactor</span> assembly. Current criticality safety codes have been benchmarked against experiments performed by Atomics International in the 1950s and 1960s. Execution of this project provides valuable experience applicable to future projects addressing space and liquid-metal-cooled <span class="hlt">reactors</span>.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/1324075-fuel-cycle-performance-thermal-spectrum-small-modular-reactors','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/1324075-fuel-cycle-performance-thermal-spectrum-small-modular-reactors"><span>Fuel Cycle Performance of Thermal Spectrum Small Modular <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Worrall, Andrew; Todosow, Michael</p> <p>2016-01-01</p> <p>Small modular <span class="hlt">reactors</span> may offer potential benefits, such as enhanced operational flexibility. However, it is vital to understand the holistic impact of small modular <span class="hlt">reactors</span> on the nuclear fuel cycle and fuel cycle performance. The focus of this paper is on the fuel cycle impacts of light water small modular <span class="hlt">reactors</span> in a once-through fuel cycle with low-enriched uranium fuel. A key objective of this paper is to describe preliminary <span class="hlt">reactor</span> core physics and fuel cycle analyses conducted in support of the U.S. Department of Energy Office of Nuclear Energy Fuel Cycle Options Campaign. Challenges with small modular <span class="hlt">reactors</span> include:more » increased neutron leakage, fewer assemblies in the core (and therefore fewer degrees of freedom in the core design), complex enrichment and burnable absorber loadings, full power operation with inserted control rods, the potential for frequent load-following operation, and shortened core height. Each of these will impact the achievable discharge burn-up in the <span class="hlt">reactor</span> and the fuel cycle performance. This paper summarizes the results of an expert elicitation focused on developing a list of the factors relevant to small modular <span class="hlt">reactor</span> fuel, core, and operation that will impact fuel cycle performance. Preliminary scoping analyses were performed using a regulatory-grade <span class="hlt">reactor</span> core simulator. The hypothetical light water small modular <span class="hlt">reactor</span> considered in these preliminary scoping studies is a cartridge type one-batch core with 4.9% enrichment. Some core parameters, such as the size of the <span class="hlt">reactor</span> and general assembly layout, are similar to an example small modular <span class="hlt">reactor</span> concept from industry. The high-level issues identified and preliminary scoping calculations in this paper are intended to inform on potential fuel cycle impacts of one-batch thermal spectrum SMRs. In particular, this paper highlights the impact of increased neutron leakage and reduced number of batches on the achievable burn-up of the <span class="hlt">reactor</span>. Fuel cycle</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://cfpub.epa.gov/si/si_public_record_report.cfm?dirEntryId=128577&Lab=NRMRL&keyword=corona&actType=&TIMSType=+&TIMSSubTypeID=&DEID=&epaNumber=&ntisID=&archiveStatus=Both&ombCat=Any&dateBeginCreated=&dateEndCreated=&dateBeginPublishedPresented=&dateEndPublishedPresented=&dateBeginUpdated=&dateEndUpdated=&dateBeginCompleted=&dateEndCompleted=&personID=&role=Any&journalID=&publisherID=&sortBy=revisionDate&count=50','EPA-EIMS'); return false;" href="https://cfpub.epa.gov/si/si_public_record_report.cfm?dirEntryId=128577&Lab=NRMRL&keyword=corona&actType=&TIMSType=+&TIMSSubTypeID=&DEID=&epaNumber=&ntisID=&archiveStatus=Both&ombCat=Any&dateBeginCreated=&dateEndCreated=&dateBeginPublishedPresented=&dateEndPublishedPresented=&dateBeginUpdated=&dateEndUpdated=&dateBeginCompleted=&dateEndCompleted=&personID=&role=Any&journalID=&publisherID=&sortBy=revisionDate&count=50"><span>CONTROL OF VOLATILE ORGANIC COMPOUNDS BY AN AC ENERGIZED FERROELECTRIC PELLET <span class="hlt">REACTOR</span> AND A PULSED CORONA <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://oaspub.epa.gov/eims/query.page">EPA Science Inventory</a></p> <p></p> <p></p> <p>The paper gives results of a study to develop baseline engineering data to demonstrate the feasibility of application of plasma <span class="hlt">reactors</span> to the destruction of various volatile organic compounds at ppm levels. Two laboratory-scale <span class="hlt">reactors</span>, an alternating current energized ferroel...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/22408033-consumption-electric-power-inside-silent-discharge-reactors','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/22408033-consumption-electric-power-inside-silent-discharge-reactors"><span>Consumption of the electric power inside silent discharge <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Yehia, Ashraf, E-mail: yehia30161@yahoo.com</p> <p></p> <p>An experimental study was made in this paper to investigate the relation between the places of the dielectric barriers, which cover the surfaces of the electrodes in the coaxial cylindrical <span class="hlt">reactors</span>, and the rate of change of the electric power that is consumed in forming silent discharges. Therefore, silent discharges have been formed inside three coaxial cylindrical <span class="hlt">reactors</span>. The dielectric barriers in these <span class="hlt">reactors</span> were pasted on both the internal surface of the outer electrode in the first <span class="hlt">reactor</span> and the external surface of the inner electrode in the second <span class="hlt">reactor</span> as well as the surfaces of the two electrodesmore » in the third <span class="hlt">reactor</span>. The <span class="hlt">reactor</span> under study has been fed by atmospheric air that flowed inside it with a constant rate at normal temperature and pressure, in parallel with the application of a sinusoidal ac voltage between the electrodes of the <span class="hlt">reactor</span>. The electric power consumed in forming the silent discharges inside the three <span class="hlt">reactors</span> was measured as a function of the ac peak voltage. The validity of the experimental results was investigated by applying Manley's equation on the same discharge conditions. The results have shown that the rate of consumption of the electric power relative to the ac peak voltage per unit width of the discharge gap improves by a ratio of either 26.8% or 80% or 128% depending on the places of the dielectric barriers that cover the surfaces of the electrodes inside the three <span class="hlt">reactors</span>.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2015APS..DPPYP2008S','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2015APS..DPPYP2008S"><span>Generic Stellarator-like Magnetic Fusion <span class="hlt">Reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Sheffield, John; Spong, Donald</p> <p>2015-11-01</p> <p>The Generic Magnetic Fusion <span class="hlt">Reactor</span> paper, published in 1985, has been updated, reflecting the improved science and technology base in the magnetic fusion program. Key changes beyond inflation are driven by important benchmark numbers for technologies and costs from ITER construction, and the use of a more conservative neutron wall flux and fluence in modern fusion <span class="hlt">reactor</span> designs. In this paper the generic approach is applied to a catalyzed D-D stellarator-like <span class="hlt">reactor</span>. It is shown that an interesting power plant might be possible if the following parameters could be achieved for a reference <span class="hlt">reactor</span>: R/ < a > ~ 4 , confinement factor, fren = 0.9-1.15, < β > ~ 8 . 0 -11.5 %, Zeff ~ 1.45 plus a relativistic temperature correction, fraction of fast ions lost ~ 0.07, Bm ~ 14-16 T, and R ~ 18-24 m. J. Sheffield was supported under ORNL subcontract 4000088999 with the University of Tennessee.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/872434','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/872434"><span>Fast quench <span class="hlt">reactor</span> method</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Detering, Brent A.; Donaldson, Alan D.; Fincke, James R.; Kong, Peter C.; Berry, Ray A.</p> <p>1999-01-01</p> <p>A fast quench reaction includes a <span class="hlt">reactor</span> chamber having a high temperature heating means such as a plasma torch at its inlet and a means of rapidly expanding a reactant stream, such as a restrictive convergent-divergent nozzle at its outlet end. Metal halide reactants are injected into the <span class="hlt">reactor</span> chamber. Reducing gas is added at different stages in the process to form a desired end product and prevent back reactions. The resulting heated gaseous stream is then rapidly cooled by expansion of the gaseous stream.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19930017765','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19930017765"><span>Particle bed <span class="hlt">reactor</span> modeling</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Sapyta, Joe; Reid, Hank; Walton, Lew</p> <p>1993-01-01</p> <p>The topics are presented in viewgraph form and include the following: particle bed <span class="hlt">reactor</span> (PBR) core cross section; PBR bleed cycle; fuel and moderator flow paths; PBR modeling requirements; characteristics of PBR and nuclear thermal propulsion (NTP) modeling; challenges for PBR and NTP modeling; thermal hydraulic computer codes; capabilities for PBR/<span class="hlt">reactor</span> application; thermal/hydralic codes; limitations; physical correlations; comparison of predicted friction factor and experimental data; frit pressure drop testing; cold frit mask factor; decay heat flow rate; startup transient simulation; and philosophy of systems modeling.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/911892','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/911892"><span>Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water <span class="hlt">Reactors</span> and Supercritical <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>D.M. McEligot; K. G. Condie; G. E. McCreery</p> <p>2005-10-01</p> <p>Background: The ultimate goal of the study is the improvement of predictive methods for safety analyses and design of Generation IV <span class="hlt">reactor</span> systems such as supercritical water <span class="hlt">reactors</span> (SCWR) for higher efficiency, improved performance and operation, design simplification, enhanced safety and reduced waste and cost. The objective of this Korean / US / laboratory / university collaboration of coupled fundamental computational and experimental studies is to develop the supporting knowledge needed for improved predictive techniques for use in the technology development of Generation IV <span class="hlt">reactor</span> concepts and their passive safety systems. The present study emphasizes SCWR concepts in the Generationmore » IV program.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19750046799&hterms=automobiles&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D60%26Ntt%3Dautomobiles','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19750046799&hterms=automobiles&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D60%26Ntt%3Dautomobiles"><span>Design and evaluation of experimental ceramic automobile thermal <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Stone, P. L.; Blankenship, C. P.</p> <p>1974-01-01</p> <p>The paper summarizes the results obtained in an exploratory evaluation of ceramics for automobile thermal <span class="hlt">reactors</span>. Candidate ceramic materials were evaluated in several <span class="hlt">reactor</span> designs using both engine dynamometer and vehicle road tests. Silicon carbide contained in a corrugated metal support structure exhibited the best performance, lasting 1100 hours in engine dynamometer tests and for more than 38,600 kilimeters (24,000 miles) in vehicle road tests. Although <span class="hlt">reactors</span> containing glass-ceramic components did not perform as well as silicon carbide, the glass-ceramics still offer good potential for <span class="hlt">reactor</span> use with improved <span class="hlt">reactor</span> designs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/19740019922','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/19740019922"><span>Design and evaluation of experimental ceramic automobile thermal <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Stone, P. L.; Blankenship, C. P.</p> <p>1974-01-01</p> <p>The results obtained in an exploratory evaluation of ceramics for automobile thermal <span class="hlt">reactors</span> are summarized. Candidate ceramic materials were evaluated in several <span class="hlt">reactor</span> designs by using both engine-dynamometer and vehicle road tests. Silicon carbide contained in a corrugated-metal support structure exhibited the best performance, lasting 1100 hr in engine-dynamometer tests and more than 38,600 km (24000 miles) in vehicle road tests. Although <span class="hlt">reactors</span> containing glass-ceramic components did not perform as well as those containing silicon carbide, the glass-ceramics still offer good potential for <span class="hlt">reactor</span> use with improved <span class="hlt">reactor</span> designs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2009PhDT.......208S','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2009PhDT.......208S"><span>Design and analysis of a nuclear <span class="hlt">reactor</span> core for innovative small light water <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Soldatov, Alexey I.</p> <p></p> <p>In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water <span class="hlt">Reactor</span> (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design issues related with increased fuel enrichment (8.0%) and specific MASLWR operational conditions (such as lower operational pressure and temperature, and increased leakage due to small core). Neutron physics calculations are performed with the commercial nuclear industry tools CASMO-4 and SIMULATE-3, developed by Studsvik Scandpower Inc. The first set of results are generated from infinite lattice level calculations with CASMO-4, and focus on evaluation of the principal differences between standard PWR fuel and MASLWR fuel. Chapter 4-1 covers aspects of fuel isotopic composition changes with burnup, evaluation of kinetic parameters and reactivity coefficients. Chapter 4-2 discusses gadolinium self-shielding and shadowing effects, and subsequent impacts on power generation peaking and <span class="hlt">Reactor</span> Control System shadowing. The second aspect of the research is dedicated to core design issues, such as reflector design (chapter 4-3), burnable absorber distribution and programmed fuel burnup and fuel use strategy (chapter 4-4). This section also includes discussion of the parameters important for safety and evaluation of <span class="hlt">Reactor</span> Control System options for the proposed core design. An evaluation of the sensitivity of the proposed design to uncertainty in calculated parameters is presented in chapter 4-5. The results presented in this dissertation cover a new area of <span class="hlt">reactor</span> design and operational parameters, and may be applicable to other small and large pressurized water <span class="hlt">reactor</span> designs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4301198','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4301198"><span>NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Treshow, M.</p> <p>1958-08-19</p> <p>A neuclear <span class="hlt">reactor</span> is described of the heterogeneous type and employing replaceable tubular fuel elements and heavy water as a coolant and moderator. A pluraltty of fuel tubesa having their axes parallel, extend through a tank type pressure vessel which contatns the liquid moderator. The fuel elements are disposed within the fuel tubes in the reaetive portion of the pressure vessel during normal operation and the fuel tubes have removable plug members at each end to permit charging and discharging of the fuel elements. The fuel elements are cylindrical strands of jacketed fissionable material having helical exterior ribs. A bundle of fuel elements are held within each fuel tube with their longitudinal axes parallel, the ribs serving to space them apart along their lengths. Coolant liquid is circulated through the fuel tubes between the spaced fuel elements. Suitable control rod and monitoring means are provided for controlling the <span class="hlt">reactor</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017HMT....53.3099T','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017HMT....53.3099T"><span>Mathematical modeling of methyl ester concentration distribution in a continuous membrane tubular <span class="hlt">reactor</span> and comparison with conventional tubular <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Talaghat, M. R.; Jokar, S. M.; Modarres, E.