Science.gov

Sample records for nuclear station projected

  1. The TACIS Nuclear Programme: Assistance in Upgrading Russian Nuclear Power Stations - An Overview of the Individual Projects in the Internet

    SciTech Connect

    Bieth, Michel; Schoels, Hubert

    2006-07-01

    The European Union' TACIS1 programme has been established for the New Independent States (NIS), among them in the Russian Federation since 1991. One priority of TACIS funding is Nuclear Safety. The European Commission has made available a total of 944 Million Euros for nuclear safety programmes covering the period 1991-2003. The TACIS nuclear safety programme is devoted to the improvement of the safety of Soviet designed nuclear installations in providing technology and safety culture transfer. JRC is carrying out works in the following areas: On-Site Assistance for TACIS operating Nuclear Power Plants; Design Safety and Dissemination of TACIS results; Reactor Pressure Vessel Embrittlement for VVER; Regulatory Assistance; Industrial Waste Management; Nuclear Safeguards; All TACIS projects, dealing with these areas of activity are now available in so called Project Description Sheets (PDS) or Project Results Sheets (PRS) in the Internet for everybody. JRC has created in the Internet an easy to open and to browse database which contains the result of works in relation to the above mentioned nuclear activities. This presentation gives an on-line overview of the app. 430 projects which have been implemented so far since the outset of the TACIS Nuclear Programme in the Russian Federation, which is representative to the other CIS countries, benefiting from the TACIS. The presentation will mainly consist of an on-line-demonstration of the TACIS Nuclear WEB Page, created by JRC. (authors)

  2. Review of DNA(Defense Nuclear Agency) Remote Security Station (RSS) Project. Phase 1

    SciTech Connect

    Pletta, J.B.; Workhoven, R.M.

    1988-08-01

    This report reviews the progress made during FY87 on the Defense Nuclear Agency (DNA) sponsored Remote Security Station (RSS). During this time frame, Sandia National Laboratories was tasked to develop a Phase 1 proof-of-principle system consisting of readily available hardware. The primary emphasis was placed upon development of software and sensor fusion techniques and, as a result, the Phase 1 hardware is not suitable for field deployment. The RSS consists of a portable (non-mobile) sensor platform and an intelligent controller. The paper includes descriptions of the sensor platform and control console hardware, as well as the software that runs the intelligent controller. The sensor fusion techniques originally considered are discussed, and the methods used in the current system are explained in detail. Phase 2 development of the RSS is scheduled for FY88, and a discussion of the planned improvements is included.

  3. Seismic structural fragility investigation for the San Onofre Nuclear Generating Station, Unit 1 (Project I); SONGS-1 AFWS Project

    SciTech Connect

    Wesley, D.A.; Hashimoto, P.S.

    1982-04-01

    An evaluation of the seismic capacities of several of the San Onofre Nuclear Generating Station, Unit 1 (SONGS-1) structures was conducted to determine input to the overall probabilistic methodology developed by Lawrence Livermore National Laboratory. Seismic structural fragilities to be used as input consist of median seismic capacities and their variabilities due to randomness and uncertainty. Potential failure modes were identified for each of the SONGS-1 structures included in this study by establishing the seismic load-paths and comparing expected load distributions to available capacities for the elements of each load-path. Particular attention was given to possible weak links and details. The more likely failure modes were screened for more detailed investigation.

  4. 75 FR 22674 - Moynihan Station Development Project

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-29

    ... Federal Railroad Administration Moynihan Station Development Project AGENCY: Federal Railroad... comment period for the Moynihan Station Development Project Environmental Assessment. SUMMARY: The Federal Railroad Administration announces the availability of the Moynihan Station ] Development Project...

  5. 75 FR 11205 - Entergy Nuclear Operations, Inc; Pilgrim Nuclear Power Station Environmental Assessment and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-10

    ... COMMISSION Entergy Nuclear Operations, Inc; Pilgrim Nuclear Power Station Environmental Assessment and... Nuclear Operations, Inc. (Entergy or the licensee), for operation of Pilgrim Nuclear Power Station... Nuclear Power Station,'' NUREG-1437, Supplement 29, published in July 2007 (ADAMS Accession...

  6. Spent Nuclear Fuel project, project management plan

    SciTech Connect

    Fuquay, B.J.

    1995-10-25

    The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

  7. Determining Yankee Nuclear Power Station neutron activation

    SciTech Connect

    Heider, K.J.; Morrissey, K.J. )

    1993-01-01

    The Yankee nuclear power station located in Rowe, Massachusetts, permanently ceased power operations on February 26, 1992, after 31 yr of operation. Yankee has since initiated decommissioning planning activities. A significant component of these activities is a determination of the extent of radiological contamination of the Yankee site. Included in this effort was determination of the extent of neutron activation of plant components. This paper describes the determination of the neutron activation of the Yankee reactor vessel, associated internals, and surrounding structures. The Yankee reactor vessel is a 600-MW(thermal) stainless steel-lined, carbon steel vessel with stainless steel internal components designed by Westinghouse. The reactor vessel is surrounded and supported by a carbon steel neutron shield tank that was filled with chromated water during plant operation. A 5-ft-thick concrete biological shield wall surrounds the neutron shield tank. A project is under way to remove the reactor vessel internals from the reactor vessel.

  8. Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project

    SciTech Connect

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

  9. Space Station Biological Research Project.

    PubMed

    Johnson, C C; Wade, C E; Givens, J J

    1997-06-01

    To meet NASA's objective of using the unique aspects of the space environment to expand fundamental knowledge in the biological sciences, the Space Station Biological Research Project at Ames Research Center is developing, or providing oversight, for two major suites of hardware which will be installed on the International Space Station (ISS). The first, the Gravitational Biology Facility, consists of Habitats to support plants, rodents, cells, aquatic specimens, avian and reptilian eggs, and insects and the Habitat Holding Rack in which to house them at microgravity; the second, the Centrifuge Facility, consists of a 2.5 m diameter centrifuge that will provide acceleration levels between 0.01 g and 2.0 g and a Life Sciences Glovebox. These two facilities will support the conduct of experiments to: 1) investigate the effect of microgravity on living systems; 2) what level of gravity is required to maintain normal form and function, and 3) study the use of artificial gravity as a countermeasure to the deleterious effects of microgravity observed in the crew. Upon completion, the ISS will have three complementary laboratory modules provided by NASA, the European Space Agency and the Japanese space agency, NASDA. Use of all facilities in each of the modules will be available to investigators from participating space agencies. With the advent of the ISS, space-based gravitational biology research will transition from 10-16 day short-duration Space Shuttle flights to 90-day-or-longer ISS increments.

  10. 75 FR 6223 - PSEG Nuclear LLC; Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-08

    ... COMMISSION PSEG Nuclear LLC; Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1... Hope Creek Generating Station (HCGS) and the Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem), located in Salem County, New Jersey. In accordance with 10 CFR 51.21, the NRC prepared an...

  11. 75 FR 75706 - Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Unit Nos. 1...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-06

    ... Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Unit Nos. 1 and 2; Notice of... Nuclear Power Station, Units 2 and 3, respectively, located in Grundy County, Illinois, and to Renewed Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Unit Nos. 1 and...

  12. 77 FR 18271 - Terrestrial Environmental Studies for Nuclear Power Stations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-27

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Terrestrial Environmental Studies for Nuclear Power Stations AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing...

  13. 76 FR 50274 - Terrestrial Environmental Studies for Nuclear Power Stations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-12

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Terrestrial Environmental Studies for Nuclear Power Stations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment. SUMMARY: The U.S. Nuclear Regulatory Commission...

  14. Yankee Nuclear Power Station - analysis of decommissioning costs

    SciTech Connect

    Lessard, L.P.

    1996-12-31

    The preparation of decommissioning cost estimates for nuclear power generating stations has received a great deal of interest in the last few years. Owners are required by regulation to ensure that adequate funds are collected for the timely decommissioning of their facilities. The unexpected premature shutdown of several facilities and uncertainties associated with radioactive waste disposal and long-term spent-fuel storage, when viewed in the light of a deregulated electric utility industry, has caused many companies to reevaluate their decommissioning cost estimates. The decommissioning of the Yankee Nuclear Power Station represents the first large-scale project involving the complete decontamination and dismantlement of a commercial light water nuclear power generation facility in the United States. Since this pressurized water reactor operated for 32 yr at a respectable 74% lifetime capacity factor, the actual costs and resources required to decommission the plant, when compared with decommissioning estimates, will yield valuable benchmarking data.

  15. Space Station Biological Research Project

    NASA Technical Reports Server (NTRS)

    Johnson, Catherine C.; Hargens, Alan R.; Wade, Charles E.

    1995-01-01

    NASA Ames Research Center is responsible for the development of the Space Station Biological Research Project (SSBRP) which will support non-human life sciences research on the International Space Station Alpha (ISSA). The SSBRP is designed to support both basic research to understand the effect of altered gravity fields on biological systems and applied research to investigate the effects of space flight on biological systems. The SSBRP will provide the necessary habitats to support avian and reptile eggs, cells and tissues, plants and rodents. In addition a habitat to support aquatic specimens will be provided by our international partners. Habitats will be mounted in ISSA compatible racks at u-g and will also be mounted on a 2.5 m diameter centrifuge except for the egg incubator which has an internal centrifuge. The 2.5 m centrifuge will provide artificial gravity levels over the range of 0.01 G to 2 G. The current schedule is to launch the first rack in 1999, the Life Sciences glovebox and a second rack early in 2001, a 4 habitat 2.5 in centrifuge later the same year in its own module, and to upgrade the centrifuge to 8 habitats in 2004. The rodent habitats will be derived from the Advanced Animal Habitat currently under development for the Shuttle program and will be capable of housing either rats or mice individually or in groups (6 rats/group and at least 12 mice/group). The egg incubator will be an upgraded Avian Development Facility also developed for the Shuttle program through a Small Business and Innovative Research grant. The Space Tissue Loss cell culture apparatus, developed by Walter Reed Army Institute of Research, is being considered for the cell and tissue culture habitat. The Life Sciences Glovebox is crucial to all life sciences experiments for specimen manipulation and performance of science procedures. It will provide two levels of containment between the work volume and the crew through the use of seals and negative pressure. The glovebox

  16. 78 FR 35646 - Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-13

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2 AGENCY: Nuclear... U.S. Nuclear Regulatory Commission (NRC) has received an application, dated May 29, 2013,...

  17. 75 FR 12311 - Entergy Nuclear Operations, Inc; Vermont Yankee Nuclear Power Station Environmental Assessment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-15

    ... COMMISSION Entergy Nuclear Operations, Inc; Vermont Yankee Nuclear Power Station Environmental Assessment and... Nuclear Operations, Inc. (Entergy or the licensee), for operation of Vermont Yankee Nuclear Power Station... Statement for Vermont Yankee Nuclear Power Station, Docket No. 50-271, dated July 1972, as...

  18. Commentary: childhood cancer near nuclear power stations

    PubMed Central

    2009-01-01

    In 2008, the KiKK study in Germany reported a 1.6-fold increase in solid cancers and a 2.2-fold increase in leukemias among children living within 5 km of all German nuclear power stations. The study has triggered debates as to the cause(s) of these increased cancers. This article reports on the findings of the KiKK study; discusses past and more recent epidemiological studies of leukemias near nuclear installations around the world, and outlines a possible biological mechanism to explain the increased cancers. This suggests that the observed high rates of infant leukemias may be a teratogenic effect from incorporated radionuclides. Doses from environmental emissions from nuclear reactors to embryos and fetuses in pregnant women near nuclear power stations may be larger than suspected. Hematopoietic tissues appear to be considerably more radiosensitive in embryos/fetuses than in newborn babies. Recommendations for advice to local residents and for further research are made. PMID:19775438

  19. Military space station implications. Study project

    SciTech Connect

    Bourne, G.D.; Skirvin, G.D.; Wilson, G.R.

    1987-03-23

    Justifying the relevancy of a Manned Military Space Station (MMSS) and subsequently proposing its deployment to capitalize upon the United States' national security interests is the essence and purpose of this group study project. The MMSS is intended to perform a two-fold purpose: (1) facilitate military peacetime operations while simultaneously supporting and promoting civilian space initiatives; and, (2) act as a force multiplier for space and terrestrial force operations in the event of conventional, theater nuclear, and/or strategic nuclear war. Data to support the future value of the MMSS was obtained from individual and group research using unclassified sources such as professional journals, books, US Air Force Staff College reference material, and information from the US Air Force space coordinating staff in Washington, DC. The importance of space to our future and especially of a MMSS by America's national leaders and its people has yet to be fully appreciated and/or realized. The significance of space and its nexus to the United States' national security has been growing dramatically in importance since the launching of the Sputnik in 1957 by Russian. Space, as the forth dimension, cannot and should not be understated in importance as it relates to commercialism, deterrence to war, and to the stability of world order.

  20. Tethered nuclear power for the space station

    NASA Technical Reports Server (NTRS)

    Bents, D. J.

    1985-01-01

    A nuclear space power system the SP-100 is being developed for future missions where large amounts of electrical power will be required. Although it is primarily intended for unmanned spacecraft, it can be adapted to a manned space platform by tethering it above the station through an electrical transmission line which isolates the reactor far away from the inhabited platform and conveys its power back to where it is needed. The transmission line, used in conjunction with an instrument rate shield, attenuates reactor radiation in the vicinity of the space station to less than one-one hundredth of the natural background which is already there. This combination of shielding and distance attenuation is less than one-tenth the mass of boom-mounted or onboard man-rated shields that are required when the reactor is mounted nearby. This paper describes how connection is made to the platform (configuration, operational requirements) and introduces a new element the coaxial transmission tube which enables efficient transmission of electrical power through long tethers in space. Design methodology for transmission tubes and tube arrays is discussed. An example conceptual design is presented that shows SP-100 at three power levels 100 kWe, 300 kWe, and 1000 kWe connected to space station via a 2 km HVDC transmission line/tether. Power system performance, mass, and radiation hazard are estimated with impacts on space station architecture and operation.

  1. Tethered nuclear power for the Space Station

    NASA Technical Reports Server (NTRS)

    Bents, D. J.

    1985-01-01

    A nuclear space power system the SP-100 is being developed for future missions where large amounts of electrical power will be required. Although it is primarily intended for unmanned spacecraft, it can be adapted to a manned space platform by tethering it above the station through an electrical transmission line which isolates the reactor far away from the inhabited platform and conveys its power back to where it is needed. The transmission line, used in conjunction with an instrument rate shield, attenuates reactor radiation in the vicinity of the space station to less than one-one hundredth of the natural background which is already there. This combination of shielding and distance attenuation is less than one-tenth the mass of boom-mounted or onboard man-rated shields that are required when the reactor is mounted nearby. This paper describes how connection is made to the platform (configuration, operational requirements) and introduces a new element the coaxial transmission tube which enables efficient transmission of electrical power through long tethers in space. Design methodology for transmission tubes and tube arrays is discussed. An example conceptual design is presented that shows SP-100 at three power levels 100 kWe, 300 kWe, and 1000 kWe connected to space station via a 2 km HVDC transmission line/tether. Power system performance, mass, and radiation hazard are estimated with impacts on space station architecture and operation.

  2. Final MTI Data Report: Pilgrim Nuclear Station

    SciTech Connect

    Parker, M.J.

    2003-03-17

    During the period from May 2000 to September 2001, ocean surface water temperature data was collected at the Pilgrim Nuclear Power Station near Plymouth, MA. This effort was led by the Savannah River Technology Center (SRTC) with the assistance of a local sub-contractor, Marine BioControl Corporation of Sandwich, MA. Permission for setting up the monitoring system was granted by Energy Corporation, which owns the plant site. This work was done in support of SRTC's ground truth mission for the U.S. Department of Energy's Multispectral Thermal Imager (MTI) satellite.

  3. Live from Space Station Learning Technologies Project

    NASA Technical Reports Server (NTRS)

    2001-01-01

    This is the Final Report for the Live From Space Station (LFSS) project under the Learning Technologies Project FY 2001 of the MSFC Education Programs Department. AZ Technology, Inc. (AZTek) has developed and implemented science education software tools to support tasks under the LTP program. Initial audience consisted of 26 TreK in the Classroom schools and thousands of museum visitors to the International Space Station: The Earth Tour exhibit sponsored by Discovery Place museum.

  4. Nuclear power station main control room habitability

    SciTech Connect

    Paschal, W.B.; Knous, W.S. )

    1989-01-01

    The main control room at a nuclear power station must remain habitable during a variety of plant conditions and postulated events. The control room habitability requirement and the function of the heating, ventilating, air-conditioning, and air treatment system are to control environmental factors, such as temperature, pressure, humidity, radiation, and toxic gas. Habitability requirements provide for the safety of personnel and enable operation of equipment required to function in the main control room. Habitability as an issue has been gaining prominence with the Advisor Committee of Reactor Safeguards and the Nuclear Regulatory Commission since the incident at Three Mile Island. Their concern is the ability of the presently installed habitability systems to control the main control room environment after an accident. This paper discusses main control room HVAC systems; the concern, requirements, and results of NRC surveys and notices; and an approach to control room habitability reviews.

  5. Radiological characterization of Yankee Nuclear Power Station

    SciTech Connect

    Bellini, F.X.; Cumming, E.R.; Hollenbeck, P. )

    1993-01-01

    The Yankee nuclear power station located in Rowe, Massachusetts, permanently ceased power operations on February 26, 1992, after 31 yr of operation. Yankee has since initiated decommissioning planning activities. A significant component of these activities is the determination of the extent of radiological contamination of the Yankee site. This paper describes the site radiological characterization program that has been implemented for decommissioning the Yankee plant. Radiological scoping surveys were completed to support submittal of a decommissioning plan to the U.S. Nuclear Regulatory Commission (NRC) by October 1, 1993. These surveys were designed to provide sufficient detail to estimate the extent of contamination, volume of radiological waste, activity of radiological waste, and personnel dose estimates for removal activities. Surveys were conducted both inside and on the grounds outside of the Yankee plant buildings. Survey results were combined with analytical evaluations to characterize the Yankee site.

  6. 75 FR 2164 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance...

  7. 75 FR 14635 - FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Environmental...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-26

    ... COMMISSION FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Environmental Assessment...Energy Nuclear Operating Company (FENOC, the licensee), for operation of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS), located in Ottawa County, Ohio. Therefore, as required by 10 CFR 51.21, the...

  8. Waste management for Shippingport Station Decommissioning Project: Extended summary

    SciTech Connect

    Mullee, G.R.; Schulmeister, A.R.

    1987-01-01

    The Shippingport Station (SSDP) is demonstrating that the techniques and methodologies of waste management, which are currently employed by the nuclear industry, provide adequate management and control of waste activities for the decommissioning of a large scale nuclear plant. The SSDP has some unique aspects in that as part of the objective to promote technology transfer, multiple subcontractors are being utilized in the project. The interfaces resulting from multiple subcontractors require additional controls. Effective control has been accomplished by the use of a process control and inventory system, coupled with personnel training in waste management activities. This report summarizes the waste management plan and provides a status of waste management activities for SSDP.

  9. International Space Station Medical Project

    NASA Technical Reports Server (NTRS)

    Starkey, Blythe A.