</p> <p>2017-10-01</p> <p>The reduction of fossil fuel resources and environmental issues made researchers find alternative fuels include biodiesels. One of the most widely used methods for production of biodiesel on a commercial scale is transesterification method. In this work, the biodiesel production by a transesterification method was modeled. Sodium hydroxide was considered as a catalyst to produce biodiesel from canola oil and methanol in a continuous tubular ceramic membranes <span class="hlt">reactor</span>. As the Biodiesel production reaction from triglycerides is an equilibrium reaction, the reaction rate constants depend on temperature and related linearly to catalyst concentration. By using the mass balance for a membrane tubular <span class="hlt">reactor</span> and considering the variation of raw materials and products concentration with time, the set of governing equations were solved by numerical methods. The results clearly show the superiority of membrane <span class="hlt">reactor</span> than conventional tubular <span class="hlt">reactors</span>. Afterward, the influences of molar ratio of alcohol to oil, weight percentage of the catalyst, and residence time on the performance of biodiesel production <span class="hlt">reactor</span> were investigated.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4700694','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4700694"><span>COMPOSITE NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Menke, J.R.</p> <p>1963-06-11</p> <p>This patent relates to a <span class="hlt">reactor</span> having a core which comprises an inner active region and an outer active region, each region separately having a k effective less than one and a k infinity greater than one. The inner and outer regions in combination have a k effective at least equal to one and each region contributes substantially to the k effective of the <span class="hlt">reactor</span> core. The inner region has a low moderator to fuel ratio such that the majority of fissions occurring therein are induced by neutrons having energies greater than thermal. The outer region has a high moderator to fuel ratio such that the majority of fissions occurring therein are induced by thermal neutrons. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/20104491-role-nuclear-reactors-space-exploration-development','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/20104491-role-nuclear-reactors-space-exploration-development"><span>The role of nuclear <span class="hlt">reactors</span> in space exploration and development</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Lipinski, R.J.</p> <p>2000-07-01</p> <p>The United States has launched more than 20 radioisotopic thermoelectric generators (RTGs) into space over the past 30 yr but has launched only one nuclear <span class="hlt">reactor</span>, and that was in 1965. Russia has launched more than 30 <span class="hlt">reactors</span>. The RTGs use the heat of alpha decay of {sup 238}Pu for power and typically generate <1 kW of electricity. Apollo, Pioneer, Voyager, Viking, Galileo, Ulysses, and Cassini all used RTGs. Space <span class="hlt">reactors</span> use the fission energy of {sup 235}U; typical designs are for 100 to 1000 kW of electricity. The only US space <span class="hlt">reactor</span> launch (SNAP-10A) was a demonstration mission. Onemore » reason for the lack of space <span class="hlt">reactor</span> use by the United States was the lack of space missions that required high power. But, another was the assumed negative publicity that would accompany a <span class="hlt">reactor</span> launch. The net result is that all space <span class="hlt">reactor</span> programs after 1970 were terminated before an operating space <span class="hlt">reactor</span> could be developed, and they are now many years from recovering the ability to build them. Two major near-term needs for space <span class="hlt">reactors</span> are the human exploration of Mars and advanced missions to and beyond the orbit of Jupiter. To help obtain public acceptance of space <span class="hlt">reactors</span>, one must correct some of the misconceptions concerning space <span class="hlt">reactors</span> and convey the following facts to the public and to decision makers: Space <span class="hlt">reactors</span> are 1000 times smaller in power and size than a commercial power <span class="hlt">reactor</span>. A space <span class="hlt">reactor</span> at launch is only as radioactive as a pile of dirt 60 m (200 ft) across. A space <span class="hlt">reactor</span> contains no plutonium at launch. It does not become significantly radioactive until it is turned on, and it will be engineered so that no launch accident can turn it on, even if that means fueling it after launch. The <span class="hlt">reactor</span> will not be turned on until it is in a high stable orbit or even on an earth-escape trajectory for some missions. The benefits of space <span class="hlt">reactors</span> are that they give humanity a stairway to the planets and perhaps the stars. They open a</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1417852','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1417852"><span>Fail-safe reactivity compensation method for a nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Nygaard, Erik T.; Angelo, Peter L.; Aase, Scott B.</p> <p></p> <p>The present invention relates generally to the field of compensation methods for nuclear <span class="hlt">reactors</span> and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear <span class="hlt">reactors</span>. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear <span class="hlt">reactor</span>. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear <span class="hlt">reactor</span> through a method that does not rely on moving components into or out of a <span class="hlt">reactor</span> core, nor does the method of the present invention rely on themore » constant repositioning of control rods within a nuclear <span class="hlt">reactor</span> in order to maintain a critical state.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/17441035','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/17441035"><span>Multiphase organic synthesis in microchannel <span class="hlt">reactors</span>.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Kobayashi, Juta; Mori, Yuichiro; Kobayashi, Shū</p> <p>2006-07-17</p> <p>"Miniaturization" is one of the most important aspects in today's technology. Organic chemistry is no exception. The search for highly effective, controllable, environmentally friendly methods for preparing products is of prime importance. The development of multiphase organic reactions in microchannel <span class="hlt">reactors</span> has gained significant importance in recent years to allow novel reactivity, and has led to many fruitful results that are not attainable in conventional <span class="hlt">reactors</span>. This Focus Review aims to shed light on how effectively multiphase organic reactions can be conducted with microchannel <span class="hlt">reactors</span> by providing examples of recent remarkable studies, which have been grouped on the basis of the phases involved.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_19");'>19</a></li> <li><a href="#" onclick='return showDiv("page_20");'>20</a></li> <li class="active"><span>21</span></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li><a href="#" onclick='return showDiv("page_23");'>23</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_21 --> <div id="page_22" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_20");'>20</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li class="active"><span>22</span></li> <li><a href="#" onclick='return showDiv("page_23");'>23</a></li> <li><a href="#" onclick='return showDiv("page_24");'>24</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="421"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/12693444','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/12693444"><span>Enzyme <span class="hlt">reactor</span> design under thermal inactivation.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Illanes, Andrés; Wilson, Lorena</p> <p>2003-01-01</p> <p>Temperature is a very relevant variable for any bioprocess. Temperature optimization of bioreactor operation is a key aspect for process economics. This is especially true for enzyme-catalyzed processes, because enzymes are complex, unstable catalysts whose technological potential relies on their operational stability. Enzyme <span class="hlt">reactor</span> design is presented with a special emphasis on the effect of thermal inactivation. Enzyme thermal inactivation is a very complex process from a mechanistic point of view. However, for the purpose of enzyme <span class="hlt">reactor</span> design, it has been oversimplified frequently, considering one-stage first-order kinetics of inactivation and data gathered under nonreactive conditions that poorly represent the actual conditions within the <span class="hlt">reactor</span>. More complex mechanisms are frequent, especially in the case of immobilized enzymes, and most important is the effect of catalytic modulators (substrates and products) on enzyme stability under operation conditions. This review focuses primarily on <span class="hlt">reactor</span> design and operation under modulated thermal inactivation. It also presents a scheme for bioreactor temperature optimization, based on validated temperature-explicit functions for all the kinetic and inactivation parameters involved. More conventional enzyme <span class="hlt">reactor</span> design is presented merely as a background for the purpose of highlighting the need for a deeper insight into enzyme inactivation for proper bioreactor design.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/871537','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/871537"><span>Fast quench <span class="hlt">reactor</span> and method</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Detering, Brent A.; Donaldson, Alan D.; Fincke, James R.; Kong, Peter C.</p> <p>1998-01-01</p> <p>A fast quench reaction includes a <span class="hlt">reactor</span> chamber having a high temperature heating means such as a plasma torch at its inlet and a restrictive convergent-divergent nozzle at its outlet end. Reactants are injected into the <span class="hlt">reactor</span> chamber. The resulting heated gaseous stream is then rapidly cooled by passage through the nozzle. This "freezes" the desired end product(s) in the heated equilibrium reaction stage.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/875304','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/875304"><span>Fast quench <span class="hlt">reactor</span> and method</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Detering, Brent A.; Donaldson, Alan D.; Fincke, James R.; Kong, Peter C.</p> <p>2002-01-01</p> <p>A fast quench reaction includes a <span class="hlt">reactor</span> chamber having a high temperature heating means such as a plasma torch at its inlet and a restrictive convergent-divergent nozzle at its outlet end. Reactants are injected into the <span class="hlt">reactor</span> chamber. The resulting heated gaseous stream is then rapidly cooled by passage through the nozzle. This "freezes" the desired end product(s) in the heated equilibrium reaction stage.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1176702','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1176702"><span>Fast quench <span class="hlt">reactor</span> and method</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Detering, Brent A.; Donaldson, Alan D.; Fincke, James R.; Kong, Peter C.</p> <p>2002-09-24</p> <p>A fast quench reaction includes a <span class="hlt">reactor</span> chamber having a high temperature heating means such as a plasma torch at its inlet and a restrictive convergent-divergent nozzle at its outlet end. Reactants are injected into the <span class="hlt">reactor</span> chamber. The resulting heated gaseous stream is then rapidly cooled by passage through the nozzle. This "freezes" the desired end product(s) in the heated equilibrium reaction stage.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1032715','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1032715"><span>Neutron shielding panels for <span class="hlt">reactor</span> pressure vessels</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Singleton, Norman R [Murrysville, PA</p> <p>2011-11-22</p> <p>In a nuclear <span class="hlt">reactor</span> neutron panels varying in thickness in the circumferential direction are disposed at spaced circumferential locations around the <span class="hlt">reactor</span> core so that the greatest radial thickness is at the point of highest fluence with lesser thicknesses at adjacent locations where the fluence level is lower. The neutron panels are disposed between the core barrel and the interior of the <span class="hlt">reactor</span> vessel to maintain radiation exposure to the vessel within acceptable limits.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2009rdsa.conf.....V','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2009rdsa.conf.....V"><span><span class="hlt">Reactor</span> Dosimetry State of the Art 2008</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Voorbraak, Wim; Debarberis, Luigi; D'Hondt, Pierre; Wagemans, Jan</p> <p>2009-08-01</p> <p>Oral session 1: Retrospective dosimetry. Retrospective dosimetry of VVER 440 <span class="hlt">reactor</span> pressure vessel at the 3rd unit of Dukovany NPP / M. Marek ... [et al.]. Retrospective dosimetry study at the RPV of NPP Greifswald unit 1 / J. Konheiser ... [et al.]. Test of prototype detector for retrospective neutron dosimetry of <span class="hlt">reactor</span> internals and vessel / K. Hayashi ... [et al.]. Neutron doses to the concrete vessel and tendons of a magnox <span class="hlt">reactor</span> using retrospective dosimetry / D. A. Allen ... [et al.]. A retrospective dosimetry feasibility study for Atucha I / J. Wagemans ... [et al.]. Retrospective <span class="hlt">reactor</span> dosimetry with zirconium alloy samples in a PWR / L. R. Greenwood and J. P. Foster -- Oral session 2: Experimental techniques. Characterizing the Time-dependent components of <span class="hlt">reactor</span> n/y environments / P. J. Griffin, S. M. Luker and A. J. Suo-Anttila. Measurements of the recoil-ion response of silicon carbide detectors to fast neutrons / F. H. Ruddy, J. G. Seidel and F. Franceschini. Measurement of the neutron spectrum of the HB-4 cold source at the high flux isotope <span class="hlt">reactor</span> at Oak Ridge National Laboratory / J. L. Robertson and E. B. Iverson. Feasibility of cavity ring-down laser spectroscopy for dose rate monitoring on nuclear <span class="hlt">reactor</span> / H. Tomita ... [et al.]. Measuring transistor damage factors in a non-stable defect environment / D. B. King ... [et al.]. Neutron-detection based monitoring of void effects in boiling water <span class="hlt">reactors</span> / J. Loberg ... [et al.] -- Poster session 1: Power <span class="hlt">reactor</span> surveillance, retrospective dosimetry, benchmarks and inter-comparisons, adjustment methods, experimental techniques, transport calculations. Improved diagnostics for analysis of a <span class="hlt">reactor</span> pulse radiation environment / S. M. Luker ... [et al.]. Simulation of the response of silicon carbide fast neutron detectors / F. Franceschini, F. H. Ruddy and B. Petrović. NSV A-3: a computer code for least-squares adjustment of neutron spectra and measured dosimeter responses / J. G</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://images.nasa.gov/#/details-GRC-1961-C-55851.html','SCIGOVIMAGE-NASA'); return false;" href="https://images.nasa.gov/#/details-GRC-1961-C-55851.html"><span>Interior of the Plum Brook <span class="hlt">Reactor</span> Facility</span></a></p> <p><a target="_blank" href="https://images.nasa.gov/">NASA Image and Video Library</a></p> <p></p> <p>1961-02-21</p> <p>A view inside the 55-foot high containment vessel of the National Aeronautics and Space Administration (NASA) Plum Brook <span class="hlt">Reactor</span> Facility in Sandusky, Ohio. The 60-megawatt test <span class="hlt">reactor</span> went critical for the first time in 1961 and began its full-power research operations in 1963. From 1961 to 1973, this <span class="hlt">reactor</span> performed some of the nation’s most advanced nuclear research. The <span class="hlt">reactor</span> was designed to determine the behavior of metals and other materials after long durations of irradiation. The materials would be used to construct a nuclear-powered rocket. The <span class="hlt">reactor</span> core, where the chain reaction occurred, sat at the bottom of the tubular pressure vessel, seen here at the center of the shielding pool. The core contained fuel rods with uranium isotopes. A cooling system was needed to reduce the heat levels during the reaction. A neutron-impervious reflector was also employed to send many of the neutrons back to the core. The Plum Brook <span class="hlt">Reactor</span> Facility was constructed from high-density concrete and steel to prevent the excess neutrons from escaping the facility, but the water in the pool shielded most of the radiation. The water, found in three of the four quadrants served as a reflector, moderator, and coolant. In this photograph, the three 20-ton protective shrapnel shields and hatch have been removed from the top of the pressure tank revealing the <span class="hlt">reactor</span> tank. An overhead crane could be manipulated to reach any section of this room. It was used to remove the shrapnel shields and transfer equipment.