    2008-01-01

    The goals and objectives of the ISS Medical Project (ISSMP) are to: 1) Maximize the utilization the ISS and other spaceflight platforms to assess the effects of longduration spaceflight on human systems; 2) Devise and verify strategies to ensure optimal crew performance; 3) Enable development and validation of a suite of integrated physical (e.g., exercise), pharmacologic and/or nutritional countermeasures against deleterious effects of space flight that may impact mission success or crew health. The ISSMP provides planning, integration, and implementation services for Human Research Program research tasks and evaluation activities requiring access to space or related flight resources on the ISS, Shuttle, Soyuz, Progress, or other spaceflight vehicles and platforms. This includes pre- and postflight activities; 2) ISSMP services include operations and sustaining engineering for HRP flight hardware; experiment integration and operation, including individual research tasks and on-orbit validation of next generation on-orbit equipment; medical operations; procedures development and validation; and crew training tools and processes, as well as operation and sustaining engineering for the Telescience Support Center; and 3) The ISSMP integrates the HRP approved flight activity complement and interfaces with external implementing organizations, such as the ISS Payloads Office and International Partners, to accomplish the HRP's objectives. This effort is led by JSC with Baseline Data Collection support from KSC.

  10. Decontamination of nuclear systems at the Grand Gulf Nuclear Station

    SciTech Connect

    Weed, R.D.; Baker, K.R.

    1996-12-31

    Early in 1994 Management at the Grand Gulf Nuclear Station realized that a potential decontamination of several reactor systems was needed to maintain the commitments to the {open_quotes}As Low As Reasonably Achievable{close_quotes} (ALARA) program. There was a substantial amount of planned outage work required to repair and replace some internals in loop isolation valves and there were inspections and other outage work that needed to be accomplished as it had been postponed from previous outages because of the radiation exposure levels in and around the system equipment. Management scheduled for the procurement specification to be revised to incorporate additional boundary areas which had not been previously considered. The schedule included the period for gathering bids, awarding a contract, and reviewing the contractor`s procedures and reports and granting approval for the decontamination to proceed during the upcoming outage. In addition to the reviews required by the engineering group for overall control of the process, the plant system engineers had to prepare procedures at the system level to provide for a smooth operation to be made during the decontamination of the systems. The system engineers were required to make certain that the decontamination fluids would be contained within the systems being decontaminated and that they would not cross contaminate any other system not being decontaminated. Since these nuclear stations do not have the provisions for decontaminating these systems with using additional equipment, the equipment required is furnished by the contractor as skid mounted packaged units which can be moved into the area, set up near the system being decontaminated, and after the decontamination is completed, the skid mounted packages are removed as part of the contract. Figure 1 shows a typical setup in block diagram required to perform a reactor system decontamination. 1 fig.

  11. 76 FR 82201 - General Site Suitability Criteria for Nuclear Power Stations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-30

    ... Power Stations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for... regulatory guide DG-4021, ``General Site Suitability Criteria for Nuclear Power Stations.'' This guide... for nuclear power stations. DATES: Submit comments by February 25, 2012. Comments received after...

  12. Station blackout at nuclear power plants: Radiological implications for nuclear war

    SciTech Connect

    Shapiro, C.S.

    1986-12-01

    Recent work on station blackout is reviewed its radiological implications for a nuclear war scenario is explored. The major conclusion is that the effects of radiation from many nuclear weapon detonations in a nuclear war would swamp those from possible reactor accidents that result from station blackout.

  13. 77 FR 35080 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station; Record of Decision and Issuance...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-12

    ... fossil fuel generation, renewable energy sources, demand-side measures such as energy conservation, and... COMMISSION Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station; Record of Decision and Issuance... Operations Inc. (the licensee), the operator of the Pilgrim Nuclear Power Station (PNPS). Renewed...

  14. 78 FR 61400 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-03

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision Notice is hereby given that the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear...

  15. 77 FR 76541 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-28

    ...] [FR Doc No: 2012-31286] NUCLEAR REGULATORY COMMISSION [Docket No. 50-293; NRC-2012-0311] Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station AGENCY: Nuclear Regulatory Commission. ACTION....S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from Title 10 of...

  16. 76 FR 17162 - Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Notice of Issuance of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-28

    ... COMMISSION Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Notice of Issuance of... Renewed Facility Operating License No. DPR-28 to Entergy Nuclear Vermont Yankee, LLC (Entergy VY), and Entergy Nuclear Operations, Inc. (ENO), (licensee), the operator of the Vermont Yankee Nuclear...

  17. 76 FR 39910 - Nine Mile Point Nuclear Station, LLC; Nine Mile Point Nuclear Station, Unit Nos. 1 and 2; Notice...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-07

    ... Nuclear Station, LLC is owned by Constellation Energy Nuclear Group, LLC (CENG). The indirect transfer of... companies, Constellation Energy Group, Inc (CEG). According to the application dated May 12, 2011, filed by... Throughout the transaction, the direct ownership by CEG of 100 percent of Constellation Nuclear, LLC...

  18. Nuclear Propulsion Project Workshop summary

    NASA Technical Reports Server (NTRS)

    Miller, Thomas J.; Clark, John S.; Barnett, John W.

    1991-01-01

    NASA-Lewis has undertaken the planning and coordination of a joint NASA/DOE/DOD Nuclear Propulsion Project which will investigate both nuclear electric and nuclear thermal concepts. The three-agency team has been tasked with the development of an Interagency Agreement and Memorandum of Understanding, as well as the drafting of a statement as to astronaut crew guidelines and values, the assessment of human-rating requirements, the development of an interagency safety and environmental assessment plan, and the development of test facility requirements. Attention is to be given to the role of SP-100 for nuclear-electric propulsion applications.

  19. The ALTCRISS Project On Board the International Space Station

    NASA Technical Reports Server (NTRS)

    Cucinotta, Francis A.; Casolino, M.; Altamura, F.; Minori, M.; Picozza, P.; Fuglesang, C.; Galper, A.; Popov, A.; Benghin, V.; Petrov, V. M.

    2006-01-01

    The Altcriss project aims to perform a long term survey of the radiation environment on board the International Space Station. Measurements are being performed with active and passive devices in different locations and orientations of the Russian segment of the station. The goal is perform a detailed evaluation of the differences in particle fluence and nuclear composition due to different shielding material and attitude of the station. The Sileye-3/Alteino detector is used to identify nuclei up to Iron in the energy range above approximately equal to 60 MeV/n; a number of passive dosimeters (TLDs, CR39) are also placed in the same location of Sileye-3 detector. Polyethylene shielding is periodically interposed in front of the detectors to evaluate the effectiveness of shielding on the nuclear component of the cosmic radiation. The project was submitted to ESA in reply to the AO the Life and Physical Science of 2004 and was begun in December 2005. Dosimeters and data cards are rotated every six months: up to now three launches of dosimeters and data cards have been performed and have been returned with the end expedition 12 and 13.

  20. ANSYS analyses on the Shippingport Station Decommissioning Project

    SciTech Connect

    DeSantis, P.V.; McNamee, H.G.

    1987-01-01

    The nuclear reactor vessel from the Shippingport Station, located in Shippingport, Pennsylvania, will be removed as part of the overall Decommissioning Project. The reactor vessel along with a specially designed lifting beam and skirt were modelled to examine the stresses and behavior of the combined structure. Both the PC/Linear Version of ANSYS and the Cray Version were used in the two phases of the analysis. This paper describes the modelling and analytical techniques used to evaluate the design of this one-of-a-kind structure. The combination of the two versions of ANSYS provided the design team with excellent results in a timely and cost effective manner.

  1. NASA's Nuclear Thermal Propulsion Project

    NASA Technical Reports Server (NTRS)

    Houts, Michael G.; Mitchell, Doyce P.; Kim, Tony; Emrich, William J.; Hickman, Robert R.; Gerrish, Harold P.; Doughty, Glen; Belvin, Anthony; Clement, Steven; Borowski, Stanley K.; Scott, John; Power, Kevin P.

    2015-01-01

    The fundamental capability of Nuclear Thermal Propulsion (NTP) is game changing for space exploration. A first generation NTP system could provide high thrust at a specific impulse above 900 s, roughly double that of state of the art chemical engines. Characteristics of fission and NTP indicate that useful first generation systems will provide a foundation for future systems with extremely high performance. The role of a first generation NTP in the development of advanced nuclear propulsion systems could be analogous to the role of the DC- 3 in the development of advanced aviation. Progress made under the NTP project could also help enable high performance fission power systems and Nuclear Electric Propulsion (NEP).

  2. 76 FR 30204 - Exelon Nuclear, Dresden Nuclear Power Station, Unit 1; Exemption From Certain Security Requirements

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-24

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Nuclear, Dresden Nuclear Power Station, Unit 1; Exemption From Certain Security Requirements 1.0 Background Exelon Nuclear is the licensee and holder of Facility Operating License No....

  3. 75 FR 14209 - Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-24

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (Entergy or the licensee) is the holder of Facility Operating License...

  4. 78 FR 784 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-04

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (the licensee) is the holder of Renewed Facility Operating License No....

  5. 75 FR 14208 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-24

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (Entergy or the licensee) is the holder of Facility Operating License No....

  6. 75 FR 16523 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-01

    ... COMMISSION FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the holder of Facility Operating License... M.S. Fertel, Nuclear Energy Institute). The licensee's request for an exemption is...

  7. 75 FR 80549 - FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-22

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the holder of Facility Operating...

  8. 75 FR 38147 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-01

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the holder of Facility Operating...

  9. Power plant of high safety for underground nuclear power station

    SciTech Connect

    Dolgov, V.N.

    1993-12-31

    An ecologically pure, reliable, and economic nuclear power station is based on the use of nuclear power plants with the liquid-metal coolant. This plant with the inherent safety is protected from external influences due to the underground accommodations in geologically stable formations such as granites, cambrian clays, and salt deposits. The design features of this underground plant are described.

  10. Yankee nuclear power station license renewal assessment

    SciTech Connect

    Hinkle, W.D. )

    1992-01-01

    Nuclear power plants are initially licensed to operate for 40 years. Recent changes to US Nuclear Regulatory Commission regulations allow licenses to be renewed for up to 20 additional years. The new regulations require a comprehensive plant assessment to ensure continued effective aging management of equipment important to license renewal (ILR). Under the industry's lead plant program, Yankee Atomic Electric Company (YAEC) has assisted with development and demonstration of a generic license renewal assessment process. The generic assessment process developed under the lead plant program is the Nuclear Management and Resources Council methodology.

  11. Summary of monitoring station component evaluation project 2009-2011.

    SciTech Connect

    Hart, Darren M.

    2012-02-01

    Sandia National Laboratories (SNL) is regarded as a center for unbiased expertise in testing and evaluation of geophysical sensors and instrumentation for ground-based nuclear explosion monitoring (GNEM) systems. This project will sustain and enhance our component evaluation capabilities. In addition, new sensor technologies that could greatly improve national monitoring system performance will be sought and characterized. This work directly impacts the Ground-based Nuclear Explosion Monitoring mission by verifying that the performance of monitoring station sensors and instrumentation is characterized and suitable to the mission. It enables the operational monitoring agency to deploy instruments of known capability and to have confidence in operational success. This effort will ensure that our evaluation capabilities are maintained for future use.

  12. Radwaste (DAW) volume reduction cost initiative at the Oyster Creek Nuclear Generation Station

    SciTech Connect

    Wacha, A.H.

    1995-05-01

    Oyster Creek Nuclear Generating Station is a General Electric Mark 1, 620 MWe (Net) Boiling Water Reactor operated by GPU Nuclear Corporation and located in Forked River, New Jersey. The plant began commercial operation on December 23, 1969, and achieved its longest continuous run during cycle 14 (413 days) 2-16-93 to 9-11-94. As part of the industry-wide initiative to reduce nuclear plant O&M costs, the Electric Power Research Institute (EPRI) was asked by GPU Nuclear to assist the Oyster Creek Nuclear Generating Station (OCNGS) in identifying opportunities for reducing the costs associated with its Radwaste Minimization Program for Dry Active Waste (DAW). The purpose of the project was to evaluate the existing generation, minimization, processing and disposal programs and to identify a wide variety of potential mechanisms for reducing waste volumes and associated costs.

  13. 77 FR 135 - Exelon Generation Company, LLC, Oyster Creek Nuclear Generating Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-01-03

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Generation Company, LLC, Oyster Creek Nuclear Generating Station; Exemption 1.0 Background...-16, which authorizes operation of the Oyster Creek Nuclear Generating Station (OCNGS). The...

  14. Engineer and technical training at GPUN's nuclear generating stations

    SciTech Connect

    Coe, R.P. )

    1993-01-01

    GPU Nuclear (GPUN) owns and operates the Oyster Creek and Three Mile Island (TMI) unit I nuclear generating stations. They also continue the recovery efforts of the damaged reactor at TMI-2. Technical training for engineers and support staff is managed by the GPUN Corporate Training Department. The group also manages the Institute of Nuclear Power Operations (INPO)-accredited Engineering Support Personnel (ESP) Training Program and the GPUN New Engineer Training Program. The New Engineer Training Program has been in existence since 1982 and has trained and oriented [approximately]100 new college graduates to the nuclear industry.

  15. A Low-Cost Nuclear Medicine Acquisition Station

    NASA Astrophysics Data System (ADS)

    Goble, John C.

    1986-06-01

    A significant obstacle to the use of local area networks in Nuclear Medicine has been the high cost of computer systems capable of digitizing the analog outputs of conventional gamma cameras. A PC-based Nuclear Image Acquisition Station has been designed using readily available components that permits acquisition, display and transfer of nuclear images. Processing functions, including camera uniformity corrections, image rotation and edge enhancement and other operators Elre available locally. With appropriate file format manipulation, images may alternatively be transferred to a conventional Nuclear Medicine computer for processing and archival storage. Hardware and software costs required to implement these functions on an existing micro are less than $4000.

  16. Space Station Biological Research Project Habitat: Incubator

    NASA Technical Reports Server (NTRS)

    Nakamura, G. J.; Kirven-Brooks, M.; Scheller, N. M.

    2001-01-01

    Developed as part of the suite of Space Station Biological Research Project (SSBRP) hardware to support research aboard the International Space Station (ISS), the Incubator is a temperature-controlled chamber, for conducting life science research with small animal, plant and microbial specimens. The Incubator is designed for use only on the ISS and is transported to/from the ISS, unpowered and without specimens, in the Multi-Purpose Logistics Module (MPLM) of the Shuttle. The Incubator interfaces with the three SSBRP Host Systems; the Habitat Holding Racks (HHR), the Life Sciences Glovebox (LSG) and the 2.5 m Centrifuge Rotor (CR), providing investigators with the ability to conduct research in microgravity and at variable gravity levels of up to 2-g. The temperature within the Specimen Chamber can be controlled between 4 and 45 C. Cabin air is recirculated within the Specimen Chamber and can be exchanged with the ISS cabin at a rate of approximately equal 50 cc/min. The humidity of the Specimen Chamber is monitored. The Specimen Chamber has a usable volume of approximately equal 19 liters and contains two (2) connectors at 28v dc, (60W) for science equipment; 5 dedicated thermometers for science; ports to support analog and digital signals from experiment unique sensors or other equipment; an Ethernet port; and a video port. It is currently manifested for UF-3 and will be launched integrated within the first SSBRP Habitat Holding Rack.

  17. PROJECTIZING AN OPERATING NUCLEAR FACILITY

    SciTech Connect

    Adams, N

    2007-07-08

    This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully

  18. 78 FR 22347 - GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-15

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain Security Requirements AGENCY: Nuclear Regulatory Commission. ACTION: Exemption. FOR FURTHER INFORMATION CONTACT: John...

  19. Tampa Electric Company Polk Power Station IGCC project: Project status

    SciTech Connect

    McDaniel, J.E.; Carlson, M.R.; Hurd, R.; Pless, D.E.; Grant, M.D.

    1997-12-31

    The Tampa Electric Company Polk Power Station is a nominal 250 MW (net) Integrated Gasification Combined Cycle (IGCC) power plant located to the southeast of Tampa, Florida in Polk County, Florida. This project is being partially funded under the Department of Energy`s Clean Coal Technology Program pursuant to a Round II award. The Polk Power Station uses oxygen-blown, entrained-flow IGCC technology licensed from Texaco Development Corporation to demonstrate significant reductions of SO{sub 2} and NO{sub x} emissions when compared to existing and future conventional coal-fired power plants. In addition, this project demonstrates the technical feasibility of commercial scale IGCC and Hot Gas Clean Up (HGCU) technology. The Polk Power Station achieved ``first fire`` of the gasification system on schedule in mid-July, 1996. Since that time, significant advances have occurred in the operation of the entire IGCC train. This paper addresses the operating experiences which occurred in the start-up and shakedown phase of the plant. Also, with the plant being declared in commercial operation as of September 30, 1996, the paper discusses the challenges encountered in the early phases of commercial operation. Finally, the future plans for improving the reliability and efficiency of the Unit in the first quarter of 1997 and beyond, as well as plans for future alternate fuel test burns, are detailed. The presentation features an up-to-the-minute update on actual performance parameters achieved by the Polk Power Station. These parameters include overall Unit capacity, heat rate, and availability. In addition, the current status of the start-up activities for the HGCU portion of the plant is discussed.

  20. Satellite nuclear power station: An engineering analysis

    NASA Technical Reports Server (NTRS)

    Williams, J. R.; Clement, J. D.; Rosa, R. J.; Kirby, K. D.; Yang, Y. Y.

    1973-01-01

    A nuclear-MHD power plant system which uses a compact non-breeder reactor to produce power in the multimegawatt range is analyzed. It is shown that, operated in synchronous orbit, the plant would transmit power safely to the ground by a microwave beam. Fuel reprocessing would take place in space, and no radioactive material would be returned to earth. Even the effect of a disastrous accident would have negligible effect on earth. A hydrogen moderated gas core reactor, or a colloid-core, or NERVA type reactor could also be used. The system is shown to approach closely the ideal of economical power without pollution.

  1. Overview of IMS infrasound station and engineering projects

    NASA Astrophysics Data System (ADS)

    Marty, J.; Doury, B.; Kramer, A.; Martysevich, P.

    2015-12-01

    The Provisional Technical Secretariat (PTS) of the Comprehensive Nuclear-Test-Ban Treaty (CTBTO) has a continuous interest in enhancing its capability in acoustic source detection, localization and characterization. The infrasound component of the International Monitoring System (IMS) constitutes the only worldwide ground-based infrasound network. It consists of sixty stations, among which forty-eight are already certified and continuously transmit data to the International Data Centre (IDC) in Vienna, Austria. Each infrasound station is composed of an array of infrasound sensors capable of measuring micro-pressure changes produced at ground level by infrasonic waves. The characteristics of infrasonic waves are computed in near real-time by IDC automatic detection software and are used as an input to IDC source categorization and localization algorithms. The PTS is continuously working towards the completion and sustainment of the IMS infrasound network. The objective of this presentation is to review the main activities performed in the IMS infrasound network over the last five years. This includes construction, installation, certification, major upgrade and revalidation activities. Major technology development projects to improve the reliability and robustness of IMS infrasound stations as well as their compliance with IMS Operational Manual requirements will also be presented. This includes advances in array geometry, wind noise reduction, system calibration, meteorological data as well as power and communication infrastructures. Finally the impact of all these changes on the overall detection capability of the IMS infrasound network will be highlighted.

  2. NASA's Nuclear Thermal Propulsion Project

    NASA Technical Reports Server (NTRS)

    Houts, Mike; Mitchell, Sonny; Kim, Tony; Borowski, Stan; Power, Kevin; Scott, John; Belvin, Anthony; Clement, Steve

    2015-01-01

    HEOMD's (Human Exploration and Operations Mission Directorate) AES (Advanced Exploration Systems) Nuclear Thermal Propulsion (NTP) project is making significant progress. First of four FY 2015 milestones achieved this month. Safety is the highest priority for NTP (as with other space systems). After safety comes affordability. No centralized capability for developing, qualifying, and utilizing an NTP system. Will require a strong, closely integrated team. Tremendous potential benefits from NTP and other space fission systems. No fundamental reason these systems cannot be developed and utilized in a safe, affordable fashion.