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/10128809','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/10128809"><span>Control console replacement at the WPI <span class="hlt">Reactor</span>. [Final report</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Not Available</p> <p>1992-12-31</p> <p>With partial funding from the Department of Energy (DOE) University <span class="hlt">Reactor</span> Instrumentation Upgrade Program (DOE Grant No. DE-FG02-90ER12982), the original control console at the Worcester Polytechnic Institute (WPI) <span class="hlt">Reactor</span> has been replaced with a modern system. The new console maintains the original design bases and functionality while utilizing current technology. An advanced remote monitoring system has been added to augment the educational capabilities of the <span class="hlt">reactor</span>. Designed and built by General Electric in 1959, the open pool nuclear training <span class="hlt">reactor</span> at WPI was one of the first such facilities in the nation located on a university campus. Devoted to undergraduatemore » use, the <span class="hlt">reactor</span> and its related facilities have been since used to train two generations of nuclear engineers and scientists for the nuclear industry. The <span class="hlt">reactor</span> power level was upgraded from 1 to 10 kill in 1969, and its operating license was renewed for 20 years in 1983. In 1988, the <span class="hlt">reactor</span> was converted to low enriched uranium. The low power output of the <span class="hlt">reactor</span> and ergonomic facility design make it an ideal tool for undergraduate nuclear engineering education and other training.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1415120','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1415120"><span>EBR-II <span class="hlt">Reactor</span> Physics Benchmark Evaluation Report</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Pope, Chad L.; Lum, Edward S; Stewart, Ryan</p> <p></p> <p>This report provides a <span class="hlt">reactor</span> physics benchmark evaluation with associated uncertainty quantification for the critical configuration of the April 1986 Experimental Breeder <span class="hlt">Reactor</span> II Run 138B core configuration.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/678568','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/678568"><span>Fast quench <span class="hlt">reactor</span> method</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Detering, B.A.; Donaldson, A.D.; Fincke, J.R.; Kong, P.C.; Berry, R.A.</p> <p>1999-08-10</p> <p>A fast quench reaction includes a <span class="hlt">reactor</span> chamber having a high temperature heating means such as a plasma torch at its inlet and a means of rapidly expanding a reactant stream, such as a restrictive convergent-divergent nozzle at its outlet end. Metal halide reactants are injected into the <span class="hlt">reactor</span> chamber. Reducing gas is added at different stages in the process to form a desired end product and prevent back reactions. The resulting heated gaseous stream is then rapidly cooled by expansion of the gaseous stream. 8 figs.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2011-title10-vol1/pdf/CFR-2011-title10-vol1-sec1-44.pdf','CFR2011'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2011-title10-vol1/pdf/CFR-2011-title10-vol1-sec1-44.pdf"><span>10 CFR 1.44 - Office of New <span class="hlt">Reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2011&page.go=Go">Code of Federal Regulations, 2011 CFR</a></p> <p></p> <p>2011-01-01</p> <p>... 10 Energy 1 2011-01-01 2011-01-01 false Office of New <span class="hlt">Reactors</span>. 1.44 Section 1.44 Energy NUCLEAR... Office of New <span class="hlt">Reactors</span>. The Office of New Reactors— (a) Develops, promulgates and implements regulations... safeguarding of nuclear <span class="hlt">reactor</span> facilities licensed under part 52 of this chapter prior to initial commencement...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2010-title10-vol1/pdf/CFR-2010-title10-vol1-sec1-44.pdf','CFR'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2010-title10-vol1/pdf/CFR-2010-title10-vol1-sec1-44.pdf"><span>10 CFR 1.44 - Office of New <span class="hlt">Reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2010&page.go=Go">Code of Federal Regulations, 2010 CFR</a></p> <p></p> <p>2010-01-01</p> <p>... 10 Energy 1 2010-01-01 2010-01-01 false Office of New <span class="hlt">Reactors</span>. 1.44 Section 1.44 Energy NUCLEAR... Office of New <span class="hlt">Reactors</span>. The Office of New Reactors— (a) Develops, promulgates and implements regulations... safeguarding of nuclear <span class="hlt">reactor</span> facilities licensed under part 52 of this chapter prior to initial commencement...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2013-title10-vol1/pdf/CFR-2013-title10-vol1-sec1-44.pdf','CFR2013'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2013-title10-vol1/pdf/CFR-2013-title10-vol1-sec1-44.pdf"><span>10 CFR 1.44 - Office of New <span class="hlt">Reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2013&page.go=Go">Code of Federal Regulations, 2013 CFR</a></p> <p></p> <p>2013-01-01</p> <p>... 10 Energy 1 2013-01-01 2013-01-01 false Office of New <span class="hlt">Reactors</span>. 1.44 Section 1.44 Energy NUCLEAR... safeguarding of nuclear <span class="hlt">reactor</span> facilities licensed under part 52 of this chapter prior to initial commencement... Office of New <span class="hlt">Reactors</span>. The Office of New Reactors— (a) Develops, promulgates and implements regulations...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2014-title10-vol1/pdf/CFR-2014-title10-vol1-sec1-44.pdf','CFR2014'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2014-title10-vol1/pdf/CFR-2014-title10-vol1-sec1-44.pdf"><span>10 CFR 1.44 - Office of New <span class="hlt">Reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2014&page.go=Go">Code of Federal Regulations, 2014 CFR</a></p> <p></p> <p>2014-01-01</p> <p>... 10 Energy 1 2014-01-01 2014-01-01 false Office of New <span class="hlt">Reactors</span>. 1.44 Section 1.44 Energy NUCLEAR... safeguarding of nuclear <span class="hlt">reactor</span> facilities licensed under part 52 of this chapter prior to initial commencement... Office of New <span class="hlt">Reactors</span>. The Office of New Reactors— (a) Develops, promulgates and implements regulations...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2012-title10-vol1/pdf/CFR-2012-title10-vol1-sec1-44.pdf','CFR2012'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2012-title10-vol1/pdf/CFR-2012-title10-vol1-sec1-44.pdf"><span>10 CFR 1.44 - Office of New <span class="hlt">Reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2012&page.go=Go">Code of Federal Regulations, 2012 CFR</a></p> <p></p> <p>2012-01-01</p> <p>... 10 Energy 1 2012-01-01 2012-01-01 false Office of New <span class="hlt">Reactors</span>. 1.44 Section 1.44 Energy NUCLEAR... safeguarding of nuclear <span class="hlt">reactor</span> facilities licensed under part 52 of this chapter prior to initial commencement... Office of New <span class="hlt">Reactors</span>. The Office of New Reactors— (a) Develops, promulgates and implements regulations...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19860035996&hterms=Electric+power+system+reliability&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D60%26Ntt%3DElectric%2Bpower%2Bsystem%2Breliability','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19860035996&hterms=Electric+power+system+reliability&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D60%26Ntt%3DElectric%2Bpower%2Bsystem%2Breliability"><span><span class="hlt">Reactor</span> power system deployment and startup</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Wetch, J. R.; Nelin, C. J.; Britt, E. J.; Klein, G.</p> <p>1985-01-01</p> <p>This paper addresses issues that should receive further examination in the near-term as concept selection for development of a U.S. space <span class="hlt">reactor</span> power system is approached. The issues include: the economics, practicality and system reliability associated with transfer of nuclear spacecraft from low earth shuttle orbits to operational orbits, via chemical propulsion versus nuclear electric propulsion; possible astronaut supervised <span class="hlt">reactor</span> and nuclear electric propulsion startup in low altitude Shuttle orbit; potential deployment methods for nuclear powered spacecraft from Shuttle; the general public safety of low altitude startup and nuclear safe and disposal orbits; the question of preferred <span class="hlt">reactor</span> power level; and the question of frozen versus molten alkali metal coolant during launch and deployment. These issues must be considered now because they impact the SP-100 concept selection, power level selection, weight and size limits, use of deployable radiators, reliability requirements, and economics, as well as the degree of need for and the urgency of developing space <span class="hlt">reactor</span> power systems.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/1987smpr.rept......','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/1987smpr.rept......"><span>Small and medium power <span class="hlt">reactors</span> 1987</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p></p> <p>1987-12-01</p> <p>This TECDOC follows the publication of TECDOC-347: Small and Medium Power <span class="hlt">Reactors</span> (SMPR) Project Initiation Study, Phase 1, published in 1985 and TECDOC-376: Small and Medium Power <span class="hlt">Reactors</span> 1985 published in 1986. It is mainly intended for decision makers in Developing Member States interested in embarking on a nuclear power program. It consists of two parts: (1) guidelines for the introduction of small and medium power <span class="hlt">reactors</span> in developing countries. These Guidelines were established during the Advisory Group Meeting held in Vienna from 11 to 15 May 1987. Their purpose is to review key aspects relating to the introduction of small and medium power <span class="hlt">reactors</span> in developing countries; (2) up-dated information on SMPR Concepts Contributed by Supplier Industries. According to the recommendations of the Second Technical Committee Meeting on SMPRs held in Vienna in March 1985, this part contains the up-dated information formerly published in Annex 1 of the above mentioned TECDOC-347.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/1993snpp.symp...10T','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/1993snpp.symp...10T"><span>Space <span class="hlt">reactor</span> fuel element testing in upgraded TREAT</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Todosow, M.; Bezler, P.; Ludewig, H.; Kato, W. Y.</p> <p></p> <p>The testing of candidate fuel elements at prototypic operating conditions with respect to temperature, power density, hydrogen coolant flow rate, etc.; a crucial component in the development and qualification of nuclear rocket engines based on the Particle Bed <span class="hlt">Reactor</span> (PBR); NERVA-derivative; and other concepts are discussed. Such testing may be performed at existing <span class="hlt">reactors</span>, or at new facilities. A scoping study has been performed to assess the feasibility of testing PBR based fuel elements at the TREAT <span class="hlt">reactor</span>. Initial results suggest that full-scale PBR elements could be tested at an average energy deposition of approximately 60-80 MW-s/L in the current TREAT <span class="hlt">reactor</span>. If the TREAT <span class="hlt">reactor</span> was upgraded to include fuel elements with a higher temperature limit, average energy deposition of approximately 100 MW/L may be achievable.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/1993AIPC..271.1167T','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/1993AIPC..271.1167T"><span>Space <span class="hlt">reactor</span> fuel element testing in upgraded TREAT</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Todosow, Michael; Bezler, Paul; Ludewig, Hans; Kato, Walter Y.</p> <p>1993-01-01</p> <p>The testing of candidate fuel elements at prototypic operating conditions with respect to temperature, power density, hydrogen coolant flow rate, etc., is a crucial component in the development and qualification of nuclear rocket engines based on the Particle Bed <span class="hlt">Reactor</span> (PBR), NERVA-derivative, and other concepts. Such testing may be performed at existing <span class="hlt">reactors</span>, or at new facilities. A scoping study has been performed to assess the feasibility of testing PBR based fuel elements at the TREAT <span class="hlt">reactor</span>. Initial results suggests that full-scale PBR elements could be tested at an average energy deposition of ˜60-80 MW-s/L in the current TREAT <span class="hlt">reactor</span>. If the TREAT <span class="hlt">reactor</span> was upgraded to include fuel elements with a higher temperture limit, average energy deposition of ˜100 MW/L may be achievable.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1162105','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1162105"><span><span class="hlt">Reactor</span> pressure vessel head vents and methods of using the same</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Gels, John L; Keck, David J; Deaver, Gerald A</p> <p>2014-10-28</p> <p>Internal head vents are usable in nuclear <span class="hlt">reactors</span> and include piping inside of the <span class="hlt">reactor</span> pressure vessel with a vent in the <span class="hlt">reactor</span> upper head. Piping extends downward from the upper head and passes outside of the <span class="hlt">reactor</span> to permit the gas to escape or be forcibly vented outside of the <span class="hlt">reactor</span> without external piping on the upper head. The piping may include upper and lowers section that removably mate where the upper head joins to the <span class="hlt">reactor</span> pressure vessel. The removable mating may include a compressible bellows and corresponding funnel. The piping is fabricated of nuclear-<span class="hlt">reactor</span>-safe materials, including carbon steel, stainless steel, and/or a Ni--Cr--Fe alloy. Methods install an internal head vent in a nuclear <span class="hlt">reactor</span> by securing piping to an internal surface of an upper head of the nuclear <span class="hlt">reactor</span> and/or securing piping to an internal surface of a <span class="hlt">reactor</span> pressure vessel.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_20");'>20</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li class="active"><span>22</span></li> <li><a href="#" onclick='return showDiv("page_23");'>23</a></li> <li><a href="#" onclick='return showDiv("page_24");'>24</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_22 --> <div id="page_23" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li class="active"><span>23</span></li> <li><a href="#" onclick='return showDiv("page_24");'>24</a></li> <li><a href="#" onclick='return showDiv("page_25");'>25</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="441"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5122307','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/5122307"><span>Control system for a small fission <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Burelbach, J.P.; Kann, W.J.; Saiveau, J.G.</p> <p>1985-02-08</p> <p>A system for controlling the reactivity of a small fission <span class="hlt">reactor</span> includes an elongated, flexible hollow tube in the general form of a helical coiled spring axially positioned around and outside of the <span class="hlt">reactor</span> vessel in an annular space between the <span class="hlt">reactor</span> vessel and a surrounding cylindrical-shaped neutron reflector. A neutron absorbing material is provided within the hollow tube with the rate of the reaction controlled by the extension and compression of the hollow tube, e.g., extension of the tube increases reactivity while its compression reduces reactivity, in varying the amount of neutron absorbing material disposed between the <span class="hlt">reactor</span> vessel and the neutron reflector. Conventional mechanical displacement means may be employed to control the coil density of the hollow tube as desired.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19750027209&hterms=applications+thermodynamic&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D70%26Ntt%3Dapplications%2Bthermodynamic','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19750027209&hterms=applications+thermodynamic&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D70%26Ntt%3Dapplications%2Bthermodynamic"><span>Applications of plasma core <span class="hlt">reactors</span> to terrestrial energy systems</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Latham, T. S.; Biancardi, F. R.; Rodgers, R. J.</p> <p>1974-01-01</p> <p>Plasma core <span class="hlt">reactors</span> offer several new options for future energy needs in addition to space power and propulsion applications. Power extraction from plasma core <span class="hlt">reactors</span> with gaseous nuclear fuel allows operation at temperatures higher than conventional <span class="hlt">reactors</span>. Highly efficient thermodynamic cycles and applications employing direct coupling of radiant energy are possible. Conceptual configurations of plasma core <span class="hlt">reactors</span> for terrestrial applications are described. Closed-cycle gas turbines, MHD systems, photo- and thermo-chemical hydrogen production processes, and laser systems using plasma core <span class="hlt">reactors</span> as prime energy sources are considered. Cycle efficiencies in the range of 50 to 65 percent are calculated for closed-cycle gas turbine and MHD electrical generators. <span class="hlt">Reactor</span> advantages include continuous fuel reprocessing which limits inventory of radioactive by-products and thorium-U-233 breeder configurations with about 5-year doubling times.-</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/864663','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/864663"><span>Process and apparatus for adding and removing particles from pressurized <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Milligan, John D.</p> <p>1983-01-01</p> <p>A method for adding and removing fine particles from a pressurized <span class="hlt">reactor</span> is provided, which comprises connecting the <span class="hlt">reactor</span> to a container, sealing the container from the <span class="hlt">reactor</span>, filling the container with particles and a liquid material compatible with the reactants, pressurizing the container to substantially the <span class="hlt">reactor</span> pressure, removing the seal between the <span class="hlt">reactor</span> and the container, permitting particles to fall into or out of the <span class="hlt">reactor</span>, and resealing the container from the <span class="hlt">reactor</span>. An apparatus for adding and removing particles is also disclosed.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/5800430','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/5800430"><span>Oregon State University TRIGA <span class="hlt">Reactor</span> annual report</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Anderson, T.V.; Johnson, A.G.; Bennett, S.L.</p> <p>1979-08-31</p> <p>The use of the Oregon State University TRIGA <span class="hlt">Reactor</span> during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to <span class="hlt">reactor</span> operation and effluents are included.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/865825','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/865825"><span>Heat exchanger for <span class="hlt">reactor</span> core and the like</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Kaufman, Jay S.; Kissinger, John A.</p> <p>1986-01-01</p> <p>A compact bayonet tube type heat exchanger which finds particular application as an auxiliary heat exchanger for transfer of heat from a <span class="hlt">reactor</span> gas coolant to a secondary fluid medium. The heat exchanger is supported within a vertical cavity in a <span class="hlt">reactor</span> vessel intersected by a <span class="hlt">reactor</span> coolant passage at its upper end and having a <span class="hlt">reactor</span> coolant return duct spaced below the inlet passage. The heat exchanger includes a plurality of relatively short length bayonet type heat exchange tube assemblies adapted to pass a secondary fluid medium therethrough and supported by primary and secondary tube sheets which are releasibly supported in a manner to facilitate removal and inspection of the bayonet tube assemblies from an access area below the heat exchanger. Inner and outer shrouds extend circumferentially of the tube assemblies and cause the <span class="hlt">reactor</span> coolant to flow downwardly internally of the shrouds over the tube bundle and exit through the lower end of the inner shroud for passage to the return duct in the <span class="hlt">reactor</span> vessel.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/869060','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/869060"><span>Nuclear <span class="hlt">reactor</span> having a polyhedral primary shield and removable vessel insulation</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ekeroth, Douglas E.; Orr, Richard</p> <p>1993-01-01</p> <p>A nuclear <span class="hlt">reactor</span> is provided having a generally cylindrical <span class="hlt">reactor</span> vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The <span class="hlt">reactor</span> vessel is supported within the opening in the primary shield by <span class="hlt">reactor</span> vessel supports which are in communication and aligned with central portions of some of the side walls. The <span class="hlt">reactor</span> vessel is connected to the central portions of the <span class="hlt">reactor</span> vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the <span class="hlt">reactor</span> vessel and is disposed between the <span class="hlt">reactor</span> vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. <span class="hlt">Reactor</span> monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the <span class="hlt">reactor</span> vessel such that insulation is not disposed between the instrumentation and the <span class="hlt">reactor</span> vessel.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://hdl.handle.net/2060/20090023312','NASA-TRS'); return false;" href="http://hdl.handle.net/2060/20090023312"><span>NACA Zero Power <span class="hlt">Reactor</span> Facility Hazards Summary</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p></p> <p>1957-01-01</p> <p>The Lewis Flight Propulsion Laboratory of the National Advisory Committee for Aeronautics proposes to build a zero power research <span class="hlt">reactor</span> facility which will be located in the laboratory grounds near Clevelaurd, Ohio. The purpose of this report is to inform the Advisory Commit tee on <span class="hlt">Reactor</span> Safeguards of the U. S. Atomic Energy Commission in re gard to the design of the <span class="hlt">reactor</span> facility, the cha,acteristics of th e site, and the hazards of operation at this location, The purpose o f this <span class="hlt">reactor</span> is to perform critical experiments, to measure reactiv ity effects, to serve as a neutron source, and to serve as a training tool. The <span class="hlt">reactor</span> facility is described. This is followed by a discu ssion of the nuclear characteristics and the control system. Site cha racteristics are then discussed followed by a discussion of the exper iments which may be conducted in the facility. The potential hazards of the facility are then considered, particularly, the maximum credib le accident. Finally, the administrative procedure is discussed.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2014JPhCS.516a2024B','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2014JPhCS.516a2024B"><span>Investigation of materials for fusion power <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Bouhaddane, A.; Slugeň, V.; Sojak, S.; Veterníková, J.; Petriska, M.; Bartošová, I.</p> <p>2014-06-01</p> <p>The possibility of application of nuclear-physical methods to observe radiation damage to structural materials of nuclear facilities is nowadays a very actual topic. The radiation damage to materials of advanced nuclear facilities, caused by extreme radiation stress, is a process, which significantly limits their operational life as well as their safety. In the centre of our interest is the study of the radiation degradation and activation of the metals and alloys for the new nuclear facilities (Generation IV fission <span class="hlt">reactors</span>, fusion <span class="hlt">reactors</span> ITER and DEMO). The observation of the microstructure changes in the <span class="hlt">reactor</span> steels is based on experimental investigation using the method of positron annihilation spectroscopy (PAS). The experimental part of the work contains measurements focused on model <span class="hlt">reactor</span> alloys and ODS steels. There were 12 model <span class="hlt">reactor</span> steels and 3 ODS steels. We were investigating the influence of chemical composition on the production of defects in crystal lattice. With application of the LT 9 program, the spectra of specimen have been evaluated and the most convenient samples have been determined.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4296426','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4296426"><span>NEUTRONIC <span class="hlt">REACTORS</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Anderson, H.L.</p> <p>1958-10-01</p> <p>The design of control rods for nuclear <span class="hlt">reactors</span> are described. In this design the control rod consists essentially of an elongated member constructed in part of a neutron absorbing material and having tube means extending therethrough for conducting a liquid to cool the rod when in use.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1346009','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1346009"><span>Integral <span class="hlt">reactor</span> system and method for fuel cells</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Fernandes, Neil Edward; Brown, Michael S.; Cheekatamaria, Praveen; Deng, Thomas; Dimitrakopoulos, James; Litka, Anthony F.</p> <p>2017-03-07</p> <p>A <span class="hlt">reactor</span> system is integrated internally within an anode-side cavity of a fuel cell. The <span class="hlt">reactor</span> system is configured to convert higher hydrocarbons to smaller species while mitigating the lower production of solid carbon. The <span class="hlt">reactor</span> system may incorporate one or more of a pre-reforming section, an anode exhaust gas recirculation device, and a reforming section.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1108943','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1108943"><span>Integral <span class="hlt">reactor</span> system and method for fuel cells</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Fernandes, Neil Edward; Brown, Michael S; Cheekatamarla, Praveen; Deng, Thomas; Dimitrakopoulos, James; Litka, Anthony F</p> <p>2013-11-19</p> <p>A <span class="hlt">reactor</span> system is integrated internally within an anode-side cavity of a fuel cell. The <span class="hlt">reactor</span> system is configured to convert hydrocarbons to smaller species while mitigating the lower production of solid carbon. The <span class="hlt">reactor</span> system may incorporate one or more of a pre-reforming section, an anode exhaust gas recirculation device, and a reforming section.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.dtic.mil/docs/citations/ADA344764','DTIC-ST'); return false;" href="http://www.dtic.mil/docs/citations/ADA344764"><span>A Review of Gas-Cooled <span class="hlt">Reactor</span> Concepts for SDI Applications</span></a></p> <p><a target="_blank" href="http://www.dtic.mil/">DTIC Science & Technology</a></p> <p></p> <p>1989-08-01</p> <p>710 program .) Wire- Core <span class="hlt">Reactor</span> (proposed by Rockwell). The wire- core <span class="hlt">reactor</span> utilizes thin fuel wires woven between spacer wires to form an open...<span class="hlt">reactor</span> is based on results of developmental studies of nuclear rocket propulsion systems. The <span class="hlt">reactor</span> core is made up of annular fuel assemblies of...XE Addendum to Volume II. NERVA Fuel Development , Westinghouse Astronuclear Laboratory, TNR-230, July 15’ 1972. J I8- Rover Program <span class="hlt">Reactor</span> Tests</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/FR-2013-12-09/pdf/2013-29302.pdf','FEDREG'); return false;" href="https://www.gpo.gov/fdsys/pkg/FR-2013-12-09/pdf/2013-29302.pdf"><span>78 FR 73898 - Operator Licensing Examination Standards for Power <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collection.action?collectionCode=FR">Federal Register 2010, 2011, 2012, 2013, 2014</a></p> <p></p> <p>2013-12-09</p> <p>... <span class="hlt">Reactors</span> AGENCY: Nuclear Regulatory Commission. ACTION: Draft NUREG; request for comment. SUMMARY: The U.S..., Revision 10, ``Operator Licensing Examination Standards for Power <span class="hlt">Reactors</span>.'' DATES: Submit comments [email protected] . Both of the Office of New <span class="hlt">Reactors</span>; or Timothy Kolb, Office of Nuclear <span class="hlt">Reactor</span> Regulation, U...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1245417','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/1245417"><span>Pressurized water <span class="hlt">reactor</span> flow skirt apparatus</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Kielb, John F.; Schwirian, Richard E.; Lee, Naugab E.; Forsyth, David R.</p> <p>2016-04-05</p> <p>A pressurized water <span class="hlt">reactor</span> vessel having a flow skirt formed from a perforated cylinder structure supported in the lower <span class="hlt">reactor</span> vessel head at the outlet of the downcomer annulus, that channels the coolant flow through flow holes in the wall of the cylinder structure. The flow skirt is supported at a plurality of circumferentially spaced locations on the lower <span class="hlt">reactor</span> vessel head that are not equally spaced or vertically aligned with the core barrel attachment points, and the flow skirt employs a unique arrangement of hole patterns that assure a substantially balanced pressure and flow of the coolant over the entire underside of the lower core support plate.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4242625','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4242625"><span>PUSH-PULL POWER <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Froman, D.K.</p> <p>1959-02-24</p> <p>Power generating nuclear <span class="hlt">reactors</span> of the homogeneous liquid fuel type are discussed. The apparatus utilizes two identical <span class="hlt">reactors</span> interconnected by conduits through heat exchanging apparatus. Each <span class="hlt">reactor</span> contains a critical geometry region and a vapor region separated from the critical region by a baffle. When the liquid in the first critical region becomes critical, the vapor pressure above the fuel is increased due to the rise in the temperature until it forces the liquid fuel out of the first critical region through the heat exchanger and into the second critical region, which is at a lower temperature and consequently a lower vapor pressure. The above reaction is repeated in the second critical region and the liquid fuel is forced back into the first critical region. In this manner criticality is achieved alternately in each critical region and power is extracted by the heat exchanger from the liquid fuel passing therethrough. The vapor region and the heat exchanger have a non-critical geometry and reactivity control is effected by conventional control rods in the critical regions.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/22257861-improving-proliferation-resistance-high-breeding-gain-generation-reactors-using-blankets-composed-light-water-reactor-waste','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/22257861-improving-proliferation-resistance-high-breeding-gain-generation-reactors-using-blankets-composed-light-water-reactor-waste"><span>Improving proliferation resistance of high breeding gain generation 4 <span class="hlt">reactors</span> using blankets composed of light water <span class="hlt">reactor</span> waste</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Hellesen, C.; Grape, S.; Haakanson, A.