  3. 76 FR 40944 - PSEG Nuclear, LLC, Salem Nuclear Generating Station, Units 1 and 2; Notice of Issuance of Renewed...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-12

    ... COMMISSION PSEG Nuclear, LLC, Salem Nuclear Generating Station, Units 1 and 2; Notice of Issuance of Renewed... License Nos. DPR-70 and DPR-75 to PSEG Nuclear LLC (the licensee), the operator of the Salem Nuclear Generating Station, Units 1 and 2 (Salem). Renewed Facility Operating License Nos. DPR-70 and...

  4. 75 FR 9619 - South Carolina Electric & Gas Company; Virgil C. Summer Nuclear Station; Environmental Assessment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-03

    ... COMMISSION South Carolina Electric & Gas Company; Virgil C. Summer Nuclear Station; Environmental Assessment.... Summer Nuclear Station (VCSNS), located in Fairfield County, South Carolina. In accordance with the.... Summer Nuclear Station, Unit No. 1, NUREG- 0719, dated May 1981 (ADAMS Accession No. ML072750234) and...

  5. 75 FR 8153 - Nebraska Public Power District; Cooper Nuclear Station Environmental Assessment and Finding of No...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-23

    ... COMMISSION Nebraska Public Power District; Cooper Nuclear Station Environmental Assessment and Finding of No... District (NPPD, the licensee), for operation of the Cooper Nuclear Station (CNS), located in Nemaha County... Statement for the Cooper Nuclear Station dated February 1973. Agencies and Persons Consulted In...

  6. 75 FR 52045 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-24

    ... COMMISSION Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental... Palo Verde Nuclear Generating Station (PVNGS), Unit 3, located in Maricopa County, Arizona. Therefore... Statement for the Palo Verde Nuclear Generating Station, NUREG-0841, dated February 1982. Agencies...

  7. License Amendment Request for Storing Exelon Sister Nuclear Stations Class B/C LLRW in the LaSalle Station Interim Radwaste Storage Facility - 13620

    SciTech Connect

    Azar, Miguel; Gardner, Donald A.; Taylor, Edward R.

    2013-07-01

    Exelon Nuclear (Exelon) designed and constructed an Interim Radwaste Storage Facility (IRSF) in the mid-1980's at LaSalle County Nuclear Station (LaSalle). The facility was designed to store low-level radioactive waste (LLRW) on an interim basis, i.e., up to five years. The primary reason for the IRSF was to offset lack of disposal in case existing disposal facilities, such as the Southeast Compact's Barnwell Disposal Facility in Barnwell, South Carolina, ceased accepting radioactive waste from utilities not in the Southeast Compact. Approximately ninety percent of the Radwaste projected to be stored in the LaSalle IRSF in that period of time was Class A, with the balance being Class B/C waste. On July 1, 2008 the Barnwell Disposal Facility in the Southeast Compact closed its doors to out of- compact Radwaste, which precluded LaSalle from shipping Class B/C Radwaste to an outside disposal facility. Class A waste generated by LaSalle is still able to be disposed at the 'Envirocare of Utah LLRW Disposal Complex' in Clive, Utah. Thus the need for utilizing the LaSalle IRSF for storing Class B/C Radwaste for an extended period, perhaps life-of-plant or more became apparent. Additionally, other Exelon Midwest nuclear stations located in Illinois that did not build an IRSF heretofore also needed extended Radwaste storage. In early 2009, Exelon made a decision to forward Radwaste from the Byron Nuclear Station (Byron), Braidwood Nuclear Station (Braidwood), and Clinton Nuclear Station (Clinton) to LaSalle's IRSF. As only Class B/C Radwaste would need to be forwarded to LaSalle, the original volumetric capacity of the LaSalle IRSF was capable of handling the small number of additional expected shipments annually from the Exelon sister nuclear stations in Illinois. Forwarding Class B/C Radwaste from the Exelon sister nuclear stations in Illinois to LaSalle would require an amendment to the LaSalle Station operating license. Exelon submitted the License Amendment Request

  8. NASA's Nuclear Thermal Propulsion Project

    NASA Technical Reports Server (NTRS)

    Houts, Michael; Mitchell, Sonny; Kim, Tony; Borowski, Stanley; Power, Kevin; Scott, John; Belvin, Anthony; Clement, Steven

    2015-01-01

    Space fission power systems can provide a power rich environment anywhere in the solar system, independent of available sunlight. Space fission propulsion offers the potential for enabling rapid, affordable access to any point in the solar system. One type of space fission propulsion is Nuclear Thermal Propulsion (NTP). NTP systems operate by using a fission reactor to heat hydrogen to very high temperature (>2500 K) and expanding the hot hydrogen through a supersonic nozzle. First generation NTP systems are designed to have an Isp of approximately 900 s. The high Isp of NTP enables rapid crew transfer to destinations such as Mars, and can also help reduce mission cost, improve logistics (fewer launches), and provide other benefits. However, for NTP systems to be utilized they must be affordable and viable to develop. NASA's Advanced Exploration Systems (AES) NTP project is a technology development project that will help assess the affordability and viability of NTP. Early work has included fabrication of representative graphite composite fuel element segments, coating of representative graphite composite fuel element segments, fabrication of representative cermet fuel element segments, and testing of fuel element segments in the Compact Fuel Element Environmental Tester (CFEET). Near-term activities will include testing approximately 16" fuel element segments in the Nuclear Thermal Rocket Element Environmental Simulator (NTREES), and ongoing research into improving fuel microstructure and coatings. In addition to recapturing fuels technology, affordable development, qualification, and utilization strategies must be devised. Options such as using low-enriched uranium (LEU) instead of highly-enriched uranium (HEU) are being assessed, although that option requires development of a key technology before it can be applied to NTP in the thrust range of interest. Ground test facilities will be required, especially if NTP is to be used in conjunction with high value or

  9. Enhancement of NRC station blackout requirements for nuclear power plants

    SciTech Connect

    McConnell, M. W.

    2012-07-01

    The U.S. Nuclear Regulatory Commission (NRC) established a Near-Term Task Force (NTTF) in response to Commission direction to conduct a systematic and methodical review of NRC processes and regulations to determine whether the agency should make additional improvements to its regulatory system and to make recommendations to the Commission for its policy direction, in light of the accident at the Fukushima Dai-ichi Nuclear Power Plant. The NTTF's review resulted in a set of recommendations that took a balanced approach to defense-in-depth as applied to low-likelihood, high-consequence events such as prolonged station blackout (SBO) resulting from severe natural phenomena. Part 50, Section 63, of Title 10 of the Code of Federal Regulations (CFR), 'Loss of All Alternating Current Power,' currently requires that each nuclear power plant must be able to cool the reactor core and maintain containment integrity for a specified duration of an SBO. The SBO duration and mitigation strategy for each nuclear power plant is site specific and is based on the robustness of the local transmission system and the transmission system operator's capability to restore offsite power to the nuclear power plant. With regard to SBO, the NTTF recommended that the NRC strengthen SBO mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events. The NTTF also recommended strengthening emergency preparedness for prolonged SBO and multi-unit events. These recommendations, taken together, are intended to clarify and strengthen US nuclear reactor safety regarding protection against and mitigation of the consequences of natural disasters and emergency preparedness during SBO. The focus of this paper is on the existing SBO requirements and NRC initiatives to strengthen SBO capability at all operating and new reactors to address prolonged SBO stemming from design-basis and beyond-design-basis external events. The NRC initiatives are intended to

  10. 75 FR 10517 - Nebraska Public Power District, Cooper Nuclear Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-08

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Nebraska Public Power District, Cooper Nuclear Station; Exemption 1.0 Background Nebraska Public... authorizes operation of the Cooper Nuclear Station (CNS). The license provides, among other things, that...

  11. 76 FR 39134 - ZIONSOLUTIONS, LLC; Zion Nuclear Power Station, Units 1 and 2 Exemption From Recordkeeping...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-05

    ... COMMISSION ZIONSOLUTIONS, LLC; Zion Nuclear Power Station, Units 1 and 2 Exemption From Recordkeeping Requirements 1.0 Background Zion Nuclear Power Station (ZNPS or Zion), Unit 1, is a Westinghouse 3250 MWt... licensing basis requirements previously applicable to the nuclear power units and associated...

  12. 78 FR 45984 - Yankee Atomic Electric Company, Yankee Nuclear Power Station

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-30

    ... COMMISSION Yankee Atomic Electric Company, Yankee Nuclear Power Station AGENCY: Nuclear Regulatory Commission... Atomic Electric Company (YAEC) is the holder of Possession-Only License DPR-3 for the Yankee Nuclear Power Station (YNPS) facility. The license, issued pursuant to the Atomic Energy Act of 1954, as...

  13. 75 FR 76055 - Nebraska Public Power District Cooper Nuclear Station; Notice of Issuance of Renewed Facility...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-07

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Docket No. 50-298; NRC-2008-0617] Nebraska Public Power District Cooper Nuclear Station; Notice of... operator of the Cooper Nuclear Station (CNS). Renewed facility operating license No. DPR-46...

  14. [Medical and psychological aspects of safety measures maintenance among nuclear and power station personnel].

    PubMed

    Ipatov, P L; Sorokin, A V; Basov, V I

    2004-01-01

    The article deals with 15-year experience of medical and psychophysiologic service in Medical and Sanitary Establishment No. 156 and Balakovo nuclear power station on providing reliability of occupational activities for the station personnel.

  15. Interdicting a Nuclear-Weapons Project

    DTIC Science & Technology

    2009-08-01

    every fowl of tyrant wing. Shakespeare, The Phoenix and the Turtle 1. Introduction Sixty years after the United States detonated the first nuclear...Carlyle, E. Skroch, K. Wood. 2006. Anatomy of a project to produce a first nuclear weapon. Sci. Global Security 14 163–182. International Atomic

  16. NUCLEAR SCIENCE CURRICULUM PROJECT. INSTRUCTIONAL RESOURCES SUPPLEMENT.

    ERIC Educational Resources Information Center

    Culver City Unified School District, CA.

    DESIGNED AS AN ADJUNCT TO MATERIALS DEVELOPED BY THE NUCLEAR SCIENCE CURRICULUM PROJECT, THIS DOCUMENT PROVIDES RESOURCE MATERIAL WITH WHICH THE NUCLEAR SCIENCE CURRICULUM MAY BE ENRICHED, AND ADDRESSES ITSELF TO (1) INSTRUCTIONAL AIDS PRESENTLY AVAILABLE, (2) USE OF INSTRUCTIONAL AIDS TO SUPPLEMENT THE CURRENT SCIENCE CURRICULA, (3) FACILITIES…

  17. 78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-05

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving Proposed... No. DPR-46, issued to Nebraska Public Power District (the licensee), for operation of the...

  18. Public response to the Diablo Canyon Nuclear Generating Station

    SciTech Connect

    Pijawka, K.D.

    1982-08-01

    The authors examine the nature of the public response to the Diablo Canyon Nuclear Generating Station located in San Luis Obispo, California, from the early 1960s to the present. Four distinct phases of public intervention were discerned, based on change in both plant-related issues and in the nature of the antinuclear constituencies in the region. The level of public concern varied both geographically and temporally and is related to the area's social structure, environmental predispositions, and distribution of plant-related economic benefits. External events, such as the prolonged debate over the risk assessment of the seismic hazard and the Three Mile Island accident were found to be important factors in explaining variation in public concern and political response.

  19. Installation for a nuclear power station with staggered swimming pools

    SciTech Connect

    Gigou, R.

    1982-12-28

    In an installation for a nuclear power station comprising a ''reactor building'' with a first swimming pool for handling of fuel units and a fuel building with a second swimming pool for the transfer, storage and deactivation of the units, the second swimming pool is located at a lower level than that of the first and is connected to the first by an intermediate auxiliary chamber filled with water and located under the first swimming pool. The auxiliary chamber is connected by a vertical pipeline to the first swimming pool and by a horizontal connecting pipeline to the second swimming pool. Each of the pipelines is provided with a shut-off valve, with interlocking means which prevents the simultaneous opening of the two valves. There is negligible dead space around a conveyor basket for fuel units when it is in the vertical or horizontal pipelines.

  20. Spent Nuclear Fuel Project Technical Databook

    SciTech Connect

    Reilly, M.A.

    1998-10-23

    The Spent Nuclear Fuel (SNF) Project Technical Databook is developed for use as a common authoritative source of fuel behavior and material parameters in support of the Hanford SNF Project. The Technical Databook will be revised as necessary to add parameters as their Databook submittals become available.

  1. 14. PROJECT PLAN, INTAKE PIER, RAW WATER CONDUITS, PUMPING STATION ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    14. PROJECT PLAN, INTAKE PIER, RAW WATER CONDUITS, PUMPING STATION FORCE MAINS, TREATED WATER PIPELINES, AND FILTRATION PLANT, SHEET 1 OF 117, 1920. - Sacramento River Water Treatment Plant Intake Pier & Access Bridge, Spanning Sacramento River approximately 175 feet west of eastern levee on river; roughly .5 mile downstream from confluence of Sacramento & American Rivers, Sacramento, Sacramento County, CA

  2. A Nuclear Data Project in Japan

    SciTech Connect

    Igashira, M.; Yamano, N.; Mizumoto, M.; Oshima, M.; Hasegawa, A.; Harada, H.; Yamana, H.; Baba, M.; Kato, K.; Sugawara, M.; Nagai, Y.; Kawade, K.

    2005-05-24

    A project entitled 'Fundamental R and D on Neutron Cross Sections for Innovative Reactors using Advanced Radiation Measurement Technology' was approved as one of 'Innovative Nuclear Energy System Technology Development Projects' by the Ministry of Education, Culture, Sports, Science and Technology and started in December 2002. This project consists of three R and D items: (1) the development of advanced measurement technology (2) the acquisition of neutron cross sections of minor actinides, and (3) the development of a neutron cross-section utilization system. This project will continue until March 2007 with a total budget of 770 million yen. The outline and present status of this project are briefly described.

  3. 75 FR 33366 - Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Notice of Withdrawal of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-06-11

    ... COMMISSION Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Notice of Withdrawal of..., application for amendment to Facility Operating License No. DPR-16 for the Oyster Creek Nuclear Generating Station (Oyster Creek), located in Ocean County, New Jersey. The proposed amendment would have revised...

  4. 76 FR 79227 - Exemption Request Submitted by Oyster Creek Nuclear Generating Station; Exelon Generation Company...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-21

    ... COMMISSION Exemption Request Submitted by Oyster Creek Nuclear Generating Station; Exelon Generation Company... Generation Company, LLC (the licensee), for operation of the Oyster Creek Nuclear Generating Station (Oyster... for Oyster Creek and NUREG-1437, Vol. 1, Supplement 28, ``Generic Environmental Impact Statement...

  5. 75 FR 33656 - Exelon Generation Company, LLC Oyster Creek Nuclear Generating Station Environmental Assessment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-06-14

    ... COMMISSION Exelon Generation Company, LLC Oyster Creek Nuclear Generating Station Environmental Assessment....2, as requested by Exelon Generation Company, LLC (the licensee), for operation of the Oyster Creek Nuclear Generating Station (Oyster Creek), located in Ocean County, New Jersey. Therefore, as required...

  6. 76 FR 41532 - Yankee Atomic Electric Company, Yankee Nuclear Power Station (Yankee-Rowe); Notice of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-14

    ... COMMISSION Yankee Atomic Electric Company, Yankee Nuclear Power Station (Yankee-Rowe); Notice of... indirect transfer of the Facility Operating License No. DPR-3 for the Yankee Nuclear Power Station (Yankee... Officer Powers, and General Hearing Management for NRC Adjudicatory Hearings,'' of 10 CFR part 2....

  7. 76 FR 48184 - Exelon Nuclear, Peach Bottom Atomic Power Station, Unit 1; Exemption From Certain Security...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-08

    ... COMMISSION Exelon Nuclear, Peach Bottom Atomic Power Station, Unit 1; Exemption From Certain Security... issued for Peach Bottom Atomic Power Station (PBAPS), Unit 1, located in York County, PA. PBAPS Unit 1 is... nuclear power reactors against radiological sabotage,'' paragraph (b)(1) states, ``The licensee...

  8. Conceptual planning for Space Station life sciences human research project

    NASA Technical Reports Server (NTRS)

    Primeaux, Gary R.; Miller, Ladonna J.; Michaud, Roger B.

    1986-01-01

    The Life Sciences Research Facility dedicated laboratory is currently undergoing system definition within the NASA Space Station program. Attention is presently given to the Humam Research Project portion of the Facility, in view of representative experimentation requirement scenarios and with the intention of accommodating the Facility within the Initial Operational Capability configuration of the Space Station. Such basic engineering questions as orbital and ground logistics operations and hardware maintenance/servicing requirements are addressed. Biospherics, calcium homeostasis, endocrinology, exercise physiology, hematology, immunology, muscle physiology, neurosciences, radiation effects, and reproduction and development, are among the fields of inquiry encompassed by the Facility.

  9. A Renewably Powered Hydrogen Generation and Fueling Station Community Project

    NASA Technical Reports Server (NTRS)

    Lyons, Valerie J.; Sekura, Linda S.; Prokopius, Paul; Theirl, Susan

    2009-01-01

    The proposed project goal is to encourage the use of renewable energy and clean fuel technologies for transportation and other applications while generating economic development. This can be done by creating an incubator for collaborators, and creating a manufacturing hub for the energy economy of the future by training both white- and blue-collar workers for the new energy economy. Hydrogen electrolyzer fueling stations could be mass-produced, shipped and installed in collaboration with renewable energy power stations, or installed connected to the grid with renewable power added later.

  10. 76 FR 19148 - PSEG Nuclear, LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-06

    ..., Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Mail Stop O-11F1, Washington... Nuclear Reactor Regulation. BILLING CODE 7590-01-P ... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  11. The Fukushima Nuclear Power Station incident and marine pollution.

    PubMed

    Chang, Yen-Chiang; Zhao, Yue

    2012-05-01

    Based on the facts relating to the radioactive wastewater discharged by the Fukushima Nuclear Power Station in Japan, this paper intends to explore the international legal obligations for Japan from three perspectives, namely, the immediate notification, the prevention of transboundary harm and the prevention of dumping. Furthermore, this article defines and compares two types of international legal liabilities, the traditional state responsibility and the responsibility for transboundary harm. Through comparison, the international legal liability of Japan is discussed. After detailed analysis, the conclusion is that Japan should be responsible for the obligation of immediate notification and since Japan unilaterally discharge the wastes without prior specific permits of other contracting countries, it should also be responsible for the violation of prevention of dumping. Since so far, no material injury has emerged and there would appear to be no culpability as regards the prevention of transboundary harm. Finally, this paper stresses the necessity to develop a worldwide agreement concerning the liability for transboundary harm and to establish an institutional framework for the enforcement of a state's obligations, and also the great significance of international cooperation between nations and organisations in relation to marine environmental protection.

  12. The TAHMO project: Designing an unconventional weather station

    NASA Astrophysics Data System (ADS)

    Hut, R. W.; van de Giesen, N. C.; Selker, J. S.

    2012-04-01

    The TAHMO project aims to build a 200 weather station for the African Market. This calls for an out of the box attitude towards design that looks into new and promising technologies and asks "Can this be used for TAHMO?". Already an acoustic rain gauge and a combined thermometer / radiation sensor have been developed. Those will be presented, along with a list of open research / design questions that need enthusiastic students to solve them.

  13. Interdicting a Nuclear-Weapons Project

    DTIC Science & Technology

    2007-12-04

    tyrant wing.” Shakespeare, The Phoenix and the Turtle Subject classifications: Government: defense, foreign policy; Military: targeting...Carlyle, E. Skroch, K. Wood. 2006. Anatomy of a project to produce a first nuclear weapon. Sci. & Global Security. 14 163-182. 4 December 2007 35

  14. 77 FR 2766 - Facility Operating License Amendment from Duke Energy Carolinas, LLC., Catawba Nuclear Station...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-01-19

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Facility Operating License Amendment from Duke Energy Carolinas, LLC., Catawba Nuclear Station, Units 1 and 2 AGENCY: Nuclear Regulatory Commission. ACTION: License amendment; request for comment and hearing, and order. DATES: Submit comments...

  15. Environmental impact assessment for nuclear and coal-fired power stations in Czechoslovakia

    SciTech Connect

    Lapcik, V.

    1994-12-31

    Czechoslovakia has had legislation requiring environmental impact assessment since 1992. A methodology for complex evaluation of areas with thermal and nuclear energy sources, as related to ecology and environment, was developed by the staff of the Department of Ecology in accordance with the environmental Protection act (No. 17/1992) for use by the Czech Energy Company (Prague). This methodology will serve as a handbook of environmental impact assessment for the energy industry. Chapter 1 of the handbook describes the project, including information on the site, design, and size of the thermal or nuclear power station. Chapter 2 includes the data necessary to identify and assess the main effects that the project is likely to have on the environment. Chapter 3 describes aspects of the environment likely to be affected significantly by a proposed project, including population, fauna, flora, soil, water, air, climatic factors, material assets (such as architectural and archeological heritage), landscape, and the interrelationship between the above factors. Chapter 4 summarizes the measures envisaged to prevent, reduce, and where possible, offer any significant adverse effects on the environment.

  16. Spent nuclear fuel project technical databook

    SciTech Connect

    Reilly, M.A.

    1998-07-22

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

  17. Advanced nuclear reactor public opinion project

    SciTech Connect

    Benson, B.

    1991-07-25

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

  18. Nuclear rocket propulsion technology - A joint NASA/DOE project

    NASA Technical Reports Server (NTRS)

    Clark, John S.

    1991-01-01

    NASA and the DOE have initiated critical technology development for nuclear rocket propulsion systems for SEI human and robotic missions to the moon and to Mars. The activities and project plan of the interagency project planning team in FY 1990 and 1991 are summarized. The project plan includes evolutionary technology development for both nuclear thermal and nuclear electric propulsion systems.

  19. Evaluation of Maximum Radionuclide Groundwater Concentrations for Basement Fill Model. Zion Station Restoration Project

    SciTech Connect

    Sullivan, T.

    2016-05-20

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Station (ZNPS). After decommissioning is completed, the site will contain two reactor Containment Buildings, the Fuel Handling Building and Transfer Canals, Auxiliary Building, Turbine Building, Crib House/Forebay, and a Waste Water Treatment Facility that have been demolished to a depth of 3 feet below grade. Additional below ground structures remaining will include the Main Steam Tunnels and large diameter intake and discharge pipes. These additional structures are not included in the modeling described in this report but the inventory remaining (expected to be very low) will be included with one of the structures that are modeled as designated in the Zion Station Restoration Project (ZSRP) License Termination Plan (LTP). The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

  20. Progress on the decommissioning of Zion nuclear generating station

    SciTech Connect

    Moloney, B. P.; Hess, J.

    2013-07-01

    The decommissioning of the twin 1040 MWe PWRs at Zion, near Chicago USA is a ground breaking programme. The original owner, Exelon Nuclear Corporation, transferred the full responsibility for reactor dismantling and site license termination to a subsidiary of EnergySolutions. The target end state of the Zion site for return to Exelon will be a green field with the exception of the dry fuel storage pad. In return, ZionSolutions has access to the full value of the decommissioning trust fund. There are two potential attractions of this model: lower overall cost and significant schedule acceleration. The Zion programme which commenced in September 2010 is designed to return the cleared site with an Independent Spent Fuel Storage Installation (ISFSI) pad in 2020, 12 years earlier than planned by Exelon. The overall cost, at $500 M per full size power reactor is significantly below the long run trend of $750 M+ per PWR. Implementation of the accelerated programme has been underway for nearly three years and is making good progress. The programme is characterised by numerous projects proceeding in parallel. The critical path is defined by the inspection and removal of fuel from the pond and transfer into dry fuel storage casks on the ISFSI pad and completion of RPV segmentation. Fuel loading is expected to commence in mid- 2013 with completion in late 2014. In parallel, ZionSolutions is proceeding with the segmentation of the Reactor Vessel (RV) and internals in both Units. Removal of large components from Unit 1 is underway. Numerous other projects are underway or have been completed to date. They include access openings into both containments, installation of heavy lift crane capacity, rail upgrades to support waste removal from the site, radiological characterization of facilities and equipment and numerous related tasks. As at February 2013, the programme is just ahead of schedule and within the latest budget. The paper will provide a fuller update. The first two

  1. 78 FR 11904 - Zion Nuclear Power Station, Units 1 and 2; ZionSolutions, LLC; Consideration of Indirect Transfer

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-20

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Zion Nuclear Power Station, Units 1 and 2; ZionSolutions, LLC; Consideration of Indirect Transfer AGENCY: Nuclear Regulatory Commission. ACTION: Request for license transfer; opportunity to...

  2. 78 FR 45987 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-30

    ... COMMISSION Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to the Primary Sampling System AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and combined... COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company,...

  3. 78 FR 45989 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-30

    ... COMMISSION Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to the Primary Sampling System AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and combined... COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company,...

  4. 75 FR 71467 - Exelon Nuclear Texas Holdings, LLC, Early Site Permit Application for the Victoria County Station...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-23

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Nuclear Texas Holdings, LLC, Early Site Permit Application for the Victoria County Station... Contention Preparation AGENCY: Nuclear Regulatory Commission (NRC or the Commission). ACTION: Notice...

  5. Space Station Biological Research Project: Reference Experiment Book

    NASA Technical Reports Server (NTRS)

    Johnson, Catherine (Editor); Wade, Charles (Editor)

    1996-01-01

    The Space Station Biological Research Project (SSBRP), which is the combined efforts of the Centrifuge Facility (CF) and the Gravitational Biology Facility (GBF), is responsible for the development of life sciences hardware to be used on the International Space Station to support cell, developmental, and plant biology research. The SSBRP Reference Experiment Book was developed to use as a tool for guiding this development effort. The reference experiments characterize the research interests of the international scientific community and serve to identify the hardware capabilities and support equipment needed to support such research. The reference experiments also serve as a tool for understanding the operational aspects of conducting research on board the Space Station. This material was generated by the science community by way of their responses to reference experiment solicitation packages sent to them by SSBRP scientists. The solicitation process was executed in two phases. The first phase was completed in February of 1992 and the second phase completed in November of 1995. Representing these phases, the document is subdivided into a Section 1 and a Section 2. The reference experiments contained in this document are only representative microgravity experiments. They are not intended to define actual flight experiments. Ground and flight experiments will be selected through the formal NASA Research Announcement (NRA) and Announcement of Opportunity (AO) experiment solicitation, review, and selection process.

  6. NASA's nuclear electric propulsion technology project

    NASA Technical Reports Server (NTRS)

    Stone, James R.; Sovey, James S.

    1992-01-01

    The National Aeronautics and Space Administration (NASA) has initiated a program to establish the readiness of nuclear electric propulsion (NEP) technology for relatively near-term applications to outer planet robotic science missions with potential future evolution to system for piloted Mars vehicles. This program was initiated in 1991 with a very modest effort identified with nuclear thermal propulsion (NTP); however, NEP is also an integral part of this program and builds upon NASA's Base Research and Technology Program in power and electric propulsion as well as the SP-100 space nuclear power program. The NEP Program will establish the feasibility and practicality of electric propulsion for robotic and piloted solar system exploration. The performance objectives are high specific impulse (200 greater than I(sub sp) greater than 10000 s), high efficiency (over 0.50), and low specific mass. The planning for this program was initially focussed on piloted Mars missions, but has since been redirected to first focus on 100-kW class systems for relatively near-term robotic missions, with possible future evolution to megawatt- and multi-megawatt-class systems applicable to cargo vehicles supporting human missions as well as to the piloted vehicles. This paper reviews current plans and recent progress for the overall nuclear electric propulsion project and closely related activities.

  7. NASA's nuclear electric propulsion technology project

    NASA Astrophysics Data System (ADS)

    Stone, James R.; Sovey, James S.

    1992-07-01

    The National Aeronautics and Space Administration (NASA) has initiated a program to establish the readiness of nuclear electric propulsion (NEP) technology for relatively near-term applications to outer planet robotic science missions with potential future evolution to system for piloted Mars vehicles. This program was initiated in 1991 with a very modest effort identified with nuclear thermal propulsion (NTP); however, NEP is also an integral part of this program and builds upon NASA's Base Research and Technology Program in power and electric propulsion as well as the SP-100 space nuclear power program. The NEP Program will establish the feasibility and practicality of electric propulsion for robotic and piloted solar system exploration. The performance objectives are high specific impulse (200 greater than I(sub sp) greater than 10000 s), high efficiency (over 0.50), and low specific mass. The planning for this program was initially focussed on piloted Mars missions, but has since been redirected to first focus on 100-kW class systems for relatively near-term robotic missions, with possible future evolution to megawatt- and multi-megawatt-class systems applicable to cargo vehicles supporting human missions as well as to the piloted vehicles. This paper reviews current plans and recent progress for the overall nuclear electric propulsion project and closely related activities.

  8. NASA's nuclear electric propulsion technology project

    NASA Technical Reports Server (NTRS)

    Stone, James R.; Sovey, James S.

    1992-01-01

    The National Aeronautics and Space Administration (NASA) has initiated a program to establish the readiness of nuclear electric propulsion (NEP) technology for relatively near-term applications to outer planet robotic science missions with potential future evolution to system for piloted Mars vehicles. This program was initiated in 1991 with a very modest effort identified with nuclear thermal propulsion (NTP); however, NEP is also an integral part of this program and builds upon NASA's Base Research and Technology Program in power and electric propulsion as well as the SP-100 space nuclear power program. The NEP Program will establish the feasibility and practicality of electric propulsion for robotic and piloted solar system exploration. The performance objectives are high specific impulse (200 greater than I(sub sp) greater than 10000 s), high efficiency (over 0.50), and low specific mass. The planning for this program was initially focussed on piloted Mars missions, but has since been redirected to first focus on 100-kW class systems for relatively near-term robotic missions, with possible future evolution to megawatt-and multi-megawatt-class systems applicable to cargo vehicles supporting human missions as well as to the piloted vehicles. This paper reviews current plans and recent progress for the overall nuclear electric propulsion project and closely related activities.

  9. NASA's nuclear electric propulsion technology project

    NASA Astrophysics Data System (ADS)

    Stone, James R.; Sovey, James S.

    1992-07-01

    The National Aeronautics and Space Administration (NASA) has initiated a program to establish the readiness of nuclear electric propulsion (NEP) technology for relatively near-term applications to outer planet robotic science missions with potential future evolution to system for piloted Mars vehicles. This program was initiated in 1991 with a very modest effort identified with nuclear thermal propulsion (NTP); however, NEP is also an integral part of this program and builds upon NASA's Base Research and Technology Program in power and electric propulsion as well as the SP-100 space nuclear power program. The NEP Program will establish the feasibility and practicality of electric propulsion for robotic and piloted solar system exploration. The performance objectives are high specific impulse (200 greater than I(sub sp) greater than 10000 s), high efficiency (over 0.50), and low specific mass. The planning for this program was initially focussed on piloted Mars missions, but has since been redirected to first focus on 100-kW class systems for relatively near-term robotic missions, with possible future evolution to megawatt-and multi-megawatt-class systems applicable to cargo vehicles supporting human missions as well as to the piloted vehicles. This paper reviews current plans and recent progress for the overall nuclear electric propulsion project and closely related activities.

  10. A feasibility assessment of nuclear reactor power system concepts for the NASA Growth Space Station

    NASA Technical Reports Server (NTRS)

    Bloomfield, H. S.; Heller, J. A.

    1986-01-01

    A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth Space Station architecture was conducted to address a variety of installation, operational, disposition and safety issues. A previous NASA sponsored study, which showed the advantages of Space Station - attached concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide a feasibility of each combination.

  11. 78 FR 29158 - In the Matter of Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Order Approving...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-17

    ... Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Order Approving Indirect Transfer of... Nuclear Power Station, Units 1 and 2 (ZNPS) in Zion, Illinois. II. By letter dated January 10, 2013, ZS... Power Station, Units 1 and 2 held by ZS, including the General License for the Zion Independent...

  12. Overview of the regulatory framework applying to nuclear power stations of France

    SciTech Connect

    Astolfi, J.F.

    1993-12-31

    The achievement of French nuclear power plants, because France has not yet issued a specific nuclear law and is tied to a very complex regulatory structure, is submitted to a large number of prior authorizations, which are issued either at a national level or by local authorities according to their goals and importance. This report will outline the regulatory framework applying to nuclear power stations in France.

  13. Review of Cytogenetic analysis of restoration workers for Fukushima Daiichi nuclear power station accident.

    PubMed

    Suto, Yumiko

    2016-09-01

    Japan faced with the nuclear accident of the Fukushima Daiichi Nuclear Power Station (NPS) caused by the combined disaster of the Great East Japan Earthquake and the subsequent tsunamis on 11 March 2011. National Institute of Radiological Sciences received all nuclear workers who were engaged in emergency response tasks at the NPS and suspected of being overexposed to acute radiation. Biological dosimetry by dicentric chromosome assay was helpful for medical triage and management of the workers.

  14. Project EGRESS: Earthbound Guaranteed Reentry from Space Station. the Design of an Assured Crew Recovery Vehicle for the Space Station

    NASA Technical Reports Server (NTRS)

    1990-01-01

    Unlike previously designed space-based working environments, the shuttle orbiter servicing the space station will not remain docked the entire time the station is occupied. While an Apollo capsule was permanently available on Skylab, plans for Space Station Freedom call for a shuttle orbiter to be docked at the space station for no more than two weeks four times each year. Consideration of crew safety inspired the design of an Assured Crew Recovery Vehicle (ACRV). A conceptual design of an ACRV was developed. The system allows the escape of one or more crew members from Space Station Freedom in case of emergency. The design of the vehicle addresses propulsion, orbital operations, reentry, landing and recovery, power and communication, and life support. In light of recent modifications in space station design, Project EGRESS (Earthbound Guaranteed ReEntry from Space Station) pays particular attention to its impact on space station operations, interfaces and docking facilities, and maintenance needs. A water-landing medium-lift vehicle was found to best satisfy project goals of simplicity and cost efficiency without sacrificing safety and reliability requirements. One or more seriously injured crew members could be returned to an earth-based health facility with minimal pilot involvement. Since the craft is capable of returning up to five crew members, two such permanently docked vehicles would allow a full evacuation of the space station. The craft could be constructed entirely with available 1990 technology, and launched aboard a shuttle orbiter.

  15. The Los Alamos National Laboratory Nuclear Vision Project

    SciTech Connect

    Arthur, E.D.; Wagner, R.L. Jr.

    1996-09-01

    Los Alamos National Laboratory has initiated a project to examine possible futures associated with the global nuclear enterprise over the course of the next 50 years. All major components are included in this study--weapons, nonproliferation, nuclear power, nuclear materials, and institutional and public factors. To examine key issues, the project has been organized around three main activity areas--workshops, research and analyses, and development of linkages with other synergistic world efforts. This paper describes the effort--its current and planned activities--as well as provides discussion of project perspectives on nuclear weapons, nonproliferation, nuclear energy, and nuclear materials focus areas.

  16. H2FIRST Reference Station Design Task: Project Deliverable 2-2

    SciTech Connect

    Pratt, Joseph; Terlip, Danny; Ainscough, Chris; Kurtz, Jennifer; Elgowainy, Amgad

    2015-04-20

    This report presents near-term station cost results and discusses cost trends of different station types. It compares various vehicle rollout scenarios and projects realistic near-term station utilization values using the station infrastructure rollout in California as an example. It describes near-term market demands and matches those to cost-effective station concepts. Finally, the report contains detailed designs for five selected stations, which include piping and instrumentation diagrams, bills of materials, and several site-specific layout studies that incorporate the setbacks required by NFPA 2, the National Fire Protection Association Hydrogen Technologies Code. This work identified those setbacks as a significant factor affecting the ability to site a hydrogen station, particularly liquid stations at existing gasoline stations. For all station types, utilization has a large influence on the financial viability of the station.

  17. Segmentation of the reactor internals at the Yankee Nuclear Power Station

    SciTech Connect

    Child, C.L.

    1995-10-01

    The Yankee Nuclear Power Station (YNPS) first achieved criticality on August 19, 1960. Located in Rowe, Massachusetts, Yankee was the third commercial power plant licensed in the US. During its lifetime, this 185 MWe plant had a capacity factor of 74%--over ten points higher than the US nuclear industry average at that time. On February 26, 1992, faced with escalating costs and a general decline in power demands in the Northeast, the Yankee Atomic Electric Company announced the permanent shut down of Yankee Rowe. Even after shutdown, the Yankee tradition of pioneering and innovation has continued. Prompted by South Carolina`s decision to extend access to the Barnwell, South Carolina, waste management facility through June 1994 to out-of compact states, Yankee initiated an innovative program to remove reactor internals, steam generators, and the pressurizer. Yankee realized that removal of these components could be completed safely using existing programs and procedures. The project would save the ratepayers several millions of dollars compared to deferring removal until after the year 2000. Yankee management approved execution of the Component Removal Program in March, 1993.

  18. 75 FR 13801 - Exelon Generation Company, LLC; Zion Nuclear Power Station, Units 1 and 2; Order Extending the...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-23

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY... Company, LLC; Zion Nuclear Power Station, Units 1 and 2; Order Extending the Effectiveness of the Approval... holder of licenses DPR-39 and DPR-48, for the Zion Nuclear Power Station, Units 1 and 2 (Zion...

  19. 78 FR 63504 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Changes to the...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-24

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Changes to the... Cooper) (the licensee), for construction and operation of the Virgil C. Summer Nuclear Station...

  20. 75 FR 12312 - South Carolina Electric and Gas Company; Virgil C. Summer Nuclear Station, Unit 1; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-15

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION South Carolina Electric and Gas Company; Virgil C. Summer Nuclear Station, Unit 1; Exemption 1.0... Operating License No. NPF-12 which authorizes operation of the Virgil C. Summer Nuclear Station, Unit...

  1. 77 FR 49463 - Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3; Application and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-16

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3; Application and... Edison Company (SCE, the licensee) for operation of the San Onofre Nuclear Generating Station...

  2. 77 FR 11168 - In the Matter of Exelon Corporation; Constellation Energy Group, Inc.; Nine Mile Nuclear Station...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-24

    ... and the indirect license transfers. Constellation Energy Nuclear Group, LLC, shall inform the NRC in... Exelon Corporation; Constellation Energy Group, Inc.; Nine Mile Nuclear Station, LLC; Nine Mile Point... Indirect Transfer of Licenses I Nine Mile Point Nuclear Station, LLC (NMPNS, LLC, or the licensee) is...

  3. 75 FR 13606 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-22

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3... Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS, Units 1, 2, and 3), located...