</p> <p>2013-07-01</p> <p>Fertile blankets can be used in fast <span class="hlt">reactors</span> to enhance the breeding gain as well as the passive safety characteristics. However, such blankets typically result in the production of weapons grade plutonium. For this reason they are often excluded from Generation IV <span class="hlt">reactor</span> designs. In this paper we demonstrate that using blankets manufactured directly from spent light water (LWR) <span class="hlt">reactor</span> fuel it is possible to produce a plutonium product with non-proliferation characteristics on a par with spent LWR fuel of 30-50 MWd/kg burnup. The beneficial breeding and safety characteristics are retained. (authors)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2010PhDT........95A','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2010PhDT........95A"><span>Methods and strategies for future <span class="hlt">reactor</span> safety goals</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Arndt, Steven Andrew</p> <p></p> <p>There have been significant discussions over the past few years by the United States Nuclear Regulatory Commission (NRC), the Advisory Committee on <span class="hlt">Reactor</span> Safeguards (ACRS), and others as to the adequacy of the NRC safety goals for use with the next generation of nuclear power <span class="hlt">reactors</span> to be built in the United States. The NRC, in its safety goals policy statement, has provided general qualitative safety goals and basic quantitative health objectives (QHOs) for nuclear <span class="hlt">reactors</span> in the United States. Risk metrics such as core damage frequency (CDF) and large early release frequency (LERF) have been used as surrogates for the QHOs. In its review of the new plant licensing policy the ACRS has looked at the safety goals, as has the NRC. A number of issues have been raised including what the Commission had in mind when it drafted the safety goals and QHOs, how risk from multiple <span class="hlt">reactors</span> at a site should be combined for evaluation, how the combination of a new and old <span class="hlt">reactor</span> at the same site should be evaluated, what the criteria for evaluating new <span class="hlt">reactors</span> should be, and whether new <span class="hlt">reactors</span> should be required to be safer than current generation <span class="hlt">reactors</span>. As part of the development and application of the NRC safety goal policy statement the Commissioners laid out the expectations for the safety of a nuclear power plant but did not address the risk associated with current multi-unit sites, potential modular <span class="hlt">reactor</span> sites, and hybrid sites that could contain current generation <span class="hlt">reactors</span>, new passive <span class="hlt">reactors</span>, and/or modular <span class="hlt">reactors</span>. The NRC safety goals and the QHOs refer to a "nuclear power plant," but do not discuss whether a "plant" refers to only a single unit or all of the units on a site. There has been much discussion on this issue recently due to the development of modular <span class="hlt">reactors</span>. Additionally, the risk of multiple <span class="hlt">reactor</span> accidents on the same site has been largely ignored in the probabilistic risk assessments (PRAs) done to date, and in most risk</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/25176303','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/25176303"><span>Nitrate removal with lateral flow sulphur autotrophic denitrification <span class="hlt">reactor</span>.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Lv, Xiaomei; Shao, Mingfei; Li, Ji; Xie, Chuanbo</p> <p>2014-01-01</p> <p>An innovative lateral flow sulphur autotrophic denitrification (LFSAD) <span class="hlt">reactor</span> was developed in this study; the treatment performance was evaluated and compared with traditional sulphur/limestone autotrophic denitrification (SLAD) <span class="hlt">reactor</span>. Results showed that nitrite accumulation in the LFSAD <span class="hlt">reactor</span> was less than 1.0 mg/L during the whole operation. Denitrification rate increased with the increased initial alkalinity and was approaching saturation when initial alkalinity exceeded 2.5 times the theoretical value. Higher influent nitrate concentration could facilitate nitrate removal capacity. In addition, denitrification efficiency could be promoted under an appropriate reflux ratio, and the highest nitrate removal percentage was achieved under reflux ratio of 200%, increased by 23.8% than that without reflux. Running resistance was only about 1/9 of that in SLAD <span class="hlt">reactor</span> with equal amount of nitrate removed, which was the prominent excellence of the new <span class="hlt">reactor</span>. In short, this study indicated that the developed <span class="hlt">reactor</span> was feasible for nitrate removal from waters with lower concentrations, including contaminated surface water, groundwater or secondary effluent of municipal wastewater treatment with fairly low running resistance. The innovation in <span class="hlt">reactor</span> design in this study may bring forth new ideas of <span class="hlt">reactor</span> development of sulphur autotrophic denitrification for nitrate-contaminated water treatment.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4310609','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4310609"><span>STEAM STIRRED HOMOGENEOUS NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Busey, H.M.</p> <p>1958-06-01</p> <p>A homogeneous nuclear <span class="hlt">reactor</span> utilizing a selfcirculating liquid fuel is described. The <span class="hlt">reactor</span> vessel is in the form of a vertically disposed tubular member having the lower end closed by the tube walls and the upper end closed by a removal fianged assembly. A spherical reaction shell is located in the lower end of the vessel and spaced from the inside walls. The reaction shell is perforated on its lower surface and is provided with a bundle of small-diameter tubes extending vertically upward from its top central portion. The <span class="hlt">reactor</span> vessel is surrounded in the region of the reaction shell by a neutron reflector. The liquid fuel, which may be a solution of enriched uranyl sulfate in ordinary or heavy water, is mainiained at a level within the <span class="hlt">reactor</span> vessel of approximately the top of the tubes. The heat of the reaction which is created in the critical region within the spherical reaction shell forms steam bubbles which more upwardly through the tubes. The upward movement of these bubbles results in the forcing of the liquid fuel out of the top of these tubes, from where the fuel passes downwardly in the space between the tubes and the vessel wall where it is cooled by heat exchangers. The fuel then re-enters the critical region in the reaction shell through the perforations in the bottom. The upper portion of the <span class="hlt">reactor</span> vessel is provided with baffles to prevent the liquid fuel from splashing into this region which is also provided with a recombiner apparatus for recombining the radiolytically dissociated moderator vapor and a control means.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866161','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866161"><span>Fuel handling apparatus for a nuclear <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Hawke, Basil C.</p> <p>1987-01-01</p> <p>Fuel handling apparatus for transporting fuel elements into and out of a nuclear <span class="hlt">reactor</span> and transporting them within the <span class="hlt">reactor</span> vessel extends through a penetration in the side of the <span class="hlt">reactor</span> vessel. A lateral transport device carries the fuel elements laterally within the vessel and through the opening in the side of the vessel, and a reversible lifting device raises and lowers the fuel elements. In the preferred embodiment, the lifting device is supported by a pair of pivot arms.</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li class="active"><span>23</span></li> <li><a href="#" onclick='return showDiv("page_24");'>24</a></li> <li><a href="#" onclick='return showDiv("page_25");'>25</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_23 --> <div id="page_24" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li><a href="#" onclick='return showDiv("page_23");'>23</a></li> <li class="active"><span>24</span></li> <li><a href="#" onclick='return showDiv("page_25");'>25</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="461"> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/868879','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/868879"><span>Shielded fluid stream injector for particle bed <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Notestein, John E.</p> <p>1993-01-01</p> <p>A shielded fluid-stream injector assembly is provided for particle bed <span class="hlt">reactors</span>. The assembly includes a perforated pipe injector disposed across the particle bed region of the <span class="hlt">reactor</span> and an inverted V-shaped shield placed over the pipe, overlapping it to prevent descending particles from coming into direct contact with the pipe. The pipe and shield are fixedly secured at one end to the <span class="hlt">reactor</span> wall and slidably secured at the other end to compensate for thermal expansion. An axially extending housing aligned with the pipe and outside the <span class="hlt">reactor</span> and an in-line reamer are provided for removing deposits from the inside of the pipe. The assembly enables fluid streams to be injected and distributed uniformly into the particle bed with minimized clogging of injector ports. The same design may also be used for extraction of fluid streams from particle bed <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5792509-development-cascade-inertial-confinement-fusion-reactor','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/5792509-development-cascade-inertial-confinement-fusion-reactor"><span>Development of the cascade inertial-confinement-fusion <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Pitts, J.H.</p> <p></p> <p>Caqscade, originally conceived as a football-shaped, steel-walled <span class="hlt">reactor</span> containing a Li/sub 2/O granule blanket, is now envisaged as a double-cone-shaped <span class="hlt">reactor</span> containing a two-layered (three-zone) flowing blanket of BeO and LiAlO/sub 2/ granules. Average blanket exit temperature is 1670 K and gross plant efficiency (net thermal conversion efficiency) using a Brayton cycle is 55%. The <span class="hlt">reactor</span> has a low-activation SiC-tiled wall. It rotates at 50 rpm, and the granules are transported to the top of the heat exchanger using their peripheral speed; no conveyors or lifts are required. The granules return to the <span class="hlt">reactor</span> by gravity. After considerable analysis andmore » experimentation, we continue to regard Cascade as a promising <span class="hlt">reactor</span> concept with the advantages of safety, efficiency, and low activation.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/5857746','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/5857746"><span>Development of the cascade inertial-confinement-fusion <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Pitts, J.H.</p> <p></p> <p>Cascade, originally conceived as a football-shaped, steel-walled <span class="hlt">reactor</span> containing a Li/sub 2/O granule blanket, is now envisaged as a double-cone-shaped <span class="hlt">reactor</span> containing a two-layered (three-zone) flowing blanket of BeO and LiAlO/sub 2/ granules. Average blanket exit temperature is 1670/sup 0/K and gross plant efficiency (net thermal conversion efficiency) using a Brayton cycle is 55%. The <span class="hlt">reactor</span> has a low-activation SiC-tiled wall. It rotates at 50 rpm, and the granules are transported to the top of the heat exchanger using their peripheral speed; no conveyors or lifts are required. The granules return to the <span class="hlt">reactor</span> by gravity. After considerable analysis andmore » experimentation, we continue to regard Cascade as a promising <span class="hlt">reactor</span> concept with the advantages of safety, efficiency, and low activation.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/10158181','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/10158181"><span>Space <span class="hlt">reactor</span> fuel element testing in upgraded TREAT</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Todosow, M.; Bezler, P.; Ludewig, H.</p> <p>1993-01-14</p> <p>The testing of candidate fuel elements at prototypic operating conditions with respect to temperature, power density, hydrogen coolant flow rate, etc., a crucial component in the development and qualification of nuclear rocket engines based on the Particle Bed <span class="hlt">Reactor</span> (PBR), NERVA-derivative, and other concepts. Such testing may be performed at existing <span class="hlt">reactors</span>, or at new facilities. A scoping study has been performed to assess the feasibility of testing PBR based fuel elements at the TREAT <span class="hlt">reactor</span>. initial results suggest that full-scale PBR, elements could be tested at an average energy deposition of {approximately}60--80 MW-s/L in the current TREAT <span class="hlt">reactor</span>. Ifmore » the TREAT <span class="hlt">reactor</span> was upgraded to include fuel elements with a higher temperature limit, average energy deposition of {approximately}100 MW/L may be achievable.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/935270','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/935270"><span>Space <span class="hlt">reactor</span> fuel element testing in upgraded TREAT</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Todosow, M.; Bezler, P.; Ludewig, H.</p> <p>1993-05-01</p> <p>The testing of candidate fuel elements at prototypic operating conditions with respect to temperature, power density, hydrogen coolant flow rate, etc., a crucial component in the development and qualification of nuclear rocket engines based on the Particle Bed <span class="hlt">Reactor</span> (PBR), NERVA-derivative, and other concepts. Such testing may be performed at existing <span class="hlt">reactors</span>, or at new facilities. A scoping study has been performed to assess the feasibility of testing PBR based fuel elements at the TREAT <span class="hlt">reactor</span>. initial results suggest that full-scale PBR, elements could be tested at an average energy deposition of {approximately}60--80 MW-s/L in the current TREAT <span class="hlt">reactor</span>. Ifmore » the TREAT <span class="hlt">reactor</span> was upgraded to include fuel elements with a higher temperature limit, average energy deposition of {approximately}100 MW/L may be achievable.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/20358828','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/20358828"><span>[Rapid startup and nitrogen removal characteristic of anaerobic ammonium oxidation <span class="hlt">reactor</span> in packed bed biofilm <span class="hlt">reactor</span> with suspended carrier].</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Chen, Sheng; Sun, De-zhi; Yu, Guang-lu</p> <p>2010-03-01</p> <p>Packed bed biofilm <span class="hlt">reactor</span> with suspended carrier was used to cultivate ANAMMOX bacteria with sludge inoculums from WWTP secondary settler. The startup of ANAMMOX <span class="hlt">reactor</span> was comparatively studied using high nitrogen loading method and low nitrogen loading method with aerobically biofilmed on the carrier, and the nitrogen removal characteristic was further investigated. The results showed that the <span class="hlt">reactor</span> could be started up successfully within 90 days using low nitrogen loading method, the removal efficiencies of ammonium and nitrite were nearly 100% and the TN removal efficiencywas over 75% , however, the high nitrogen loading method was proved unsuccessfully for startup of ANAMMOX <span class="hlt">reactor</span> probably because of the inhibition effect of high concentration of ammonium and nitrite. The pH value of effluent was slightly higher than the influent and the pH value can be used as an indicator for the process of ANAMMOX reaction. The packed bed ANAMMOX <span class="hlt">reactor</span> with suspended carrier showed good characteristics of high nitrogen loading and high removal efficiency, 100% of removal efficiency could be achieved when the influent ammonium and nitrite concentration was lower than 800 mg/L.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1169446','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1169446"><span>Risk Management for Sodium Fast <span class="hlt">Reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Denman, Matthew R.; Groth, Katrina; Cardoni, Jeffrey N.