  4. Natural Disasters and Safety Risks at Nuclear Power Stations

    NASA Astrophysics Data System (ADS)

    Tutnova, T.

    2012-04-01

    In the aftermath of Fukushima natural-technological disaster the global opinion on nuclear energy divided even deeper. While Germany, Italy and the USA are currently reevaluating their previous plans on nuclear growth, many states are committed to expand nuclear energy output. In China and France, where the industry is widely supported by policymakers, there is little talk about abandoning further development of nuclear energy. Moreover, China displays the most remarkable pace of nuclear development in the world: it is responsible for 40% of worldwide reactors under construction, and aims at least to quadruple its nuclear capacity by 2020. In these states the consequences of Fukushima natural-technological accident will probably result in safety checks and advancement of new reactor technologies. Thus, China is buying newer reactor design from the USA which relies on "passive safety systems". It means that emergency power generators, crucial for reactor cooling in case of an accident, won't depend on electricity, so that tsunami won't disable them like it happened in the case of Fukushima. Nuclear energy managed to draw lessons from previous nuclear accidents where technological and human factors played crucial role. But the Fukushima lesson shows that the natural hazards, nevertheless, were undervalued. Though the ongoing technological advancements make it possible to increase the safety of nuclear power plants with consideration of natural risks, it is not just a question of technology improvement. A necessary action that must be taken is the reevaluation of the character and sources of the potential hazards which natural disasters can bring to nuclear industry. One of the examples is a devastating impact of more than one natural disaster happening at the same time. This subject, in fact, was not taken into account before, while it must be a significant point in planning sites for new nuclear power plants. Another important lesson unveiled is that world nuclear

  5. Spacelab, Spacehab, and Space Station Freedom payload interface projects

    NASA Technical Reports Server (NTRS)

    Smith, Dean Lance

    1992-01-01

    Contributions were made to several projects. Howard Nguyen was assisted in developing the Space Station RPS (Rack Power Supply). The RPS is a computer controlled power supply that helps test equipment used for experiments before the equipment is installed on Space Station Freedom. Ron Bennett of General Electric Government Services was assisted in the design and analysis of the Standard Interface Rack Controller hardware and software. An analysis was made of the GPIB (General Purpose Interface Bus), looking for any potential problems while transmitting data across the bus, such as the interaction of the bus controller with a data talker and its listeners. An analysis was made of GPIB bus communications in general, including any negative impact the bus may have on transmitting data back to Earth. A study was made of transmitting digital data back to Earth over a video channel. A report was written about the study and a revised version of the report will be submitted for publication. Work was started on the design of a PC/AT compatible circuit board that will combine digital data with a video signal. Another PC/AT compatible circuit board is being designed to recover the digital data from the video signal. A proposal was submitted to support the continued development of the interface boards after the author returns to Memphis State University in the fall. A study was also made of storing circuit board design software and data on the hard disk server of a LAN (Local Area Network) that connects several IBM style PCs. A report was written that makes several recommendations. A preliminary design review was started of the AIVS (Automatic Interface Verification System). The summer was over before any significant contribution could be made to this project.

  6. 78 FR 44603 - Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2; Exelon...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-24

    ... Generation Company, LLC AGENCY: Nuclear Regulatory Commission. ACTION: License renewal application; notice of...-37, NPF-66, NPF- 72, and NPF-77, which authorize Exelon Generation Company, LLC (Exelon), to...

  7. NASA Growth Space Station missions and candidate nuclear/solar power systems

    NASA Technical Reports Server (NTRS)

    Heller, Jack A.; Nainiger, Joseph J.

    1987-01-01

    A brief summary is presented of a NASA study contract and in-house investigation on Growth Space Station missions and appropriate nuclear and solar space electric power systems. By the year 2000 some 300 kWe will be needed for missions and housekeeping power for a 12 to 18 person Station crew. Several Space Station configurations employing nuclear reactor power systems are discussed, including shielding requirements and power transmission schemes. Advantages of reactor power include a greatly simplified Station orientation procedure, greatly reduced occultation of views of the earth and deep space, near elimination of energy storage requirements, and significantly reduced station-keeping propellant mass due to very low drag of the reactor power system. The in-house studies of viable alternative Growth Space Station power systems showed that at 300 kWe a rigid silicon solar cell array with NiCd batteries had the highest specific mass at 275 kg/kWe, with solar Stirling the lowest at 40 kg/kWe. However, when 10 year propellant mass requirements are factored in, the 300 kWe nuclear Stirling exhibits the lowest total mass.

  8. Project Planning Resulted in Outstanding Building Deficiencies and Decreased Functionality of the Main Fire Station at Naval Station Great Lakes

    DTIC Science & Technology

    2012-09-14

    emergency medical technicians5 to the main fire station. The scope of the project also included replacing the roofing, insulation, doors, fire sprinklers ...emergency lighting, and fire alarms. In addition, the scope included repairing water and wastewater piping and mechanical systems to meet...rooms, alert systems , and dorm rooms. PPE Storage Was Inadequate The storage area for PPE in the fire station did not comply with the

  9. 78 FR 27260 - Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3 Request for Action

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-09

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3 Request for... Southern California Edison (SCE) to ] submit a license amendment application for the design...

  10. Surveys of Food Intake Just after the Nuclear Accident at the Fukushima Daiichi Nuclear Power Station.

    PubMed

    Hirakawa, Sachiko; Yoshizawa, Nobuaki; Murakami, Kana; Takizawa, Mari; Kawai, Masaki; Sato, Osamu; Takagi, Shunji; Suzuki, Gen

    2017-01-01

    As a result of the nuclear accident at the Fukushima Daiichi nuclear power station (FDNPS) after the Great East Japan Earthquake on March 11, 2011, volatile radionuclides including iodine-131 were released into the environment and contaminated open-field vegetables, raw milk, tap water, etc. It is important for the health care of residents to correctly comprehend the level of their exposure to radioactive substances released following the accident. However, an evaluation of the internal exposure doses of residents of Fukushima Prefecture as a result of the ingestion of foods, which is indicated in the report issued by United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR)1 is based on a number of assumptions. For instance, the estimation assumes that foods were ingested as usual, without regard to the places to which residents were evacuated after the accident, the places where food shipment restrictions were imposed, and so forth. The present report aims to improve the accuracy of estimation of the amount of food actually ingested at evacuation areas, in order to reduce as much as possible the level of uncertainty in conventional values estimated directly after the accident, which were in fact values based on conservative assumptions. More concretely, as basic source material to more accurately estimate internal exposure doses from food ingestion, various patterns of evacuation and dietary habits at the time of the accident of the residents of 13 municipalities in Fukushima Prefecture who were evacuated during the period from directly after the accident of March 11, 2011 until the end of March are clarified in this report. From survey results, most of the food that evacuees took immediately after the accident was confirmed to have been sourced from either stockpiles prepared before the accident, or relief supplies from outside of the affected areas. The restriction orders of food supplies such as contaminated vegetables and milk, and tap

  11. Ultrafiltration treatment for liquid laundry wastes from nuclear power stations

    SciTech Connect

    Kichik, V.A.; Maslova, M.N.; Svittsov, A.A.; Kuleshov, N.F.

    1988-03-01

    The authors conduct a comprehensive analysis of the waste constituents--radioactive and organic--of the laundry water resulting from the on-site laundering and decontamination of clothing worn in nuclear power plants. The primary isotope contaminants consist of niobium and zirconium 95, manganese 54, cobalt 60, iron 59, and cesium 134 and 137. A variety of filter and adsorbent materials used in an ultrafiltration process are comparatively tested for their effectiveness in removing not only these isotopes but also the organic contaminants in the process of recycling the water. Those materials consist of copper hexacyanoferrate, polyacrylophosphonic acid, and several metal-polymer complexes.

  12. ALARA Overview System at Crystal River Unit 3 Nuclear Station.

    PubMed

    Kline, K B; Cope, W B

    1995-08-01

    During the Spring of 1994 the Health Physics Department at Florida Power Company used video and audio equipment to support remote health physics coverage for their Crystal River Unit 3 refueling outage (Refuel 9). The system consisted of eight cameras with audio interface linked to a control center located in a low-dose area. The system allowed health physics personnel to monitor steam generator and refueling activities with minimum exposure in high-dose areas, cutting by half the dose from the previous outage. B&W Nuclear Technologies provided complete setup, maintenance and tear-down, as well as assuming responsibilities for contaminated video and audio equipment.

  13. In situ monitoring of animal micronuclei before the operation of Daya Bay Nuclear Power Station

    SciTech Connect

    Y.N. Cai; H.Y. He; L.M. Qian; G.C. Sun; J.Y. Zhao

    1994-12-31

    Daya Bay Nuclear Power Station, a newly-built nuclear power station in southern mainland China, started its operation in 1993. We examined micro-nucleated cells of Invertibrate (Bivalves) and Vertibrate (Fish and Amphibia) in different spots within the 50km surroundings of the Power Station during 1986-1993. This paper reports the results of the investigation carried out in Dong Shan, a place 4.7km to the Power Station:Bivalves; Pteria martensil 5.1(1986),4.8(1988),4.8(1991),5,0(1993),Mytilus smardinus 4.7(1987),4.6(1988); Chamys nobilis 4.9(1987);4.9(1991),4.5(1992),4.5(1993). Fish; Therapon jarbua 0.48(1991),0.67(1992),0.47(1993). Amphibia; Bufo melanostictus 0.29 (1987), 0.34(1988),0.39(1992),0.39(1993). These results showed that the environmental situation, estimated by using the frequencies of micronucleated cells, was stable-there was no obvious chromosome damage in the animals studied. It was found that the incidence of micronucleated cells of Bivalves was higher than that of Fish and Amphibia, suggesting the epithelial cells to be more sensitive than peripheral erythrocytes to environmental genotoxic effects. The results of our studies for other spots will be reported afterward. These data can be used as the original background information to monitor the environment when the Nuclear Power Station is in operation.

  14. The TOMAS software system for approximate analysis of emergency situations at nuclear power stations

    NASA Astrophysics Data System (ADS)

    Zhukavin, A. P.

    2009-05-01

    The TOMAS software system for carrying out prompt analysis of different emergency situations in power units of nuclear power stations equipped with VVER-1000 and RBMK-1000 reactors is described. This software system can be used by experts of crisis centers for evaluating various situations, as well as for teaching students in higher schools specializing in the appropriate disciplines.

  15. 78 FR 28005 - System Energy Resources, Inc.; Grand Gulf Nuclear Station; Order Approving Direct and Indirect...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-13

    ... COMMISSION System Energy Resources, Inc.; Grand Gulf Nuclear Station; Order Approving Direct and Indirect Transfers of Early Site Permit and Approving Conforming Amendment I System Energy Resources, Inc. (SERI), is... direct transfer of Grand Gulf ESP Site, to a new limited liability company, System Energy Resource,...

  16. Reactor Vessel and Reactor Vessel Internals Segmentation at Zion Nuclear Power Station - 13230

    SciTech Connect

    Cooke, Conrad; Spann, Holger

    2013-07-01

    Zion Nuclear Power Station (ZNPS) is a dual-unit Pressurized Water Reactor (PWR) nuclear power plant located on the Lake Michigan shoreline, in the city of Zion, Illinois approximately 64 km (40 miles) north of Chicago, Illinois and 67 km (42 miles) south of Milwaukee, Wisconsin. Each PWR is of the Westinghouse design and had a generation capacity of 1040 MW. Exelon Corporation operated both reactors with the first unit starting production of power in 1973 and the second unit coming on line in 1974. The operation of both reactors ceased in 1996/1997. In 2010 the Nuclear Regulatory Commission approved the transfer of Exelon Corporation's license to ZionSolutions, the Long Term Stewardship subsidiary of EnergySolutions responsible for the decommissioning of ZNPS. In October 2010, ZionSolutions awarded Siempelkamp Nuclear Services, Inc. (SNS) the contract to plan, segment, remove, and package both reactor vessels and their respective internals. This presentation discusses the tools employed by SNS to remove and segment the Reactor Vessel Internals (RVI) and Reactor Vessels (RV) and conveys the recent progress. SNS's mechanical segmentation tooling includes the C-HORCE (Circumferential Hydraulically Operated Cutting Equipment), BMT (Bolt Milling Tool), FaST (Former Attachment Severing Tool) and the VRS (Volume Reduction Station). Thermal segmentation of the reactor vessels will be accomplished using an Oxygen- Propane cutting system. The tools for internals segmentation were designed by SNS using their experience from other successful reactor and large component decommissioning and demolition (D and D) projects in the US. All of the designs allow for the mechanical segmentation of the internals remotely in the water-filled reactor cavities. The C-HORCE is designed to saw seven circumferential cuts through the Core Barrel and Thermal Shield walls with individual thicknesses up to 100 mm (4 inches). The BMT is designed to remove the bolts that fasten the Baffle Plates to

  17. 75 FR 6071 - Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station Units 2 and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-05

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station Units 2 and 3... Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and...

  18. 76 FR 25378 - Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station, Units 2 and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-04

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station, Units 2 and... Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, located...

  19. 77 FR 21593 - V. C. Summer Nuclear Station, Units 2 and 3 Combined Licenses and Record of Decision

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-10

    ... COMMISSION V. C. Summer Nuclear Station, Units 2 and 3 Combined Licenses and Record of Decision AGENCY... Evaluation Report for Combined Licenses for Virgil C. Summer Nuclear Station, Units 2 and 3'' ML11098A044 NUREG-1939, Vol 1, ``Final Environmental Impact Statement for Combined Licenses for Virgil C....

  20. 78 FR 40200 - Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-03

    ... COMMISSION Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...) for an exemption request submitted by Duke Energy Carolinas, LLC, on August 13, 2012 for the Oconee Nuclear Station Independent Spent Fuel Storage Facility (ISFSI). ] ADDRESSES: Please refer to Docket...

  1. 76 FR 24064 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-29

    ... COMMISSION [Docket Nos. 50-528, 50-529, 50-530; NRC-2009-0012 Arizona Public Service Company, Palo Verde... of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS). Renewed Facility Operating... Palo Verde Nuclear Generating Station,'' issued January 2011, discusses the Commission's...

  2. 75 FR 8149 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-23

    ... COMMISSION Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3... Verde Nuclear Generating Station (PVNGS, the facility), Units 1, 2, and 3, respectively, located in... different resources than those previously considered in the Final Environmental Statement for the Palo...

  3. Childhood cancer mortality in relation to the St Lucie nuclear power station.

    PubMed

    Boice, John D; Mumma, Michael T; Blot, William J; Heath, Clark W

    2005-09-01

    An unusual county-wide excess of childhood cancers of brain and other nervous tissue in the late 1990s in St Lucie County, Florida, prompted the Florida Department of Health to conduct a case-control study within the county assessing residential chemical exposures. No clear associations were found, but claims were then made that the release of radioactive substances such as strontium 90 from the St Lucie nuclear power station, which began operating in 1976, might have played a role. To test the plausibility of this hypothesis, we extended by 17 years a previous study of county mortality conducted by the National Cancer Institute. Rates of total cancer, leukaemia and cancer of brain and other nervous tissue in children and across all ages in St Lucie County were evaluated with respect to the years before and after the nuclear power station began operation and contrasted with rates in two similar counties in Florida (Polk and Volusia). Over the prolonged period 1950-2000, no unusual patterns of childhood cancer mortality were found for St Lucie County as a whole. In particular, no unusual patterns of childhood cancer mortality were seen in relation to the start-up of the St Lucie nuclear power station in 1976. Further, there were no significant differences in mortality between the study and comparison counties for any cancer in the time period after the power station was in operation. Relative rates for all childhood cancers and for childhood leukaemia were higher before the nuclear facility began operating than after, while rates of brain and other nervous tissue cancer were slightly lower in St Lucie County than in the two comparison counties for both time periods. Although definitive conclusions cannot be drawn from descriptive studies, these data provide no support for the hypothesis that the operation of the St Lucie nuclear power station has adversely affected the cancer mortality experience of county residents.

  4. Accident at the Fukushima Dai-ichi nuclear power stations of TEPCO--outline & lessons learned.

    PubMed

    Tanaka, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others.

  5. Sodium coolant purification systems for a nuclear power station equipped with a BN-1200 reactor

    NASA Astrophysics Data System (ADS)

    Alekseev, V. V.; Kovalev, Yu. P.; Kalyakin, S. G.; Kozlov, F. A.; Kumaev, V. Ya.; Kondrat'ev, A. S.; Matyukhin, V. V.; Pirogov, E. P.; Sergeev, G. P.; Sorokin, A. P.; Torbenkova, I. Yu.

    2013-05-01

    Both traditional coolant purification methods (by means of traps and sorbents for removing cesium), the use of which supported successful operation of nuclear power installations equipped with fast-neutron reactors with a sodium coolant, and the possibility of removing oxygen from sodium through the use of hot traps are analyzed in substantiating the purification system for a nuclear power station equipped with a BN-1200 reactor. It is shown that a cold trap built into the reactor vessel must be a mandatory component of the reactor plant primary coolant circuit's purification system. The use of hot traps allows oxygen to be removed from the sodium coolant down to permissible concentrations when the nuclear power station operates in its rated mode. The main lines of works aimed at improving the performance characteristics of cold traps are suggested based on the results of performed investigations.

  6. The Next Generation Nuclear Plant (NGNP) Project

    SciTech Connect

    F. H. Southworth; P. E. MacDonald

    2003-11-01

    The Next Generation Nuclear Power (NGNP) Project will demonstrate emissions-free nuclearassisted electricity and hydrogen production by 2015. The NGNP reactor will be a helium-cooled, graphite moderated, thermal neutron spectrum reactor with a design goal outlet temperature of 1000 C or higher. The reactor thermal power and core configuration will be designed to assure passive decay heat removal without fuel damage during hypothetical accidents. The fuel cycle will be a once-through very high burnup low-enriched uranium fuel cycle. This paper provides a description of the project to build the NGNP at the Idaho National Engineering and Environmental Laboratory (INEEL). The NGNP Project includes an overall reactor design activity and four major supporting activities: materials selection and qualification, NRC licensing and regulatory support, fuel development and qualification, and the hydrogen production plant. Each of these activities is discussed in the paper. All the reactor design and construction activities will be managed under the DOE’s project management system as outlined in DOE Order 413.3. The key elements of the overall project management system discussed in this paper include the client and project management organization relationship, critical decisions (CDs), acquisition strategy, and the project logic and timeline. The major activities associated with the materials program include development of a plan for managing the selection and qualification of all component materials required for the NGNP; identification of specific materials alternatives for each system component; evaluation of the needed testing, code work, and analysis required to qualify each identified material; preliminary selection of component materials; irradiation of needed sample materials; physical, mechanical, and chemical testing of unirradiated and irradiated materials; and documentation of final materials selections. The NGNP will be licensed by the NRC under 10 CFR 50 or 10

  7. Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations

    SciTech Connect

    Wittenbrock, N. G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated

  8. Development of Standard Station Interface for Comprehensive Nuclear Test Ban Treaty Organistation Monitoring Networks

    NASA Astrophysics Data System (ADS)

    Dricker, I. G.; Friberg, P.; Hellman, S.

    2001-12-01

    Under the contract with the CTBTO, Instrumental Software Technologies Inc., (ISTI) has designed and developed a Standard Station Interface (SSI) - a set of executable programs and application programming interface libraries for acquisition, authentication, archiving and telemetry of seismic and infrasound data for stations of the CTBTO nuclear monitoring network. SSI (written in C) is fully supported under both the Solaris and Linux operating systems and will be shipped with fully documented source code. SSI consists of several interconnected modules. The Digitizer Interface Module maintains a near-real-time data flow between multiple digitizers and the SSI. The Disk Buffer Module is responsible for local data archival. The Station Key Management Module is a low-level tool for data authentication and verification of incoming signatures. The Data Transmission Module supports packetized near-real-time data transmission from the primary CTBTO stations to the designated Data Center. The AutoDRM module allows transport of seismic and infrasound signed data via electronic mail (auxiliary station mode). The Command Interface Module is used to pass the remote commands to the digitizers and other modules of SSI. A station operator has access to the state-of-health information and waveforms via an the Operator Interface Module. Modular design of SSI will allow painless extension of the software system within and outside the boundaries of CTBTO station requirements. Currently an alpha version of SSI undergoes extensive tests in the lab and onsite.

  9. Hanford spent nuclear fuel project update

    SciTech Connect

    Williams, N.H.

    1997-08-19

    Twenty one hundred metric tons of spent nuclear fuel (SNF) are currently stored in the Hanford Site K Basins near the Columbia River. The deteriorating conditions of the fuel and the basins provide engineering and management challenges to assure safe current and future storage. DE and S Hanford, Inc., part of the Fluor Daniel Hanford, Inc. lead team on the Project Hanford Management Contract, is constructing facilities and systems to move the fuel from current pool storage to a dry interim storage facility away from the Columbia River, and to treat and dispose of K Basins sludge, debris and water. The process starts in K Basins where fuel elements will be removed from existing canisters, washed, and separated from sludge and scrap fuel pieces. Fuel elements will be placed in baskets and loaded into Multi-Canister Overpacks (MCOs) and into transportation casks. The MCO and cask will be transported to the Cold Vacuum Drying Facility, where free water within the MCO will be removed under vacuum at slightly elevated temperatures. The MCOs will be sealed and transported via the transport cask to the Canister Storage Building.

  10. Nuclear monitoring research and development project. Final report, November 1991-March 1996

    SciTech Connect

    Sereno, T.J.

    1996-03-01

    This final report covers the period November 1991 through March 1996. This project is a follow on to a previous project to develop the next generation system for nuclear explosion monitoring called the Intelligent Monitoring System or IMS. It exploits emerging technologies in artificial intelligence, distributed computing, data management, and computer graphics. Under this contract, the IMS was extended by adding data from many new stations and station types, improving the event identification capabilities, and extending the knowledge acquisition subsystem and adding new region-specific knowledge. Other tasks included development of software and documentation to enhance the productivity of other research projects funded by ARPA, demonstration of a capability to transfer NMRD technology to other problem domains, assessment of the detection and location capability of hypothetical networks, and integration of data from the AFTAC Distributed Subsurface Network (ADSN) with data from the IMS.

  11. Computational nuclear quantum many-body problem: The UNEDF project

    SciTech Connect

    Fann, George I

    2013-01-01

    The UNEDF project was a large-scale collaborative effort that applied high-performance computing to the nuclear quantum many-body problem. The primary focus of the project was on constructing, validating, and applying an optimized nuclear energy density functional, which entailed a wide range of pioneering developments in microscopic nuclear structure and reactions, algorithms, high-performance computing, and uncertainty quantification. UNEDF demonstrated that close associations among nuclear physicists, mathematicians, and computer scientists can lead to novel physics outcomes built on algorithmic innovations and computational developments. This review showcases a wide range of UNEDF science results to illustrate this interplay.

  12. Spent nuclear fuel project design basis capacity study

    SciTech Connect

    Cleveland, K.J.

    1996-09-09

    A parametric study of the Spent Nuclear Fuel Project system capacity is presented. The study was completed using a commercially available software package to develop a summary level model of the major project systems. Alternative configurations, sub-system cycle times, and operating scenarios were tested to identify their impact on total project duration and equipment requirements.

  13. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    SciTech Connect

    PICKETT, W.W.

    2000-09-22

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure.

  14. 78 FR 50455 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Changes to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-19

    ... COMMISSION Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Changes to the Chemical Volume Control System AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and... NPF-92. The COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power...

  15. 78 FR 41805 - In the Matter of FirstEnergy Nuclear Operating Company; Beaver Valley Power Station; Independent...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-11

    ... COMMISSION In the Matter of FirstEnergy Nuclear Operating Company; Beaver Valley Power Station; Independent Spent Fuel Storage Installation; Order Modifying License (Effective Immediately) AGENCY: Nuclear... fingerprinting for unescorted access to FirstEnergy Nuclear Operating Company. FOR FURTHER INFORMATION CONTACT:...

  16. 75 FR 8757 - Nebraska Public Power District, Cooper Nuclear Station, Unit 1; Notice of Availability of the...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-25

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Nebraska Public Power District, Cooper Nuclear Station, Unit 1; Notice of Availability of the Draft Supplement 41 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants, and Public Meetings for The License Renewal...

  17. Chernobyl Doses. Volume 3. Habitat and Vegetation Near the Chernobyl Nuclear Reactor Station

    DTIC Science & Technology

    1993-01-01

    AD-A260 167 A lexandria, VA 22310-3398 l,* Defense Nuclear Agency Alexandria, VA 22310-.3398 DNA-TR-92-37-V3 Chernobyl Doses, Volume 3-Habitat and...Vegetation Near the Chernobyl Nuclear Reactor Station DTIC~ ELECTF. Elizabeth L. Painter i IN•9 199EIF F. Ward Whicker JAN % 93f Pacific-Sierra...930101 Technical 870929- 920228 4. TITLE AND SUBTITLE 5. FUNDING NUMBERS Chernobyl Doses C - DNA 001-87-C-0104 Volume 3-Habitat and Vegetation Near the

  18. Benefits of 20 kHz PMAD in a nuclear space station

    NASA Technical Reports Server (NTRS)

    Sundberg, Gale R.

    1987-01-01

    Compared to existing systems, high frequency ac power provides higher efficiency, lower cost, and improved safety benefits. The 20 kHz power system has exceptional flexibility, is inherently user friendly, and is compatible with all types of energy sources; photovoltaic, solar dynamic, rotating machines and nuclear. A 25 kW, 20 kHz ac power distribution system testbed was recently (1986) developed. The testbed possesses maximum flexibility, versatility, and transparency to user technology while maintaining high efficiency, low mass, and reduced volume. Several aspects of the 20 kHz power management and distribution (PMAD) system that have particular benefits for a nuclear power Space Station are discussed.

  19. Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams

    SciTech Connect

    Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

    1993-02-01

    Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., {sup 108m}Ag, {sup 93}Mo, {sup 36}Cl, {sup 10}Be, {sup 113m}Cd, {sup 121m}Sn, {sup 126}Sn, {sup 93m}Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., {sup 14}C, {sup 129}I, and {sup 99}Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC`s understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments.

  20. Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams

    SciTech Connect

    Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

    1993-02-01

    Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., [sup 108m]Ag, [sup 93]Mo, [sup 36]Cl, [sup 10]Be, [sup 113m]Cd, [sup 121m]Sn, [sup 126]Sn, [sup 93m]Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., [sup 14]C, [sup 129]I, and [sup 99]Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC's understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments.

  1. Fuel Retrieval Sub Project (FRS) Stuck Fuel Station Performance Test Data Report

    SciTech Connect

    THIELGES, J.R.

    2000-02-23

    This document provides the test data report for Stuck Fuel Station Performance Testing in support of the Fuel Retrieval Sub-Project. The stuck fuel station was designed to provide a means of cutting open a canister barrel to release fuel elements, etc.

  2. Implicit attitudes toward nuclear power and mobile phone base stations: support for the affect heuristic.

    PubMed

    Siegrist, Michael; Keller, Carmen; Cousin, Marie-Eve

    2006-08-01

    The implicit association test (IAT) measures automatic associations. In the present research, the IAT was adapted to measure implicit attitudes toward technological hazards. In Study 1, implicit and explicit attitudes toward nuclear power were examined. Implicit measures (i.e., the IAT) revealed negative attitudes toward nuclear power that were not detected by explicit measures (i.e., a questionnaire). In Study 2, implicit attitudes toward EMF (electro-magnetic field) hazards were examined. Results showed that cell phone base stations and power lines are judged to be similarly risky and, further, that base stations are more closely related to risk concepts than home appliances are. No differences between experts and lay people were observed. Results of the present studies are in line with the affect heuristic proposed by Slovic and colleagues. Affect seems to be an important factor in risk perception.

  3. Accumulation of /sup 137/Cs in commercial fish of the Belyarsk nuclear power station cooling supply

    SciTech Connect

    Trapeznikova, V.N.; Kulikov, N.V.; Trapeznikov, A.V.

    1984-07-01

    Results are presented of a comparative study of the accumulation of /sup 137/Cs in basic species of commercial fish of the Beloyarsk reservoir which is used as the cooling supply for the Beloyarsk nuclear power station. Possible reasons for interspecies differences in accumulation of the radionuclide are indicated, and the increased accumulation of /sup 137/Cs by free-living fish in the zone of heated water effluent from the station and the reduced accumulation of the emitter in carp, which are cultivated on artificial food in cages, are noted. Levels of the content of the radionuclide are compared in roach and farm carp from the cooling supplies of the Beloyarsk station and the Reftinsk power plant in the Urals.

  4. System Definition Document: Reactor Data Necessary for Modeling Plutonium Disposition in Catawba Nuclear Station Units 1 and 2

    SciTech Connect

    Ellis, R.J.

    2000-11-01

    The US Department of Energy (USDOE) has contracted with Duke Engineering and Services, Cogema, Inc., and Stone and Webster (DCS) to provide mixed-oxide (MOX) fuel fabrication and reactor irradiation services in support of USDOE's mission to dispose of surplus weapons-grade plutonium. The nuclear station units currently identified as mission reactors for this project are Catawba Units 1 and 2 and McGuire Units 1 and 2. This report is specific to Catawba Nuclear Station Units 1 and 2, but the details and materials for the McGuire reactors are very similar. The purpose of this document is to present a complete set of data about the reactor materials and components to be used in modeling the Catawba reactors to predict reactor physics parameters for the Catawba site. Except where noted, Duke Power Company or DCS documents are the sources of these data. These data are being used with the ORNL computer code models of the DCS Catawba (and McGuire) pressurized-water reactors.

  5. 78 FR 4879 - Nine Mile Point 3 Nuclear Project, LLC and UniStar Nuclear Operating Services, LLC Combined...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-23

    ... COMMISSION Nine Mile Point 3 Nuclear Project, LLC and UniStar Nuclear Operating Services, LLC Combined... Nuclear Project, LLC, and UniStar Nuclear Operating Services, LLC (UniStar), submitted a Combined License...) application for UniStar's Calvert Cliffs Nuclear Power Plant, Unit 3 (CCNPP3). The NRC docketed the...

  6. 77 FR 1748 - Atomic Safety and Licensing Board; Calvert Cliffs 3 Nuclear Project, LLC, and UniStar Nuclear...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-01-11

    ... COMMISSION Atomic Safety and Licensing Board; Calvert Cliffs 3 Nuclear Project, LLC, and UniStar Nuclear... Calvert Cliffs 3 Nuclear Project, L.L.C., and UniStar Nuclear Operating Services, L.L.C. (Applicants) for... Citizens Alliance for Renewable Energy Solutions; (2) UniStar Nuclear Operating Services, LLC and...

  7. Confirmatory Survey Results for the Reactor Building Dome Upper Surfaces, Rancho Saco Nuclear Generating Station

    SciTech Connect

    Wade C. Adams

    2006-10-25

    Results from a confirmatory survey of the upper structural surfaces of the Reactor Building Dome at the Rancho Seco Nuclear Generating Station (RSNGS) performed by the Oak Ridge Institute for Science and Education for the NRC. Also includes results of interlaboratory comparison analyses on several archived soil samples that would be provided by RSNGS personnel. The confirmatory surveys were performed on June 7 and 8, 2006.

  8. [Evaluating psychophysiologic adaptation state in operators of Bilibino nuclear power station].

    PubMed

    Isaeva, N A; Torubarov, F S; Denisova, E A; Zvereva, Z F; Koronotova, M A

    2014-01-01

    The study revealed that 60% operators of Bilibino nuclear power station suffer from psychosomatic diseases, 41.7% of them are assigned to occupational group of workers, and major part of the examinees with psychosomatic diseases (45.82%) are aged 41-50, high integral level ofpsychophysiologic adaptation is revealed in 5 examinees (12.5%), medium integral level--in 12 examinees (30%). Lower integral level of psychophysiologic adaptation manifested in decrease in psychophysiologic and physiologic levels.

  9. IET. Snaptran2 experiment. Project photographer working on "station c" camera. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Snaptran-2 experiment. Project photographer working on "station c" camera. Photographer: Page Comiskey. Date: September 22, 1965. INEEL negative no. 65-4949 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  10. The effects of solar-geomagnetically induced currents on electrical systems in nuclear power stations

    SciTech Connect

    Subudhi, M.; Carroll, D.P.; Kasturi, S.

    1994-01-01

    This report presents the results of a study to evaluate the potential effects of geomagnetically induced currents (GICs) caused by the solar disturbances on the in-plant electrical distribution system and equipment in nuclear power stations. The plant-specific electrical distribution system for a typical nuclear plant is modeled using the ElectroMagnetic Transient Program (EMTP). The computer model simulates online equipment and loads from the station transformer in the switchyard of the power station to the safety-buses at 120 volts to which all electronic devices are connected for plant monitoring. The analytical model of the plant`s electrical distribution system is studied to identify the transient effects caused by the half-cycle saturation of the station transformers due to GIC. This study provides results of the voltage harmonics levels that have been noted at various electrical buses inside the plant. The emergency circuits appear to be more susceptible to high harmonics due to the normally light load conditions. In addition to steady-state analysis, this model was further analyzed simulating various plant transient conditions (e.g., loss of load or large motor start-up) occurring during GIC events. Detail models of the plant`s protective relaying system employed in bus transfer application were included in this model to study the effects of the harmonic distortion of the voltage input. Potential harmonic effects on the uniterruptable power system (UPS) are qualitatively discussed as well.

  11. Modeling of a horizontal steam generator for the submerged nuclear power station concept

    SciTech Connect

    Palmrose, D.E.; Herring, J.S.

    1993-01-01

    A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube's inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

  12. Modeling of a horizontal steam generator for the submerged nuclear power station concept

    SciTech Connect

    Palmrose, D.E.; Herring, J.S.

    1993-05-01

    A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube`s inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

  13. Science in Flux: NASA's Nuclear Program at Plum Brook Station 1955-2005

    NASA Technical Reports Server (NTRS)

    Bowles, Mark D.

    2006-01-01

    Science in Flux traces the history of one of the most powerful nuclear test reactors in the United States and the only nuclear facility ever built by NASA. In the late 1950's NASA constructed Plum Brook Station on a vast tract of undeveloped land near Sandusky, Ohio. Once fully operational in 1963, it supported basic research for NASA's nuclear rocket program (NERVA). Plum Brook represents a significant, if largely forgotten, story of nuclear research, political change, and the professional culture of the scientists and engineers who devoted their lives to construct and operate the facility. In 1973, after only a decade of research, the government shut Plum Brook down before many of its experiments could be completed. Even the valiant attempt to redefine the reactor as an environmental analysis tool failed, and the facility went silent. The reactors lay in costly, but quiet standby for nearly a quarter-century before the Nuclear Regulatory Commission decided to decommission the reactors and clean up the site. The history of Plum Brook reveals the perils and potentials of that nuclear technology. As NASA, Congress, and space enthusiasts all begin looking once again at the nuclear option for sending humans to Mars, the echoes of Plum Brook's past will resonate with current policy and space initiatives.

  14. The Satellite Nuclear Power Station - An option for future power generation.

    NASA Technical Reports Server (NTRS)

    Williams, J. R.; Clement, J. D.

    1973-01-01

    A new concept in nuclear power generation is being explored which essentially eliminates major objections to nuclear power. The Satellite Nuclear Power Station, remotely operated in synchronous orbit, would transmit power safely to the ground by a microwave beam. Fuel reprocessing would take place in space and no radioactive materials would ever be returned to earth. Even the worst possible accident to such a plant should have negligible effect on the earth. An exploratory study of a satellite nuclear power station to provide 10,000 MWe to the earth has shown that the system could weigh about 20 million pounds and cost less than $1000/KWe. An advanced breeder reactor operating with an MHD power cycle could achieve an efficiency of about 50% with a 1100 K radiator temperature. If a hydrogen moderated gas core reactor is used, its breeding ratio of 1.10 would result in a fuel doubling time of a few years. A rotating fluidized bed or NERVA type reactor might also be used. The efficiency of power transmission from synchronous orbit would range from 70% to 80%.

  15. [Water-soluble anions of atmosphere on Tianwan nuclear power station].

    PubMed

    Zhao, Heng-Qiang; He, Ying; Zheng, Xiao-Ling; Chen, Fa-Rong; Pang, Shi-Ping; Wang, Cai-Xia; Wang, Xiao-Ru

    2010-11-01

    Three major water-soluble anions (Cl-, SO4(2-) and NO3-) in the atmosphere of the Tianwan nuclear power station in Lianyungang were determined by ion chromatography from June 2005 to May 2006. The results showed that the annual average concentration of Cl-, SO4(2-) and NO3- in the atmosphere of Tianwan nuclear power station was (33.12 +/- 53.63) microg x m(-3), (53.34 +/- 30.34) microg x m(-3) and (8.34 +/- 4.47) microg x m(-3), respectively. The concentrations of the three water-soluble anions showed evident trend of seasonal variation. The concentrations of Cl-, SO4(2-) reached the highest level in summer and the lowest level in winter, while the concentration of NO3- in autumn and winter was higher than those in summer and spring. Meteorological parameters such as wind direction, wind speed, temperature and relative humidity were studied and showed definite influence to the anions concentration of the atmosphere. This is the first simultaneous monitoring of corrosive anions in the atmosphere of Chinese coastal nuclear power plant, and it will provide basis for the prevention of marine atmospheric corrosion, which will ensure the safely operating of our nuclear power industry.

  16. 75 FR 7628 - Davis-Besse Nuclear Power Station; Notice of Consideration of Issuance of Amendment to Facility...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-22

    ... COMMISSION Davis-Besse Nuclear Power Station; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a... determination that the amendment request involves no significant hazards consideration. Under the...

  17. Summary report of project SIREN (Search, Intercept, Retrieve, Expulsion, Nuclear)

    SciTech Connect

    Buden, D.

    1992-12-01

    Project SIREN (Search, Intercept, Retrieve, Expulsion, Nuclear) has evaluated the technologies and operational strategies needed to rendezvous with and capture aerospace radioactive materials (e.g., a distressed or spent space reactor core) before such materials can reenter the terrestrial atmosphere and to move these captured materials to a space destination for proper disposal. The use of systems external to a satellite allows multiple attempts to prevent the nuclear materials from reentering the atmosphere. SIREN also has investigated means to prevent the breakup of nuclear-powered systems already in space. The SIREN project has determined that external means can be used reliably to prevent nuclear materials from reentering the terrestrial environment, prepared a computer model that can be used to evaluate the means to dispose of radioactive materials, assessed the hazards from existing nuclear power systems in space, and in discussions with Russian Federation representatives determined interest in joint activities in this area.

  18. Atmospheric release advisory capability pilot project at two nuclear power plants and associated state offices of emergency preparedness. Final report

    SciTech Connect

    Rosen, L.C.