</p> <p>2015-01-01</p> <p>Accident management is an important component to maintaining risk at acceptable levels for all complex systems, such as nuclear power plants. With the introduction of self - correcting, or inherently safe, <span class="hlt">reactor</span> designs the focus has shifted from management by operators to allowing the syste m's design to manage the accident. While inherently and passively safe designs are laudable, extreme boundary conditions can interfere with the design attributes which facilitate inherent safety , thus resulting in unanticipated and undesirable end states. This report examines an inherently safe and small sodium fast <span class="hlt">reactor</span> experiencing a beyond design basis seismic event withmore » the intend of exploring two issues : (1) can human intervention either improve or worsen the potential end states and (2) can a Bayes ian Network be constructed to infer the state of the <span class="hlt">reactor</span> to inform (1). ACKNOWLEDGEMENTS The author s would like to acknowledge the U.S. Department of E nergy's Office of Nuclear Energy for funding this research through Work Package SR - 14SN100303 under the Advanced <span class="hlt">Reactor</span> Concepts program. The authors also acknowledge the PRA teams at A rgonne N ational L aborator y , O ak R idge N ational L aborator y , and I daho N ational L aborator y for their continue d contributions to the advanced <span class="hlt">reactor</span> PRA mission area.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/FR-2010-11-16/pdf/2010-28846.pdf','FEDREG'); return false;" href="https://www.gpo.gov/fdsys/pkg/FR-2010-11-16/pdf/2010-28846.pdf"><span>75 FR 70042 - In the Matter of All Power <span class="hlt">Reactor</span> Licensees and Research <span class="hlt">Reactor</span> Licensees Who Transport Spent...</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collection.action?collectionCode=FR">Federal Register 2010, 2011, 2012, 2013, 2014</a></p> <p></p> <p>2010-11-16</p> <p>... NUCLEAR REGULATORY COMMISSION [Docket Nos (Redacted), License Nos (Redacted), EA (Redacted); NRC- 2010-0351] In the Matter of All Power <span class="hlt">Reactor</span> Licensees and Research <span class="hlt">Reactor</span> Licensees Who Transport Spent Nuclear Fuel; Order Modifying License (Effective Immediately) I. The licensees identified in...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/FR-2010-12-20/pdf/2010-31855.pdf','FEDREG'); return false;" href="https://www.gpo.gov/fdsys/pkg/FR-2010-12-20/pdf/2010-31855.pdf"><span>75 FR 79423 - In the Matter of All Power <span class="hlt">Reactor</span> Licensees and Research <span class="hlt">Reactor</span> Licensees Who Transport Spent...</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collection.action?collectionCode=FR">Federal Register 2010, 2011, 2012, 2013, 2014</a></p> <p></p> <p>2010-12-20</p> <p>... NUCLEAR REGULATORY COMMISSION [Docket Nos. (Redacted), License Nos.: (Redacted), EA (Redacted); NRC- 2010-0351] In the Matter of All Power <span class="hlt">Reactor</span> Licensees and Research <span class="hlt">Reactor</span> Licensees Who Transport Spent Nuclear Fuel; Order Modifying License (Effective Immediately) I The licensees identified in...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.pubmedcentral.nih.gov/articlerender.fcgi?tool=pmcentrez&artid=1236956','PMC'); return false;" href="https://www.pubmedcentral.nih.gov/articlerender.fcgi?tool=pmcentrez&artid=1236956"><span>Biofilm <span class="hlt">reactors</span> for industrial bioconversion processes: employing potential of enhanced reaction rates</span></a></p> <p><a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pmc">PubMed Central</a></p> <p>Qureshi, Nasib; Annous, Bassam A; Ezeji, Thaddeus C; Karcher, Patrick; Maddox, Ian S</p> <p>2005-01-01</p> <p>This article describes the use of biofilm <span class="hlt">reactors</span> for the production of various chemicals by fermentation and wastewater treatment. Biofilm formation is a natural process where microbial cells attach to the support (adsorbent) or form flocs/aggregates (also called granules) without use of chemicals and form thick layers of cells known as "biofilms." As a result of biofilm formation, cell densities in the <span class="hlt">reactor</span> increase and cell concentrations as high as 74 gL-1 can be achieved. The <span class="hlt">reactor</span> configurations can be as simple as a batch <span class="hlt">reactor</span>, continuous stirred tank <span class="hlt">reactor</span> (CSTR), packed bed <span class="hlt">reactor</span> (PBR), fluidized bed <span class="hlt">reactor</span> (FBR), airlift <span class="hlt">reactor</span> (ALR), upflow anaerobic sludge blanket (UASB) <span class="hlt">reactor</span>, or any other suitable configuration. In UASB granular biofilm particles are used. This article demonstrates that <span class="hlt">reactor</span> productivities in these <span class="hlt">reactors</span> have been superior to any other <span class="hlt">reactor</span> types. This article describes production of ethanol, butanol, lactic acid, acetic acid/vinegar, succinic acid, and fumaric acid in addition to wastewater treatment in the biofilm <span class="hlt">reactors</span>. As the title suggests, biofilm <span class="hlt">reactors</span> have high potential to be employed in biotechnology/bioconversion industry for viable economic reasons. In this article, various <span class="hlt">reactor</span> types have been compared for the above bioconversion processes. PMID:16122390</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2014EPJWC..6702133Z','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2014EPJWC..6702133Z"><span>Solution of heat removal from nuclear <span class="hlt">reactors</span> by natural convection</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Zitek, Pavel; Valenta, Vaclav</p> <p>2014-03-01</p> <p>This paper summarizes the basis for the solution of heat removal by natural convection from both conventional nuclear <span class="hlt">reactors</span> and <span class="hlt">reactors</span> with fuel flowing coolant (such as <span class="hlt">reactors</span> with molten fluoride salts MSR).The possibility of intensification of heat removal through gas lift is focused on. It might be used in an MSR (Molten Salt <span class="hlt">Reactor</span>) for cleaning the salt mixture of degassed fission products and therefore eliminating problems with iodine pitting. Heat removal by natural convection and its intensification increases significantly the safety of nuclear <span class="hlt">reactors</span>. Simultaneously the heat removal also solves problems with lifetime of pumps in the primary circuit of high-temperature <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2016PPN....47.1014S','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2016PPN....47.1014S"><span>Experiment for search for sterile neutrino at SM-3 <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Serebrov, A. P.; Ivochkin, V. G.; Samoylov, R. M.; Fomin, A. K.; Zinoviev, V. G.; Neustroev, P. V.; Golovtsov, V. L.; Gruzinsky, N. V.; Solovey, V. A.; Cherniy, A. V.; Zherebtsov, O. M.; Martemyanov, V. P.; Zinoev, V. G.; Tarasenkov, V. G.; Aleshin, V. I.; Petelin, A. L.; Pavlov, S. V.; Izhutov, A. L.; Sazontov, S. A.; Ryazanov, D. K.; Gromov, M. O.; Afanasiev, V. V.; Matrosov, L. N.; Matrosova, M. Yu.</p> <p>2016-11-01</p> <p>In connection with the question of possible existence of sterile neutrino the laboratory on the basis of SM-3 <span class="hlt">reactor</span> was created to search for oscillations of <span class="hlt">reactor</span> antineutrino. A prototype of a neutrino detector with scintillator volume of 400 l can be moved at the distance of 6-11 m from the <span class="hlt">reactor</span> core. The measurements of background conditions have been made. It is shown that the main experimental problem is associated with cosmic radiation background. Test measurements of dependence of a <span class="hlt">reactor</span> antineutrino flux on the distance from a <span class="hlt">reactor</span> core have been made. The prospects of search for oscillations of <span class="hlt">reactor</span> antineutrino at short distances are discussed.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/1998RScI...69.1850W','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/1998RScI...69.1850W"><span>Design of a laboratory scale fluidized bed <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Wikström, E.; Andersson, P.; Marklund, S.</p> <p>1998-04-01</p> <p>The aim of this project was to construct a laboratory scale fluidized bed <span class="hlt">reactor</span> that simulates the behavior of full scale municipal solid waste combustors. The design of this <span class="hlt">reactor</span> is thoroughly described. The size of the laboratory scale fluidized bed <span class="hlt">reactor</span> is 5 kW, which corresponds to a fuel-feeding rate of approximately 1 kg/h. The <span class="hlt">reactor</span> system consists of four parts: a bed section, a freeboard section, a convector (postcombustion zone), and an air pollution control (APC) device system. The inside diameter of the <span class="hlt">reactor</span> is 100 mm at the bed section and it widens to 200 mm in diameter in the freeboard section; the total height of the <span class="hlt">reactor</span> is 1760 mm. The convector part consists of five identical sections; each section is 2700 mm long and has an inside diameter of 44.3 mm. The <span class="hlt">reactor</span> is flexible regarding the placement and number of sampling ports. At the beginning of the first convector unit and at the end of each unit there are sampling ports for organic micropollutants (OMP). This makes it possible to study the composition of the flue gases at various residence times. Sampling ports for inorganic compounds and particulate matter are also placed in the convector section. All operating parameters, <span class="hlt">reactor</span> temperatures, concentrations of CO, CO2, O2, SO2, NO, and NO2 are continuously measured and stored at selected intervals for further evaluation. These unique features enable full control over the fuel feed, air flows, and air distribution as well as over the temperature profile. Elaborate details are provided regarding the configuration of the fuel-feeding systems, the fluidized bed, the convector section, and the APC device. This laboratory <span class="hlt">reactor</span> enables detailed studies of the formation mechanisms of OMP, such as polychlorinated dibenzo-p-dioxins (PCDDs), polychlorinated dibenzofurans (PCDFs), poly-chlorinated biphenyls (PCBs), and polychlorinated benzenes (PCBzs). With this system formation mechanisms of OMP occurring in both the combustion</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/5447306','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/5447306"><span>Nuclear <span class="hlt">reactor</span> having a polyhedral primary shield and removable vessel insulation</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Ekeroth, D.E.; Orr, R.</p> <p>1993-12-07</p> <p>A nuclear <span class="hlt">reactor</span> is provided having a generally cylindrical <span class="hlt">reactor</span> vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The <span class="hlt">reactor</span> vessel is supported within the opening in the primary shield by <span class="hlt">reactor</span> vessel supports which are in communication and aligned with central portions of some of the side walls. The <span class="hlt">reactor</span> vessel is connected to the central portions of the <span class="hlt">reactor</span> vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the <span class="hlt">reactor</span> vessel and is disposed between the <span class="hlt">reactor</span> vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. <span class="hlt">Reactor</span> monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the <span class="hlt">reactor</span> vessel such that insulation is not disposed between the instrumentation and the <span class="hlt">reactor</span> vessel. 5 figures.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://www.osti.gov/accomplishments/documents/fullText/ACC0531.pdf','DOE-RDACC'); return false;" href="http://www.osti.gov/accomplishments/documents/fullText/ACC0531.pdf"><span>Five Lectures on Nuclear <span class="hlt">Reactors</span> Presented at Cal Tech</span></a></p> <p><a target="_blank" href="http://www.osti.gov/accomplishments/fieldedsearch.html">DOE R&D Accomplishments Database</a></p> <p>Weinberg, Alvin M.</p> <p>1956-02-10</p> <p>The basic issues involved in the physics and engineering of nuclear <span class="hlt">reactors</span> are summarized. Topics discussed include theory of <span class="hlt">reactor</span> design, technical problems in power <span class="hlt">reactors</span>, physical problems in nuclear power production, and future developments in nuclear power. (C.H.)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4138446','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4138446"><span>MOLTEN FLUORIDE NUCLEAR <span class="hlt">REACTOR</span> FUEL</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Barton, C.J.; Grimes, W.R.</p> <p>1960-01-01</p> <p>Molten-salt <span class="hlt">reactor</span> fuel compositions consisting of mixtures of fluoride salts are reported. In its broadest form, the composition contains an alkali fluoride such as sodium fluoride, zirconium tetrafluoride, and a uranium fluoride, the latter being the tetrafluoride or trifluoride or a mixture of the two. An outstanding property of these fuel compositions is a high coeffieient of thermal expansion which provides a negative temperature coefficient of reactivity in <span class="hlt">reactors</span> in which they are used.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/10108743-combined-hybrid-system-symbiotic-thermal-reactor-fast-reactor-system-power-generation-radioactive-waste-toxicity-reduction','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/10108743-combined-hybrid-system-symbiotic-thermal-reactor-fast-reactor-system-power-generation-radioactive-waste-toxicity-reduction"><span>The combined hybrid system: A symbiotic thermal <span class="hlt">reactor</span>/fast <span class="hlt">reactor</span> system for power generation and radioactive waste toxicity reduction</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Hollaway, W.R.</p> <p>1991-08-01</p> <p>If there is to be a next generation of nuclear power in the United States, then the four fundamental obstacles confronting nuclear power technology must be overcome: safety, cost, waste management, and proliferation resistance. The Combined Hybrid System (CHS) is proposed as a possible solution to the problems preventing a vigorous resurgence of nuclear power. The CHS combines Thermal <span class="hlt">Reactors</span> (for operability, safety, and cost) and Integral Fast <span class="hlt">Reactors</span> (for waste treatment and actinide burning) in a symbiotic large scale system. The CHS addresses the safety and cost issues through the use of advanced <span class="hlt">reactor</span> designs, the waste management issuemore » through the use of actinide burning, and the proliferation resistance issue through the use of an integral fuel cycle with co-located components. There are nine major components in the Combined Hybrid System linked by nineteen nuclear material mass flow streams. A computer code, CHASM, is used to analyze the mass flow rates CHS, and the <span class="hlt">reactor</span> support ratio (the ratio of thermal/fast <span class="hlt">reactors</span>), IFR of the system. The primary advantages of the CHS are its essentially actinide-free high-level radioactive waste, plus improved <span class="hlt">reactor</span> safety, uranium utilization, and widening of the option base. The primary disadvantages of the CHS are the large capacity of IFRs required (approximately one MW{sub e} IFR capacity for every three MW{sub e} Thermal <span class="hlt">Reactor</span>) and the novel radioactive waste streams produced by the CHS. The capability of the IFR to burn pure transuranic fuel, a primary assumption of this study, has yet to be proven. The Combined Hybrid System represents an attractive option for future nuclear power development; that disposal of the essentially actinide-free radioactive waste produced by the CHS provides an excellent alternative to the disposal of intact actinide-bearing Light Water <span class="hlt">Reactor</span> spent fuel (reducing the toxicity based lifetime of the waste from roughly 360,000 years to about 510 years).« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2004PhDT........79P','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2004PhDT........79P"><span>Isotopic composition and neutronics of the Okelobondo natural <span class="hlt">reactor</span></span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Palenik, Christopher Samuel</p> <p></p> <p>The Oklo-Okelobondo and Bangombe uranium deposits, in Gabon, Africa host Earth's only known natural nuclear fission <span class="hlt">reactors</span>. These 2 billion year old <span class="hlt">reactors</span> represent a unique opportunity to study used nuclear fuel over geologic periods of time. The <span class="hlt">reactors</span> in these deposits have been studied as a means by which to constrain the source term of fission product concentrations produced during <span class="hlt">reactor</span> operation. The source term depends on the neutronic parameters, which include <span class="hlt">reactor</span> operation duration, neutron flux and the neutron energy spectrum. <span class="hlt">Reactor</span> operation has been modeled using a point-source computer simulation (Oak Ridge Isotope Generation and Depletion, ORIGEN, code) for a light water <span class="hlt">reactor</span>. Model results have been constrained using secondary ionization mass spectroscopy (SIMS) isotopic measurements of the fission products Nd and Te, as well as U in uraninite from samples collected in the Okelobondo <span class="hlt">reactor</span> zone. Based upon the constraints on the operating conditions, the pre-<span class="hlt">reactor</span> concentrations of Nd (150 ppm +/- 75 ppm) and Te (<1 ppm) in uraninite were estimated. Related to the burnup measured in Okelobondo samples (0.7 to 13.8 GWd/MTU), the final fission product inventories of Nd (90 to 1200 ppm) and Te (10 to 110 ppm) were calculated. By the same means, the ranges of all other fission products and actinides produced during <span class="hlt">reactor</span> operation were calculated as a function of burnup. These results provide a source term against which the present elemental and decay abundances at the fission <span class="hlt">reactor</span> can be compared. Furthermore, they provide new insights into the extent to which a "fossil" nuclear <span class="hlt">reactor</span> can be characterized on the basis of its isotopic signatures. In addition, results from the study of two other natural systems related to the radionuclide and fission product transport are included. A detailed mineralogical characterization of the uranyl mineralogy at the Bangombe uranium deposit in Gabon, Africa was completed to improve</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.ncbi.nlm.nih.gov/pubmed/17764354','PUBMED'); return false;" href="https://www.ncbi.nlm.nih.gov/pubmed/17764354"><span>Moving bed <span class="hlt">reactor</span> setup to study complex gas-solid reactions.</span></a></p> <p><a target="_blank" href="https://www.ncbi.nlm.nih.gov/entrez/query.fcgi?DB=pubmed">PubMed</a></p> <p>Gupta, Puneet; Velazquez-Vargas, Luis G; Valentine, Charles; Fan, Liang-Shih</p> <p>2007-08-01</p> <p>A moving bed scale <span class="hlt">reactor</span> setup for studying complex gas-solid reactions has been designed in order to obtain kinetic data for scale-up purpose. In this bench scale <span class="hlt">reactor</span> setup, gas and solid reactants can be contacted in a cocurrent and countercurrent manner at high temperatures. Gas and solid sampling can be performed through the <span class="hlt">reactor</span> bed with their composition profiles determined at steady state. The <span class="hlt">reactor</span> setup can be used to evaluate and corroborate model parameters accounting for intrinsic reaction rates in both simple and complex gas-solid reaction systems. The moving bed design allows experimentation over a variety of gas and solid compositions in a single experiment unlike differential bed <span class="hlt">reactors</span> where the gas composition is usually fixed. The data obtained from the <span class="hlt">reactor</span> can also be used for direct scale-up of designs for moving bed <span class="hlt">reactors</span>.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/21367123-angra-project-monitoring-nuclear-reactors-antineutrino-detectors','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/21367123-angra-project-monitoring-nuclear-reactors-antineutrino-detectors"><span>The Angra Project: Monitoring Nuclear <span class="hlt">Reactors</span> with Antineutrino Detectors</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Anjos, J. C.; Barbosa, A. F.; Lima, H. P. Jr.</p> <p>2010-03-30</p> <p>We present the status of the Angra Neutrino project, describing the development of an antineutrino detector aimed at monitoring nuclear <span class="hlt">reactor</span> activity. The experiment will take place at the Brazilian nuclear power plant located in Angra dos Reis. The Angra II <span class="hlt">reactor</span>, with 4 GW of thermal power, will be used as a source of antineutrinos. A water Cherenkov detector will be placed above ground in a commercial container outside the <span class="hlt">reactor</span> containment, about 30 m from the <span class="hlt">reactor</span> core. With a detector of one ton scale a few thousand antineutrino interactions per day are expected. We intend, in amore » first step, to use the measured neutrino event rate to monitor the on--off status and the thermal power delivered by the <span class="hlt">reactor</span>. In addition to the safeguards issues the project will provide an alternative tool to have an independent measurement of the <span class="hlt">reactor</span> power.« less</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li><a href="#" onclick='return showDiv("page_23");'>23</a></li> <li class="active"><span>24</span></li> <li><a href="#" onclick='return showDiv("page_25");'>25</a></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_24 --> <div id="page_25" class="hiddenDiv"> <div class="row"> <div class="col-sm-12"> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li><a href="#" onclick='return showDiv("page_23");'>23</a></li> <li><a href="#" onclick='return showDiv("page_24");'>24</a></li> <li class="active"><span>25</span></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div> </div> <div class="row"> <div class="col-sm-12"> <ol class="result-class" start="481"> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2010AIPC.1222..427A','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2010AIPC.1222..427A"><span>The Angra Project: Monitoring Nuclear <span class="hlt">Reactors</span> with Antineutrino Detectors</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Anjos, J. C.; Barbosa, A. F.; Bezerra, T. J. C.; Chimenti, P.; Gonzalez, L. F. G.; Kemp, E.; de Oliveira, M. A. Leigui; Lima, H. P.; Lima, R. M.; Nunokawa, H.</p> <p>2010-03-01</p> <p>We present the status of the Angra Neutrino project, describing the development of an antineutrino detector aimed at monitoring nuclear <span class="hlt">reactor</span> activity. The experiment will take place at the Brazilian nuclear power plant located in Angra dos Reis. The Angra II <span class="hlt">reactor</span>, with 4 GW of thermal power, will be used as a source of antineutrinos. A water Cherenkov detector will be placed above ground in a commercial container outside the <span class="hlt">reactor</span> containment, about 30 m from the <span class="hlt">reactor</span> core. With a detector of one ton scale a few thousand antineutrino interactions per day are expected. We intend, in a first step, to use the measured neutrino event rate to monitor the on—off status and the thermal power delivered by the <span class="hlt">reactor</span>. In addition to the safeguards issues the project will provide an alternative tool to have an independent measurement of the <span class="hlt">reactor</span> power.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/1433345','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/1433345"><span>Advanced Instrumentation for Transient <span class="hlt">Reactor</span> Testing</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Corradini, Michael L.; Anderson, Mark; Imel, George</p> <p></p> <p>Transient testing involves placing fuel or material into the core of specialized materials test <span class="hlt">reactors</span> that are capable of simulating a range of design basis accidents, including reactivity insertion accidents, that require the <span class="hlt">reactor</span> produce short bursts of intense highpower neutron flux and gamma radiation. Testing fuel behavior in a prototypic neutron environment under high-power, accident-simulation conditions is a key step in licensing nuclear fuels for use in existing and future nuclear power plants. Transient testing of nuclear fuels is needed to develop and prove the safety basis for advanced <span class="hlt">reactors</span> and fuels. In addition, modern fuel development and designmore » increasingly relies on modeling and simulation efforts that must be informed and validated using specially designed material performance separate effects studies. These studies will require experimental facilities that are able to support variable scale, highly instrumented tests providing data that have appropriate spatial and temporal resolution. Finally, there are efforts now underway to develop advanced light water <span class="hlt">reactor</span> (LWR) fuels with enhanced performance and accident tolerance. These advanced <span class="hlt">reactor</span> designs will also require new fuel types. These new fuels need to be tested in a controlled environment in order to learn how they respond to accident conditions. For these applications, transient <span class="hlt">reactor</span> testing is needed to help design fuels with improved performance. In order to maximize the value of transient testing, there is a need for in-situ transient realtime imaging technology (e.g., the neutron detection and imaging system like the hodoscope) to see fuel motion during rapid transient excursions with a higher degree of spatial and temporal resolution and accuracy. There also exists a need for new small, compact local sensors and instrumentation that are capable of collecting data during transients (e.g., local displacements, temperatures, thermal conductivity, neutron flux</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/10124502','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/10124502"><span>The Experimental Breeder <span class="hlt">Reactor</span> II seismic probabilistic risk assessment</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Roglans, J; Hill, D J</p> <p>1994-02-01</p> <p>The Experimental Breeder <span class="hlt">Reactor</span> II (EBR-II) is a US Department of Energy (DOE) Category A research <span class="hlt">reactor</span> located at Argonne National Laboratory (ANL)-West in Idaho. EBR-II is a 62.5 MW-thermal Liquid Metal <span class="hlt">Reactor</span> (LMR) that started operation in 1964 and it is currently being used as a testbed in the Integral Fast <span class="hlt">Reactor</span> (IFR) Program. ANL has completed a Level 1 Probabilistic Risk Assessment (PRA) for EBR-II. The Level 1 PRA for internal events and most external events was completed in June 1991. The seismic PRA for EBR-H has recently been completed. The EBR-II <span class="hlt">reactor</span> building contains the <span class="hlt">reactor</span>, themore » primary system, and the decay heat removal systems. The <span class="hlt">reactor</span> vessel, which contains the core, and the primary system, consisting of two primary pumps and an intermediate heat exchanger, are immersed in the sodium-filled primary tank, which is suspended by six hangers from a beam support structure. Three systems or functions in EBR-II were identified as the most significant from the standpoint of risk of seismic-induced fuel damage: (1) the <span class="hlt">reactor</span> shutdown system, (2) the structural integrity of the passive decay heat removal systems, and (3) the integrity of major structures, like the primary tank containing the <span class="hlt">reactor</span> that could threaten both the reactivity control and decay heat removal functions. As part of the seismic PRA, efforts were concentrated in studying these three functions or systems. The passive safety response of EBR-II <span class="hlt">reactor</span> -- both passive reactivity shutdown and passive decay heat removal, demonstrated in a series of tests in 1986 -- was explicitly accounted for in the seismic PRA as it had been included in the internal events assessment.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4261845','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4261845"><span>SELF-REACTIVATING NEUTRON SOURCE FOR A NEUTRONIC <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Newson, H.W.</p> <p>1959-02-01</p> <p><span class="hlt">Reactors</span> of the type employing beryllium in a reflector region around the active portion and to a neutron source for use therewith are discussed. The neutron source is comprised or a quantity of antimony permanently incorporated in, and as an integral part of, the <span class="hlt">reactor</span> in or near the beryllium reflector region. During operation of the <span class="hlt">reactor</span> the natural occurring antimony isotope of atomic weight 123 absorbs neutrons and is thereby transformed to the antimony isotope of atomic weight 124, which is radioactive and emits gamma rays. The gamma rays react with the beryllium to produce neutrons. The beryllium and antimony thus cooperate to produce a built in neutron source which is automatically reactivated by the operation of the <span class="hlt">reactor</span> itself and which is of sufficient strength to maintain the slow neutron flux at a sufficiently high level to be reliably measured during periods when the <span class="hlt">reactor</span> is shut down.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2006AIPC..830..359N','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2006AIPC..830..359N"><span>A Compact Nuclear Fusion <span class="hlt">Reactor</span> for Space Flights</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Nastoyashchiy, Anatoly F.</p> <p>2006-05-01</p> <p>A small-scale nuclear fusion <span class="hlt">reactor</span> is suggested based on the concepts of plasma confinement (with a high pressure gas) which have been patented by the author. The <span class="hlt">reactor</span> considered can be used as a power setup in space flights. Among the advantages of this <span class="hlt">reactor</span> is the use of a D3He fuel mixture which at burning gives main <span class="hlt">reactor</span> products — charged particles. The energy balance considerably improves, as synchrotron radiation turn out "captured" in the plasma volume, and dangerous, in the case of classical magnetic confinement, instabilities in the direct current magnetic field configuration proposed do not exist. As a result, the <span class="hlt">reactor</span> sizes are quite suitable (of the order of several meters). A possibility of making reactive thrust due to employment of ejection of multiply charged ions formed at injection of pellets from some adequate substance into the hot plasma center is considered.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/565153','SCIGOV-STC'); return false;" href="https://www.osti.gov/servlets/purl/565153"><span>Nuclear <span class="hlt">reactors</span> built, being built, or planned 1996</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>NONE</p> <p>1997-08-01</p> <p>This publication contains unclassified information about facilities, built, being built, or planned in the United States for domestic use or export as of December 31, 1996. The Office of Scientific and Technical Information, U.S. Department of Energy, gathers this information annually from Washington headquarters, and field offices of DOE; from the U.S. Nuclear Regulatory Commission (NRC); from the U. S. <span class="hlt">reactor</span> manufacturers who are the principal nuclear contractors for foreign <span class="hlt">reactor</span> locations; from U.S. and foreign embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: (1) a commercial <span class="hlt">reactor</span> locator map and tables ofmore » the characteristic and statistical data that follow; a table of abbreviations; (2) tables of data for <span class="hlt">reactors</span> operating, being built, or planned; and (3) tables of data for <span class="hlt">reactors</span> that have been shut down permanently or dismantled.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2-sec140-11.pdf','CFR2014'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2-sec140-11.pdf"><span>10 CFR 140.11 - Amounts of financial protection for certain <span class="hlt">reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2014&page.go=Go">Code of Federal Regulations, 2014 CFR</a></p> <p></p> <p>2014-01-01</p> <p>...,000,000 for each nuclear <span class="hlt">reactor</span> he is authorized to operate at a thermal power level not exceeding ten kilowatts; (2) In the amount of $1,500,000 for each nuclear <span class="hlt">reactor</span> he is authorized to operate at... amount of $2,500,000 for each nuclear <span class="hlt">reactor</span> other than a testing <span class="hlt">reactor</span> or a <span class="hlt">reactor</span> licensed under...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2012-title10-vol2/pdf/CFR-2012-title10-vol2-sec140-11.pdf','CFR2012'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2012-title10-vol2/pdf/CFR-2012-title10-vol2-sec140-11.pdf"><span>10 CFR 140.11 - Amounts of financial protection for certain <span class="hlt">reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2012&page.go=Go">Code of Federal Regulations, 2012 CFR</a></p> <p></p> <p>2012-01-01</p> <p>...,000,000 for each nuclear <span class="hlt">reactor</span> he is authorized to operate at a thermal power level not exceeding ten kilowatts; (2) In the amount of $1,500,000 for each nuclear <span class="hlt">reactor</span> he is authorized to operate at... amount of $2,500,000 for each nuclear <span class="hlt">reactor</span> other than a testing <span class="hlt">reactor</span> or a <span class="hlt">reactor</span> licensed under...