    1983-01-01

    A project to demonstrate the feasibility of utilizing Atmospheric Release Advisory Capability (ARAC) limited service with commercial nuclear power plants and their associated state offices of emergency preparedness is discussed. Preliminary planning, installation and testing of the ARAC site facilities at Indian Point Nucler Power Station, New York State; at New York State Office of Emergency Preparedness, Albany, New York; at Rancho Seco Nuclear Generating Station, California; and at the State of California Office of Emergency Services, Sacramento, California, are summarized. ARAC participation in the Robert E. Ginna nuclear generating plant accident in New York on January 25, 1982, is discussed. The ARAC system is evaluated with emphasis on communications, the suite of models contained within the ARAC system, and the staff. The implications of this project in designing the next-generation ARAC system to service federal and state needs are assessed.

  19. Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability

    SciTech Connect

    Golay, Michael

    2016-10-30

    This project aims to go beyond effective communication in understanding how to design nuclear enterprise projects that will gain stakeholder acceptability. Much of what we are studying is generally applicable to controversial projects, and we expect our results to be of broad value beyond the nuclear arena. Acceptability is more than effective communication; it also requires varying degrees of engagement with a disparate number of stakeholder groups. In the nuclear enterprise, previous attempts have been well designed physically (i.e., technologically sound), but have floundered by being insensitive concerning acceptance. Though effective communication is a necessary, but insufficient, condition for such success, there is a lack of scholarship regarding how to gain stakeholder acceptance for new controversial projects, including nuclear ones. Our work is building a model for use in assessing the performance of a project in the area of acceptability. In the nuclear-social nexus, gaining acceptance requires a clear understanding of factors regarded as being important by the many stakeholders that are common to new nuclear project (many of whom hold an effective veto power). Projects tend to become socially controversial when public beliefs, expert opinion and decision-maker understanding are misaligned. As such, stakeholder acceptance is hypothesized as both an ongoing process and an initial project design parameter comprised of complex, social, cognitive and technical components. Controversial projects may be defined as aspects of modern technologies that some people question, or are cautious about. They could range from genetic modifications, biological hazards, effects of chemical agents, nuclear radiation or hydraulic fracturing operations. We intend that our work will result in a model likely to be valuable for refining project design and implementation to increase the knowledge needed for successful management of stakeholder relationships.

  20. Characteristics of neurological status and the electroencephalogram in nuclear power station control operators.

    PubMed

    Laskova, I V; Tret'yakova, E E

    2010-05-01

    A total of 105 control operators at the Kursk nuclear power station were studied: 45 after working shifts (study group) and 60 on rest days (reference group). These investigations showed that operators' work shifts had significant influences on the functional state of the nervous system, promoting the appearance or exacerbation of autonomic dysfunction. In some cases, work shifts increased arterial blood pressure to risk levels for the development of cerebrovascular disease. The effects of nuclear power station operators' work shifts on brain bioelectrical activity included a decrease in the proportion of unaltered EEG traces, along with increases in the spectral power densities of the alpha rhythm in the parietal leads and the theta rhythm in the posterior temporal and parietal leads. The origin of these changes may be related to both fatigue and the effects of adverse industrial factors. It is suggested that clinical observation of power station operators should be supplemented by assessments of autonomic dysfunction and measurement of the spectral power densities of the alpha and theta rhythms in the parietal and posterior temporal leads.

  1. Spent Nuclear Fuel Project Configuration Management Plan

    SciTech Connect

    Reilly, M.A.

    1995-06-09

    This document is a rewrite of the draft ``C`` that was agreed to ``in principle`` by SNF Project level 2 managers on EDT 609835, dated March 1995 (not released). The implementation process philosphy was changed in keeping with the ongoing reengineering of the WHC Controlled Manuals to achieve configuration management within the SNF Project.

  2. Future of strategic nuclear deterrence. Study project

    SciTech Connect

    Floris, J.

    1992-04-10

    The evolving role of our Strategic Nuclear Forces and the deterrent requirement of that force in a changing and volatile world are two of the most contentious issues facing this country's leadership. The debate surrounding these forces has been brought about by many diverse factors that include the dissolution of the Soviet Union and the resultant end of the Cold War, bilateral arms control agreements and unilateral reductions which have reduced the number and operational status of nuclear forces, and a perceived reduction in the threat facing the U.S. and its allies. Additionally, the success of U.S. technology as seen in the effects of modern conventional munitions in the Gulf War and the proliferation of ballistic missile and nuclear weapons technology into Third World countries have further compounded the complexity of the issue. The concomitant changes in the focus and structure of U.S. and allied military forces have further fueled the debate. As the National Security Strategy and supporting National Military Strategy are evolving to meet new threats, it is essential to provide an analysis of the continued deterrent role of our Strategic Nuclear Force in this changing world.

  3. Nuclear carrier business volume projections, 1980-2000

    SciTech Connect

    Lebo, R.G.; McKeown, M.S.; Rhyne, W.R.

    1980-05-01

    The expected number of shipments of commodities in the nuclear fuel cycle are projected for the years 1980 thru 2000. Projections are made for: yellowcake (U/sub 3/O/sub 8/); natural, enriched and reprocessed uranium hexafluoride (UF/sub 6/); uranium dioxide powder (UO/sub 2/); plutonium dioxide powder (PuO/sub 2/); fresh UO/sub 2/ and mixed oxide (MOX) fuel; spent UO/sub 2/ fuel; low-level waste (LLW); transuranic (TRU) waste; high-activity TRU waste; high-level waste (HLW), and cladding hulls. Projections are also made for non-fuel cycle commodities such as defense TRU wastes and institutional wastes, since they also are shipped by the commercial transportation industry. Projections of waste shipments from LWRs are based on the continuation of current volume reduction and solidification techniques now used by the utility industry. Projections are also made based on a 5% per year reduction in LWR waste volume shipped which is assumed to occur as a result of increased implementation of currently available volume reduction systems. This assumption results in a net 64% decrease in the total waste shipped by the year 2000. LWR waste shipment projections, and essentially all other projections for fuel cycle commodities covered in this report, are normalized to BWR and PWR generating capacity projections set forth by the Department of Energy (DOE) in their low-growth projection of April, 1979. Therefore these commodity shipment projections may be altered to comply with future changes in generating capacity projections. Projected shipments of waste from the reprocessing of spent UO/sub 2/ fuel are based on waste generation rates proposed by Nuclear Fuels Services, Allied-General Nuclear Services, Exxon Nuclear, and the DOE. Reprocessing is assumed to begin again in 1990, with mixed oxide fresh fuel available for shipment by 1991.

  4. A radiological assessment of nuclear power and propulsion operations near Space Station Freedom

    NASA Technical Reports Server (NTRS)

    Bolch, Wesley E.; Thomas, J. Kelly; Peddicord, K. Lee; Nelson, Paul; Marshall, David T.; Busche, Donna M.

    1990-01-01

    Scenarios were identified which involve the use of nuclear power systems in the vicinity of Space Station Freedom (SSF) and their radiological impact on the SSF crew was quantified. Several of the developed scenarios relate to the use of SSF as an evolutionary transportation node for lunar and Mars missions. In particular, radiation doses delivered to SSF crew were calculated for both the launch and subsequent return of a Nuclear Electric Propulsion (NEP) cargo vehicle and a Nuclear Thermal Rocket (NTR) personnel vehicle to low earth orbit. The use of nuclear power on co-orbiting platforms and the storage and handling issues associated with radioisotope power systems were also explored as they relate to SSF. A central philosophy in these analyses was the utilization of a radiation dose budget, defined as the difference between recommended dose limits from all radiation sources and estimated doses received by crew members from natural space radiations. Consequently, for each scenario examined, the dose budget concept was used to identify and quantify constraints on operational parameters such as launch separation distances, returned vehicle parking distances, and reactor shutdown times prior to vehicle approach. The results indicate that realistic scenarios do not exist which would preclude the use of nuclear power sources in the vicinity of SSF. The radiation dose to the SSF crew can be maintained at safe levels solely by implementing proper and reasonable operating procedures.

  5. The {open_quotes}Dragon of Kovachitsa{close_quotes}: Local perceptions of radioactive pollution near the Kozlodui Nuclear Power Station (Bulgaria)

    SciTech Connect

    Konstantinov, Y.

    1995-03-01

    There is continuing uncertainty surrounding the safety of nuclear power stations in Eastern Europe, among them the one at Kozlodui, Bulgaria. It is argued in this paper that attempts on the part of the state to assert the safety of nuclear power stations are expressed in terms of an official {open_quotes}nuclear-safe{close_quotes} discourse, while the local inhabitants near the Kozlodui nuclear power station employ a vernacular mode of expression to explain possible radioactive pollution.

  6. Spent nuclear fuel project integrated schedule plan

    SciTech Connect

    Squires, K.G.

    1995-03-06

    The Spent Nuclear Fuel Integrated Schedule Plan establishes the organizational responsibilities, rules for developing, maintain and status of the SNF integrated schedule, and an implementation plan for the integrated schedule. The mission of the SNFP on the Hanford site is to provide safe, economic, environmentally sound management of Hanford SNF in a manner which stages it to final disposition. This particularly involves K Basin fuel.

  7. 75 FR 14211 - Southern California Edison, San Onofre Nuclear Generating Station, Unit 2 and Unit 3; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-24

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern California Edison, San Onofre Nuclear Generating Station, Unit 2 and Unit 3; Exemption 1.0 Background Southern California Edison (SCE, the licensee) is the holder of the Facility...

  8. 75 FR 71152 - Southern California Edison; San Onofre Nuclear Generating Station, Unit 2 and Unit 3; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-22

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern California Edison; San Onofre Nuclear Generating Station, Unit 2 and Unit 3; Exemption 1.0 Background Southern California Edison (SCE, the licensee) is the holder of the Facility...

  9. 78 FR 47426 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to the...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-05

    ... shield building in order to support the current electrical loads required within containment. This... COMMISSION Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to the Containment Structure for Additional Electrical Penetration Assemblies AGENCY: Nuclear Regulatory...

  10. 75 FR 9623 - Arizona Public Service Company, et al.; Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-03

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Arizona Public Service Company, et al.; Palo Verde Nuclear Generating Station, Units 1, 2, and 3... Facility Operating License Nos. NPF-41, NPF-51, and NPF- 74, which authorize operation of the Palo...

  11. 75 FR 15745 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-30

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3... Operating License Nos. NPF-41, NPF-51, and NPF-74, which authorize operation of the Palo Verde...

  12. Agile Machining and Inspection Non-Nuclear Report (NNR) Project

    SciTech Connect

    Lazarus, Lloyd

    2009-02-19

    This report is a high level summary of the eight major projects funded by the Agile Machining and Inspection Non-Nuclear Readiness (NNR) project (FY06.0422.3.04.R1). The largest project of the group is the Rapid Response project in which the six major sub categories are summarized. This project focused on the operations of the machining departments that will comprise Special Applications Machining (SAM) in the Kansas City Responsive Infrastructure Manufacturing & Sourcing (KCRIMS) project. This project was aimed at upgrading older machine tools, developing new inspection tools, eliminating Classified Removable Electronic Media (CREM) in the handling of classified Numerical Control (NC) programs by installing the CRONOS network, and developing methods to automatically load Coordinated-Measuring Machine (CMM) inspection data into bomb books and product score cards. Finally, the project personnel leaned perations of some of the machine tool cells, and now have the model to continue this activity.

  13. Radiation exposure to the orbiting lunar station and lunar surface related to reusable nuclear shuttle operations

    NASA Technical Reports Server (NTRS)

    Hutchinson, P. I.

    1972-01-01

    The radiation environment created by the Reusable Nuclear Vehicle (RNS) in performing its normal mission functions while in the lunar vicinity and the impact of that environment on the Orbiting Lunar Station (OLS) and/or the lunar surface are examined. Lunar surface exposures from the operating reactor were evaluated for both the arrival and departure burns and while there is little probability that manned bases would lie along the paths in which measurable exposures would be recorded, the analyses do indicate the need to consider this possibility in planning such operations. Conclusions supported by the analyses and recommended operational constraints for the RNS are presented.

  14. Safety research of insulating materials of cable for nuclear power generating station

    NASA Technical Reports Server (NTRS)

    Lee, C. K.; Choi, J. H.; Kong, Y. K.; Chang, H. S.

    1988-01-01

    The polymers PE, EPR, PVC, Neoprene, CSP, CLPE, EP and other similar substances are frequently used as insulation and protective covering for cables used in nuclear power generating stations. In order to test these materials for flame retardation, environmental resistance, and cable specifications, they were given the cable normal test, flame test, chemical tests, and subjected to design analysis and loss of coolant accident tests. Material was collected on spark tests and actual experience standards were established through these contributions and technology was accumulated.

  15. Report of the State of Nevada Commission on Nuclear Projects

    SciTech Connect

    1990-12-01

    This third biennial Report of the Nevada Commission on Nuclear Projects has been prepared in fulfillment of the requirements of NRS 459.0092, which stipulates that the Commission shall report to the Governor and Legislature on any matter relating to radioactive waste disposal the Commission deems appropriate and advise and make recommendations on the policy of the State concerning nuclear waste disposal projects. Chapter One of the Report presents a brief overview of the Commission`s functions and statutory charges. It also contains a summary of developments which have affected the overall nuclear waste disposl issue since the last Commission Report was published in November, 1988. Chapter Two contains a synthesis of Commission activities and reports on the findings of the Commission relative to the geotechnical, environmental, socioeconomic, transportation, intergovernmental and legal aspects of federal and State nuclear waste program efforts.

  16. The AP1000{sup R} nuclear power plant innovative features for extended station blackout mitigation

    SciTech Connect

    Vereb, F.; Winters, J.; Schulz, T.; Cummins, E.; Oriani, L.

    2012-07-01

    Station Blackout (SBO) is defined as 'a condition wherein a nuclear power plant sustains a loss of all offsite electric power system concurrent with turbine trip and unavailability of all onsite emergency alternating current (AC) power system. Station blackout does not include the loss of available AC power to buses fed by station batteries through inverters or by alternate AC sources as defined in this section, nor does it assume a concurrent single failure or design basis accident...' in accordance with Reference 1. In this paper, the innovative features of the AP1000 plant design are described with their operation in the scenario of an extended station blackout event. General operation of the passive safety systems are described as well as the unique features which allow the AP1000 plant to cope for at least 7 days during station blackout. Points of emphasis will include: - Passive safety system operation during SBO - 'Fail-safe' nature of key passive safety system valves; automatically places the valve in a conservatively safe alignment even in case of multiple failures in all power supply systems, including normal AC and battery backup - Passive Spent Fuel Pool cooling and makeup water supply during SBO - Robustness of AP1000 plant due to the location of key systems, structures and components required for Safe Shutdown - Diverse means of supplying makeup water to the Passive Containment Cooling System (PCS) and the Spent Fuel Pool (SFP) through use of an engineered, safety-related piping interface and portable equipment, as well as with permanently installed onsite ancillary equipment. (authors)

  17. Photovoltaic power system for satellite Earth stations in remote areas: Project status and design description

    NASA Technical Reports Server (NTRS)

    Delombard, R.

    1984-01-01

    A photovoltaic power system which will be installed at a remote location in Indonesia to provide power for a satellite Earth station and a classroom for video and audio teleconferences are described. The Earth station may also provide telephone service to a nearby village. The use of satellite communications for development assistance applications and the suitability of a hybrid photovoltaic engine generator power system for remote satellite Earth stations are demonstrated. The Indonesian rural satellite project is discussed and the photovoltaic power system is described.

  18. Polar automatic weather station project of the University of Wisconsin

    SciTech Connect

    Stearns, C.R.; Weidner, G.A.

    1992-03-01

    The polar automatic weather station (AWS) of the University of Wisconsin is a battery-powered, solar panel-charged, computer-controlled unit that measures wind speed, wind direction, air temperature, air pressure, vertical temperature difference, and relative humidity. The nominal height of the measurements is three to five meters at the time of installation. The data are transmitted to polar-orbiting satellites equipped with the ARGOS data collection system. The sensors are measured at ten-minute intervals and three to five values of each sensor are transmitted at 200-second intervals. More than 100 values at ten-minute intervals are recorded in 24 hours. Thirty-four AWS units are installed in Antarctica and four AWS units are installed on the Greenland Crest. Up to 28 of the 38 AWS units are received by the Global Telecommunications System at six-hour intervals.

  19. State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, January 1--June 30, 1991

    SciTech Connect

    1996-08-01

    The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada`s responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency`s oversight responsibilities. (1) Assure that the health and safety of Nevada`s citizens are adequately protected with regard to any federal high-level radioactive waste program within the State. (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987. (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State. (4) Work closely and consult with affected local governments and State agencies. (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository.

  20. Recovery Act Hospital Alteration Project at Naval Air Station Jacksonville

    DTIC Science & Technology

    2010-12-07

    QMAD Quantitative Methods and Analysis Division RLF Rogers Lovelock & Fritz, Incorporated SE Southeast SF Square Feet SOW Statement of Work TMA TRICARE...Finally, the contractor, Rogers Lovelock & Fritz, Incorporated, reported the recipient information required by the Recovery Act. What We Recommend...contractor, Rogers Lovelock & Fritz, Incorporated (RLF), reported the recipient information required by the Recovery Act. Planning: Initially, Project

  1. Elimination of redundant thermoluminescent dosemeter monitoring at Oyster Creek nuclear generating station

    SciTech Connect

    Schwartz, P.E.

    1989-01-01

    The Oyster Creek direct radiation monitoring network has long been operating using several time-scale measurements. This network is used to assess the radiation levels during normal plant operations as well as to set the background radiation levels used to determine the radiological impact of a nonroutine release of radioactivity from the plant. Through analysis of the behavior of the monthly and quarterly activity of several types of direct radiation monitoring, the successful elimination of redundant and artificially high measurement techniques has been done in concert with providing the community with most efficient direct radiation monitoring methods. Dose rates from external radiation sources are measured around licensed U.S. Nuclear Regulatory Commission (NRC) facilities using passive detectors known as thermoluminescent dosimeters (TLDs). These detectors provide a quantitative measurement of the radiation levels in the are in which they are placed. The detected radiation could be the result of cosmic or naturally occurring origin in the air and on the ground, prior nuclear weapons testing, and activity from a nuclear facility. This paper describes the TLD network placed around the Oyster Creek nuclear generating station (OCNGS) and the comparisons between TLDs of different manufacturers and of different resident times and the successful elimination of the less accurate monthly TLD for the purpose of cost containment.

  2. Gas Core Nuclear Rocket Feasibility Project

    NASA Technical Reports Server (NTRS)

    Howe, S. D.; DeVolder, B.; Thode, L.; Zerkle, D.

    1997-01-01

    The next giant leap for mankind will be the human exploration of Mars. Almost certainly within the next thirty years, a human crew will brave the isolation, the radiation, and the lack of gravity to walk on and explore the Red planet. However, because the mission distances and duration will be hundreds of times greater than the lunar missions, a human crew will face much greater obstacles and a higher risk than those experienced during the Apollo program. A single solution to many of these obstacles is to dramatically decrease the mission duration by developing a high performance propulsion system. The gas core nuclear rocket (GCNR) has the potential to be such a system. The gas core concept relies on the use of fluid dynamic forces to create and maintain a vortex. The vortex is composed of a fissile material which will achieve criticality and produce high power levels. By radiatively coupling to the surrounding fluids, extremely high temperatures in the propellant and, thus, high specific impulses can be generated. The ship velocities enabled by such performance may allow a 9 month round trip, manned Mars mission to be considered. Alternatively, one might consider slightly longer missions in ships that are heavily shielded against the intense Galactic Cosmic Ray flux to further reduce the radiation dose to the crew. The current status of the research program at the Los Alamos National Laboratory into the gas core nuclear rocket feasibility will be discussed.