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/CFR-2013-title10-vol2/pdf/CFR-2013-title10-vol2-sec140-11.pdf','CFR2013'); return false;" href="https://www.gpo.gov/fdsys/pkg/CFR-2013-title10-vol2/pdf/CFR-2013-title10-vol2-sec140-11.pdf"><span>10 CFR 140.11 - Amounts of financial protection for certain <span class="hlt">reactors</span>.</span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collectionCfr.action?selectedYearFrom=2013&page.go=Go">Code of Federal Regulations, 2013 CFR</a></p> <p></p> <p>2013-01-01</p> <p>...,000,000 for each nuclear <span class="hlt">reactor</span> he is authorized to operate at a thermal power level not exceeding ten kilowatts; (2) In the amount of $1,500,000 for each nuclear <span class="hlt">reactor</span> he is authorized to operate at... amount of $2,500,000 for each nuclear <span class="hlt">reactor</span> other than a testing <span class="hlt">reactor</span> or a <span class="hlt">reactor</span> licensed under...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/servlets/purl/866549','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/servlets/purl/866549"><span>Nuclear <span class="hlt">reactor</span> shutdown control rod assembly</span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Bilibin, Konstantin</p> <p>1988-01-01</p> <p>A temperature responsive, self-actuated nuclear <span class="hlt">reactor</span> shutdown control rod assembly 10. The upper end 18 of a lower drive line 17 fits within the lower end of an upper drive line 12. The lower end (not shown) of the lower drive line 17 is connected to a neutron absorber. During normal temperature conditions the lower drive line 17 is supported by detent means 22,26. When an overtemperature condition occurs thermal actuation means 34 urges ring 26 upwardly sufficiently to allow balls 22 to move radially outwardly thereby allowing lower drive line 17 to move downwardly toward the core of the nuclear <span class="hlt">reactor</span> resulting in automatic reduction of the <span class="hlt">reactor</span> powder.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('http://adsabs.harvard.edu/abs/2017JPhCS.781a2007S','NASAADS'); return false;" href="http://adsabs.harvard.edu/abs/2017JPhCS.781a2007S"><span>Low-power lead-cooled fast <span class="hlt">reactor</span> loaded with MOX-fuel</span></a></p> <p><a target="_blank" href="http://adsabs.harvard.edu/abstract_service.html">NASA Astrophysics Data System (ADS)</a></p> <p>Sitdikov, E. R.; Terekhova, A. M.</p> <p>2017-01-01</p> <p>Fast <span class="hlt">reactor</span> for the purpose of implementation of research, education of undergraduate and doctoral students in handling innovative fast <span class="hlt">reactors</span> and training specialists for atomic research centers and nuclear power plants (BRUTs) was considered. Hard neutron spectrum achieved in the fast <span class="hlt">reactor</span> with compact core and lead coolant. Possibility of prompt neutron runaway of the <span class="hlt">reactor</span> is excluded due to the low reactivity margin which is less than the effective fraction of delayed neutrons. The possibility of using MOX fuel in the BRUTs <span class="hlt">reactor</span> was examined. The effect of Keff growth connected with replacement of natural lead coolant to 208Pb coolant was evaluated. The calculations and <span class="hlt">reactor</span> core model were performed using the Serpent Monte Carlo code.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.gpo.gov/fdsys/pkg/FR-2013-09-24/pdf/2013-23228.pdf','FEDREG'); return false;" href="https://www.gpo.gov/fdsys/pkg/FR-2013-09-24/pdf/2013-23228.pdf"><span>78 FR 58575 - Review of Experiments for Research <span class="hlt">Reactors</span></span></a></p> <p><a target="_blank" href="http://www.gpo.gov/fdsys/browse/collection.action?collectionCode=FR">Federal Register 2010, 2011, 2012, 2013, 2014</a></p> <p></p> <p>2013-09-24</p> <p>... NUCLEAR REGULATORY COMMISSION [NRC-2013-0219] Review of Experiments for Research <span class="hlt">Reactors</span> AGENCY... Commission (NRC) is withdrawing Regulatory Guide (RG) 2.4, ``Review of Experiments for Research <span class="hlt">Reactors</span>... withdrawing RG 2.4, ``Review of Experiments for Research <span class="hlt">Reactors</span>,'' (ADAMS Accession No. ML003740131) because...</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/1177616-reactor-physics-scoping-characterization-study-implementation-triga-fuel-advanced-test-reactor','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/1177616-reactor-physics-scoping-characterization-study-implementation-triga-fuel-advanced-test-reactor"><span><span class="hlt">Reactor</span> Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test <span class="hlt">Reactor</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Jennifer Lyons; Wade R. Marcum; Mark D. DeHart</p> <p>2014-01-01</p> <p>The Advanced Test <span class="hlt">Reactor</span> (ATR), under the Reduced Enrichment for Research and Test <span class="hlt">Reactors</span> (RERTR) Program and the Global Threat Reduction Initiative (GTRI), is conducting feasibility studies for the conversion of its fuel from a highly enriched uranium (HEU) composition to a low enriched uranium (LEU) composition. These studies have considered a wide variety of LEU plate-type fuels to replace the current HEU fuel. Continuing to investigate potential alternatives to the present HEU fuel form, this study presents a preliminary analysis of TRIGA® fuel within the current ATR fuel envelopes and compares it to the functional requirements delineated by themore » Naval <span class="hlt">Reactors</span> Program, which includes: greater than 4.8E+14 fissions/s/g of 235U, a fast to thermal neutron flux ratio that is less than 5% deviation of its current value, a constant cycle power within the corner lobes, and an operational cycle length of 56 days at 120 MW. Other parameters outside those put forth by the Naval <span class="hlt">Reactors</span> Program which are investigated herein include axial and radial power profiles, effective delayed neutron fraction, and mean neutron generation time.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6687838-significance-breeding-fast-nuclear-reactors','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/6687838-significance-breeding-fast-nuclear-reactors"><span>Significance of breeding in fast nuclear <span class="hlt">reactors</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Raza, S.M.; Abidi, S.B.M.</p> <p>1983-12-01</p> <p>Only breeder <span class="hlt">reactors</span>--nuclear power plants that produce more fuel than they consume--are capable in principle of extracting the maximum amount of fission energy contained in uranium ore, thus offering a practical long-term solution to uranium supply problems. Uranium would then constitute a virtually inexhaustible fuel reserve for the world's future energy needs. The ultimate argument for breeding is to conserve the energy resources available to mankind. A long-term role for nuclear power with fast <span class="hlt">reactors</span> is proven to be economically viable, environmentally acceptable and capable of wide scale exploitation in many countries. In this paper, various suggestions pertaining to themore » fuel fabrication route, fuel cycle economics, studies of the physics of fast nuclear <span class="hlt">reactors</span> and of engineering design simplifications are presented. Fast <span class="hlt">reactors</span> contain no moderator and inherently require enriched fuel. In general, the main aim is to suggest an improvement in the understanding of the safety and control characteristics of fast breeder power <span class="hlt">reactors</span>. Development work is also being devoted to new carbide and nitride fuels, which are likely to exhibit breeding characteristics superior to those of the oxides of plutonium and uranium.« less</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/pages/biblio/1254086-liquid-fuel-molten-salt-reactors-thorium-utilization','SCIGOV-DOEP'); return false;" href="https://www.osti.gov/pages/biblio/1254086-liquid-fuel-molten-salt-reactors-thorium-utilization"><span>Liquid fuel molten salt <span class="hlt">reactors</span> for thorium utilization</span></a></p> <p><a target="_blank" href="http://www.osti.gov/pages">DOE PAGES</a></p> <p>Gehin, Jess C.; Powers, Jeffrey J.</p> <p>2016-04-08</p> <p>Molten salt <span class="hlt">reactors</span> (MSRs) represent a class of <span class="hlt">reactors</span> that use liquid salt, usually fluoride- or chloride-based, as either a coolant with a solid fuel (such as fluoride salt-cooled high temperature <span class="hlt">reactors</span>) or as a combined coolant and fuel with fuel dissolved in a carrier salt. For liquid-fuelled MSRs, the salt can be processed online or in a batch mode to allow for removal of fission products as well as introduction of fissile fuel and fertile materials during <span class="hlt">reactor</span> operation. The MSR is most commonly associated with the 233U/thorium fuel cycle, as the nuclear properties of 233U combined with themore » online removal of parasitic absorbers allow for the ability to design a thermal-spectrum breeder <span class="hlt">reactor</span>; however, MSR concepts have been developed using all neutron energy spectra (thermal, intermediate, fast, and mixed-spectrum zoned concepts) and with a variety of fuels including uranium, thorium, plutonium, and minor actinides. Early MSR work was supported by a significant research and development (R&D) program that resulted in two experimental systems operating at ORNL in the 1960s, the Aircraft <span class="hlt">Reactor</span> Experiment and the Molten Salt <span class="hlt">Reactor</span> Experiment. Subsequent design studies in the 1970s focusing on thermal-spectrum thorium-fueled systems established reference concepts for two major design variants: (1) a molten salt breeder <span class="hlt">reactor</span> (MSBR), with multiple configurations that could breed additional fissile material or maintain self-sustaining operation; and (2) a denatured molten salt <span class="hlt">reactor</span> (DMSR) with enhanced proliferation-resistance. T MSRs has been selected as one of six most promising Generation IV systems and development activities have been seen in fast-spectrum MSRs, waste-burning MSRs, MSRs fueled with low-enriched uranium (LEU), as well as more traditional thorium fuel cycle-based MSRs. This study provides an historical background of MSR R&D efforts, surveys and summarizes many of the recent development, and provides analysis comparing</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4823983','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4823983"><span><span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Spitzer, L. Jr.</p> <p>1962-01-01</p> <p>The system conteraplates ohmically heating a gas to high temperatures such as are useful in thermonuclear <span class="hlt">reactors</span> of the stellarator class. To this end the gas is ionized and an electric current is applied to the ionized gas ohmically to heat the gas while the ionized gas is confined to a central portion of a reaction chamber. Additionally, means are provided for pumping impurities from the gas and for further heating the gas. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://ntrs.nasa.gov/search.jsp?R=19770029945&hterms=nuclear+reactors&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D40%26Ntt%3Dnuclear%2Breactors','NASA-TRS'); return false;" href="https://ntrs.nasa.gov/search.jsp?R=19770029945&hterms=nuclear+reactors&qs=Ntx%3Dmode%2Bmatchall%26Ntk%3DAll%26N%3D0%26No%3D40%26Ntt%3Dnuclear%2Breactors"><span>Heat pipe nuclear <span class="hlt">reactor</span> for space power</span></a></p> <p><a target="_blank" href="http://ntrs.nasa.gov/search.jsp">NASA Technical Reports Server (NTRS)</a></p> <p>Koening, D. R.</p> <p>1976-01-01</p> <p>A heat-pipe-cooled nuclear <span class="hlt">reactor</span> has been designed to provide 3.2 MWth to an out-of-core thermionic conversion system. The <span class="hlt">reactor</span> is a fast <span class="hlt">reactor</span> designed to operate at a nominal heat-pipe temperature of 1675 K. Each <span class="hlt">reactor</span> fuel element consists of a hexagonal molybdenum block which is bonded along its axis to one end of a molybdenum/lithium-vapor heat pipe. The block is perforated with an array of longitudinal holes which are loaded with UO2 pellets. The heat pipe transfers heat directly to a string of six thermionic converters which are bonded along the other end of the heat pipe. An assembly of 90 such fuel elements forms a hexagonal core. The core is surrounded by a thermal radiation shield, a thin thermal neutron absorber, and a BeO reflector containing boron-loaded control drums.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/1232207-reactor-application-coaching-newbies','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/1232207-reactor-application-coaching-newbies"><span><span class="hlt">Reactor</span> Application for Coaching Newbies</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p></p> <p>2015-06-17</p> <p>RACCOON is a Moose based <span class="hlt">reactor</span> physics application designed to engage undergraduate and first-year graduate students. The code contains capabilities to solve the multi group Neutron Diffusion equation in eigenvalue and fixed source form and will soon have a provision to provide simple thermal feedback. These capabilities are sufficient to solve example problems found in Duderstadt & Hamilton (the typical textbook of senior level <span class="hlt">reactor</span> physics classes). RACCOON does not contain any advanced capabilities as found in YAK.</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/4716155','DOE-PATENT-XML'); return false;" href="https://www.osti.gov/biblio/4716155"><span>PROCESS FOR COOLING A NUCLEAR <span class="hlt">REACTOR</span></span></a></p> <p><a target="_blank" href="http://www.osti.gov/doepatents">DOEpatents</a></p> <p>Borst, L.B.</p> <p>1962-12-11</p> <p>This patent relates to the operation of a <span class="hlt">reactor</span> cooled by liquid sulfur dioxide. According to the invention the pressure on the sulfur dioxide in the <span class="hlt">reactor</span> is maintained at least at the critical pressure of the sulfur dioxide. Heating the sulfur dioxide to its critical temperature results in vaporization of the sulfur dioxide without boiling. (AEC)</p> </li> <li> <p><a target="_blank" onclick="trackOutboundLink('https://www.osti.gov/biblio/6010086-dr-reactor-vsr-channel-damage','SCIGOV-STC'); return false;" href="https://www.osti.gov/biblio/6010086-dr-reactor-vsr-channel-damage"><span>DR <span class="hlt">Reactor</span> VSR channel damage</span></a></p> <p><a target="_blank" href="http://www.osti.gov/search">DOE Office of Scientific and Technical Information (OSTI.GOV)</a></p> <p>Kempf, F.J.; Rawlins, J.K.</p> <p>1961-10-30</p> <p>On July 11, 1961 the Ball 3X System at DR <span class="hlt">Reactor</span> was inadventently tripped. All vertical safety rods dropped and all channels were filled with balls. This report has the twofold purpose of documenting borescope observations of ten vertical rod channels at DR <span class="hlt">Reactor</span> and recording the estimated extent of graphite damage resulting from the above incident. Channel damage data are presented on appended drawings. With suitable notations, the tracings of these drawings may be revised to reflect any future graphite damage. All vertical rod channels at DR <span class="hlt">Reactor</span> were visually examined with a closed circuit television system during ballmore » removal efforts. Typical photographs of trapped balls and ledges, as viewed on the television monitor, are shown. Photographs of typical graphite damage, obtained through the borescope are also included in this report. 3 refs., 8 figs., 1 tab.« less</p> </li> </ol> <div class="pull-right"> <ul class="pagination"> <li><a href="#" onclick='return showDiv("page_1");'>«</a></li> <li><a href="#" onclick='return showDiv("page_21");'>21</a></li> <li><a href="#" onclick='return showDiv("page_22");'>22</a></li> <li><a href="#" onclick='return showDiv("page_23");'>23</a></li> <li><a href="#" onclick='return showDiv("page_24");'>24</a></li> <li class="active"><span>25</span></li> <li><a href="#" onclick='return showDiv("page_25");'>»</a></li> </ul> </div> </div><!-- col-sm-12 --> </div><!-- row --> </div><!-- page_25 --> <div class="footer-extlink text-muted" style="margin-bottom:1rem; text-align:center;">Some links on this page may take you to non-federal websites. 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