  3. Gas core nuclear rocket feasibility project

    SciTech Connect

    Howe, S.D.; DeVolder, B.; Thode, L.; Zerkle, D.

    1997-09-01

    The next giant leap for mankind will be the human exploration of Mars. Almost certainly within the next thirty years, a human crew will brave the isolation, the radiation, and the lack of gravity to walk on and explore the Red planet. However, because the mission distances and duration will be hundreds of times greater than the lunar missions, a human crew will face much greater obstacles and a higher risk than those experienced during the Apollo program. A single solution to many of these obstacles is to dramatically decrease the mission duration by developing a high performance propulsion system. The gas core nuclear rocket (GCNR) has the potential to be such a system. The gas core concept relies on the use of fluid dynamic forces to create and maintain a vortex. The vortex is composed of a fissile material which will achieve criticality and produce high power levels. By radiatively coupling to the surrounding fluids, extremely high temperatures in the propellant and, thus, high specific impulses can be generated. The ship velocities enabled by such performance may allow a 9 month round trip, manned Mars mission to be considered. Alternatively, one might consider slightly longer missions in ships that are heavily shielded against the intense Galactic Cosmic Ray flux to further reduce the radiation dose to the crew. The current status of the research program at the Los Alamos National Laboratory into the gas core nuclear rocket feasibility will be discussed.

  4. [Nuclear energy and environment: review of the IAEA environmental projects].

    PubMed

    Fesenko, S; Fogt, G

    2012-01-01

    The review of the environmental projects of the International Atomic Energy Agency is presented. Basic IAEA documents intended to protect humans and the Environment are considered and their main features are discussed. Some challenging issues in the area of protection of the Environment and man, including the impact of nuclear facilities on the environment, radioactive waste management, and remediation of the areas affected by radiological accidents, nuclear testing and sites of nuclear facilities are also discussed. The need to maintain the existing knowledge in radioecology and protection of the environment is emphasised.

  5. The May 18, 1998 Indian Nuclear Test Seismograms at station NIL

    SciTech Connect

    Walter, W R; Rodgers, A J; Bowers, D; Selby, N

    2005-04-11

    The last underground nuclear tests were conducted by India and Pakistan in May 1998. Although the Comprehensive Test Ban Treaty has not entered force, an International Monitoring System (IMS), established by the treaty is nearing completion. This system includes 170 seismic stations, a number of them originally established by IRIS. The station IRIS station NIL (Nilore, Pakistan) is close to a planned IMS primary station and recorded some very interesting seismograms from the May 18, 1998 Indian test. We carefully calibrated the path to NIL using a prior Mw 4.4 that occurred on April 4, 1995 about 110 km north of the Indian test site. We used joint epicentral location techniques along with teleseismic P waves and regional surface waves to fix the epicenter, depth, mechanism and moment of this event. From these we obtained a velocity model for the path to NIL and created explosion synthetic seismograms to compare with the data. Interestingly the observed Rayleigh waves are reversed, consistent with an implosion rather than an explosion source. The preferred explanation is that the explosion released tectonic stress near the source region, which can be modeled as a thrust earthquake of approximate Mw 4.0 plus a pure explosion. This tectonic release is sufficient to completely dominate the Rayleigh waves and produce the observed signal (Walter et al. 2005). We also examined the explosion at high frequencies of 6 6-8 Hz where many studies have shown that relative P/S amplitudes can discriminate explosions from a background of earthquakes (Rodgers and Walter, 2002). Comparing with the April 4 1995 earthquake we see the classic difference of relatively large P/S values for the explosion compared to the earthquakes despite the complication of the large tectonic release during the explosion.

  6. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    SciTech Connect

    Sanchez, R.G.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

  7. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    SciTech Connect

    BAZINET, G.D.

    2000-11-03

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted

  8. [Cytogenetic characteristics of seed offspring of leafy tree plants from one-kilometer zone of Novovoronezh nuclear power station].

    PubMed

    Artiukhov, V G; Kalaev, V N; Sen'kevich, E V; Vakhtel', V M; Savko, A D

    2004-01-01

    Cytogenetic characteristics (mitotic activity, level and spectrum of pathological mitoses, nucleoly characteristics) of seed offspring of Quercus robur L. and Betula pendula Roth from Novovoronezh nuclear power station's 1-kilometer zone have been studied. It has been shown the change of time of passing though mitotic stages by cells, the increasing of bridges frequency occur in spectrum of mitotic aberrations (that shows activation of reparation systems), the change in nucleoly characteristics (the part of polynucleolaris cells increase in case of oak and decrease in case of birch, the rase of surface square of single nucleolies). The phenomena, mean above, probably, induced by synergic effects of Novovoronezh nuclear power station and environment pollutants. The most contaminated territories of 1-kilometer zone of Novovoronezh nuclear power station have been discovered by means of methods of cluster analysis of total cytogenetic characteristics of tree plants seed offspring.

  9. Nuclear electric propulsion: An integral part of NASA's nuclear propulsion project

    NASA Technical Reports Server (NTRS)

    Stone, James R.

    1992-01-01

    NASA has initiated a technology program to establish the readiness of nuclear propulsion technology for the Space Exploration Initiative (SEI). This program was initiated with a very modest effort identified with nuclear thermal propulsion (NTP); however, nuclear electric propulsion (NEP) is also an integral part of this program and builds upon NASA's Base Research and Technology Program in power and electric propulsion as well as the SP-100 space nuclear power program. Although the Synthesis Group On America's SEI has identified NEP only as an option for cargo missions, recent studies conducted by NASA-Lewis show that NEP offers the potential for early manned Mars missions as well. Lower power NEP is also of current interest for outer planetary robotic missions. Current plans are reviewed for the overall nuclear propulsion project, with emphasis on NEP and those elements of NTP program which have synergism with NEP.

  10. Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report

    SciTech Connect

    Hebdon, F.J.

    1993-03-01

    On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility`s actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities.

  11. Projects of High-Temperature Nuclear Reactors

    NASA Astrophysics Data System (ADS)

    Ekmanis, J.; Tomsons, E.; Zeltiņš, N.

    2013-04-01

    Part 2 of the overview gives emphasis to the projects of high-temperature NRs, whose development is an area of active engagement for the specialists from the USA, France, Japan, Russia, China, the Netherlands, and Germany. Projects of several powerful NRs of the HTGR type for commercial use had been worked out in the USA and Germany already by 1970 but not yet implemented. Augstas temperatūras ar gāzes dzesēšanu HTGR (High Temperature Gas cooled Reactor) tipa kodolreaktoru (KR) izstrādes koncepcija bija piedāvāta 1956. gadā Lielbritānijā. Apmēram tanī pašā laikā minētā tipa KR izstrādi uzsāka Vācijā un ASV. HTGR tipa KR kodoldegviela un kodoldegvielas atražošanas materiāla sīkās daļiņas ar diametru apmēram 0.5 mm pārklātas ar vairākām aizsargkārtām un atrodas grafīta neitronu palēninātājā, kas aizsargā daļiņas no neitronu palēninātāja un dzesētāja iedarbes. Augstas temperatūras KR bez hēlija gāzes siltumnesēja var izmantot šķidrus metālus (nātriju, svinu vai svina-bismuta sakausējumu) un izkausētu sāli. Pašlaik darbojās divi augstas temperatūras ar hēlija gāzi dzesēti eksperimentālie HTGR tipa KR. Viens Japānā "HTTR" no 1998. gada oktobra (sākts būvēt 1991. gada 15. martā) ar 30 MWth siltuma jaudu. Otrs Ķīnā "HTR-10" no 2000.gada decembra (sākts būvēt 1995. gada14. jūnijā) ar 10 MWth siltuma jaudu. Ķīnā Shandong provincē 2011.gada aprīlī uzsāka augstas temperatūras "HTR-PM" (High Temperature Gas-cooled Reactor - Pebble bed Module) tipa kodolreaktora celtniecību ar 250 MWth siltuma jaudu. Augstas temperatūras kodolreaktoru izstrādē pašlaik aktīvi iesaistīti ASV, Francijas, Japānas, Krievijas, Ķīnas, Nīderlandes un Vācijas speciālisti.

  12. Current status of radiological protection at nuclear power stations in Japan.

    PubMed

    Suzuki, Akira; Hori, Shunsuke

    2011-07-01

    The radiation dose to workers at nuclear power stations (NPSs) in Japan was drastically reduced between the late-1970s and the early-1990s by continuous dose-reduction programmes. The total collective dose of radiation workers in FY 2008 was 84.04 person Sv, while the average collective dose was 1.5 person Sv per reactor. The average annual individual dose was 1.1 mSv and the maximum annual individual dose was 19.5 mSv. These values are sufficiently lower than the regulatory dose limits. Radioactive effluent released from NPSs is already so trivial that additional protective measures will not be necessary. Experience in radiation protection at NPSs has been accumulated over 40 y and will be very useful in establishing a rational radiation control system in the future.

  13. Concentration of (3)H in plants around Fukushima Dai-ichi Nuclear Power Station.

    PubMed

    Kakiuchi, Hideki; Akata, Naofumi; Hasegawa, Hidenao; Ueda, Shinji; Tokonami, Shinji; Yamada, Masatoshi; Hosoda, Masahiro; Sorimachi, Atsuyuki; Tazoe, Hirofumi; Noda, Kaori; Hisamatsu, Shun'ichi

    2012-01-01

    A large amount of radionuclides was released from the Fukushima Dai-ichi Nuclear Power Station (FDNPS) following the damage caused by the tsunami due to the Great East Japan Earthquake on 11 March 2011. Although many radionuclides in various environmental samples around the FDNPS have been measured, (3)H in the terrestrial environment has not yet been reported. We present here the first survey results of (3)H concentrations in plant samples collected around the FDNPS in 2011 from shortly after the accident. The free-water (3)H concentrations in herbaceous plant shoots and evergreen tree leaves were considerably higher than the previous background concentration, and diminished with distance from the FDNPS. Although reconstruction of atmospheric (3)H concentrations after the accident is difficult, a rough estimate of the radiation dose due to (3)H inhalation about 20 km from the FDNPS is on the order of a few microsieverts (μSv).

  14. Indian Point Nuclear Power Station: verification analysis of County Radiological Emergency-Response Plans

    SciTech Connect

    Nagle, J.; Whitfield, R.

    1983-05-01

    This report was developed as a management tool for use by the Federal Emergency Management Agency (FEMA) Region II staff. The analysis summarized in this report was undertaken to verify the extent to which procedures, training programs, and resources set forth in the County Radiological Emergency Response Plans (CRERPs) for Orange, Putnam, and Westchester counties in New York had been realized prior to the March 9, 1983, exercise of the Indian Point Nuclear Power Station near Buchanan, New York. To this end, a telephone survey of county emergency response organizations was conducted between January 19 and February 22, 1983. This report presents the results of responses obtained from this survey of county emergency response organizations.

  15. Temporal variation of dose rate distribution around the Fukushima Daiichi nuclear power station using unmanned helicopter.

    PubMed

    Sanada, Yukihisa; Orita, Tadashi; Torii, Tatsuo

    2016-12-01

    Aerial radiological survey using an unmanned aerial vehicle (UAV) was applied to measurement surface contamination around the Fukushima Daiichi nuclear power station (FDNPS). An unmanned helicopter monitoring system (UHMS) was developed to survey the environmental effect of radioactive cesium scattered as a result of the FDNPS accident. The UHMS was used to monitor the area surrounding the FDNPS six times from 2012 to 2015. Quantitative changes in the radioactivity distribution trend were revealed from the results of these monitoring runs. With this information, we found that the actual reduction of dose rate was faster than the one calculated with radiocesium physical half-life. It is indicated that the attenuation effect of radiation by radiocesium penetration in soil is dominant as for reason of reduction of dose rate.

  16. Project EGRESS: The design of an assured crew return vehicle for the space station

    NASA Technical Reports Server (NTRS)

    1990-01-01

    Keeping preliminary studies by NASA in mind, an Assured Crew Return Vehicle (ACRV) was developed. The system allows the escape of one or more crew members from Space Station Freedom in case of emergency. The design of the vehicle addresses propulsion, orbital operations, reentry, landing and recovery, power and communication, and life support. In light of recent modifications in Space Station design, Project EGRESS (Earthbound Guaranteed ReEntry from Space Station) pays particular attention to its impact on Space Station operations, interfaces and docking facilities, and maintenance needs. A water landing, medium lift vehicle was found to best satisfy project goals of simplicity and cost efficiency without sacrificing the safety and reliability requirements. With a single vehicle, one injured crew member could be returned to Earth with minimal pilot involvement. Since the craft is capable of returning up to five crew members, two such permanently docked vehicles would allow full evacuation of the Space Station. The craft could be constructed entirely with available 1990 technology and launched aboard a shuttle orbiter.

  17. Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station

    SciTech Connect

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Dawson, J.W.; Brunk, J.L.; Jokela, T.A.

    1985-03-22

    This report summarizes the information compiled in 1984 while assessing the environmental impact of radionuclides in aquatic releases from the Rancho Seco Nuclear Power Generating Station. Gamma-emitting radionuclides discharged since 1981 are found in many of the dietary components derived from the creeks receiving the effluent wastewater. Some soils and crops are found to contain radionuclides that originate from the contaminated water that was transferred to land during the irrigation season. /sup 134/Cs and /sup 137/Cs are the primary gamma-emitting radionuclides detected in the edible flesh of fish from the creeks. Concentrations in the flesh of fish decreased exponentially with distance from the plant. No significant differences in the /sup 137/Cs activity were found between male and female fish of equal size, but concentrations may vary in fish of different size, with the season and diet. 21% of the total /sup 137/Cs and /sup 134/Cs discharged between 1981 and 1984 is associated with the creek sediments to a distance of 27 km from the plant. Fractions of the missing inventory have been transferred to land during the irrigation season or to downstream regions more distant than 27 km from the plant. The radiocesium content of the sediments in 1984 decreased significantly in a downstream direction, much in the same manner as concentrations decreased in fish. Radioactivity originating from the plant was not above detection limits in any terrestrial food item sampled beyond 6.5 km from the plant. Based on the usage factors provided by individuals interviewed in a 1984 survey, the fish and aquatic-organism ingestion pathway contributed the largest radiological dose to humans utilizing products contaminated with the radionuclides in the liquid wastes discharged from the Rancho Seco Nuclear Power Generating Station in 1984.

  18. Reconfigurable Assembly Station for Precision Manufacture of Nuclear Fusion Ignition Targets

    SciTech Connect

    Castro, C; Montesanti, R C; Taylor, J S; Hamza, A V; Dzenitis, E G

    2009-08-11

    This paper explores the design and testing of a reconfigurable assembly station developed for assembling the inertial confinement nuclear fusion ignition targets that will be fielded in the National Ignition Facility (NIF) laser [1]. The assembly station, referred to as the Flexible Final Assembly Machine (FlexFAM) and shown in Figure 1, is a companion system to the earlier Final Assembly Machine (FAM) [2]. Both machines consist of a manipulator system integrated with an optical coordinate measuring machine (OCMM). The manipulator system has six groups of stacked axis used to manipulate the millimeter-sized target components with submicron precision, and utilizes the same force and torque feedback sensing as the FAM. Real-time dimensional metrology is provided by the OCMM's vision system and through-the-lens (TTL) laser-based height measuring probe. The manually actuated manipulator system of the FlexFAM provides a total of thirty degrees-of-freedom to the target components being assembled predominantly in a cubic centimeter work zone.

  19. A modernized high-pressure heater protection system for nuclear and thermal power stations

    NASA Astrophysics Data System (ADS)

    Svyatkin, F. A.; Trifonov, N. N.; Ukhanova, M. G.; Tren'kin, V. B.; Koltunov, V. A.; Borovkov, A. I.; Klyavin, O. I.

    2013-09-01

    Experience gained from operation of high-pressure heaters and their protection systems serving to exclude ingress of water into the turbine is analyzed. A formula for determining the time for which the high-pressure heater shell steam space is filled when a rupture of tubes in it occurs is analyzed, and conclusions regarding the high-pressure heater design most advisable from this point of view are drawn. A typical structure of protection from increase of water level in the shell of high-pressure heaters used in domestically produced turbines for thermal and nuclear power stations is described, and examples illustrating this structure are given. Shortcomings of components used in the existing protection systems that may lead to an accident at the power station are considered. A modernized protection system intended to exclude the above-mentioned shortcomings was developed at the NPO Central Boiler-Turbine Institute and ZioMAR Engineering Company, and the design solutions used in this system are described. A mathematical model of the protection system's main elements (the admission and check valves) has been developed with participation of specialists from the St. Petersburg Polytechnic University, and a numerical investigation of these elements is carried out. The design version of surge tanks developed by specialists of the Central Boiler-Turbine Institute for excluding false operation of the high-pressure heater protection system is proposed.

  20. Space Station Furnace Facility Preliminary Project Implementation Plan (PIP). Volume 2, Appendix 2

    NASA Technical Reports Server (NTRS)

    Perkey, John K.

    1992-01-01

    The Space Station Furnace Facility (SSFF) is an advanced facility for materials research in the microgravity environment of the Space Station Freedom and will consist of Core equipment and various sets of Furnace Module (FM) equipment in a three-rack configuration. This Project Implementation Plan (PIP) document was developed to satisfy the requirements of Data Requirement Number 4 for the SSFF study (Phase B). This PIP shall address the planning of the activities required to perform the detailed design and development of the SSFF for the Phase C/D portion of this contract.

  1. Operation Dominic, Shot Sword Fish. Project Officer's report - Project 1. 3b. Effects of an underwater nuclear explosion on hydroacoustic systems

    SciTech Connect

    McMillan, T.; La Houssaye, W.P.; Johnson, C.T.

    1985-09-01

    The objectives of Project 1.2 were to determine and evaluate the effects of an underwater nuclear explosion on the operational capabilities of shipboard sonar and other types of hydroacoustic systems. Project 1.3b included all measurements at ranges greater than 10 nautical miles and the results of these measurements constitute the subject of this report. This report concerns the effects of the underwater nuclear explosion, Sword Fish, on: (a) Long-range active detection systems at the first convergence zone (25 to 30 miles); (b) Passive shipboard or submarine sonars at a few hundred miles; and (c) Long-range passive detection and surveillance at Sound Surveillance System (SOSUS) and Missile Impact Locating System (MILS) stations at several hundred to several thousand miles. A submarine station at the first convergence zone and five shipboard stations at ranges from 200 miles to 5,000 miles recorded signals from hydrophones suspended at various depths to approximately 2,000 feet. Submarines on other assignments recorded signals on standard submarine sonar equipment on a not-to interfere basis. SOSUS and MILS stations operated normally during the period and also made special magnetic-tape and strip-chart recordings of signals from single hydrophones from before burst time to several hours after burst.

  2. Structural integrity analysis of the degraded drywell containment at the Oyster Creek Nuclear generating station.

    SciTech Connect

    Petti, Jason P.

    2007-01-01

    This study examines the effects of the degradation experienced in the steel drywell containment at the Oyster Creek Nuclear Generating Station. Specifically, the structural integrity of the containment shell is examined in terms of the stress limits using the ASME Boiler and Pressure Vessel (B&PV) Code, Section III, Division I, Subsection NE, and examined in terms of buckling (stability) using the ASME B&PV Code Case N-284. Degradation of the steel containment shell (drywell) at Oyster Creek was first observed during an outage in the mid-1980s. Subsequent inspections discovered reductions in the shell thickness due to corrosion throughout the containment. Specifically, significant corrosion occurred in the sandbed region of the lower sphere. Since the presence of the wet sand provided an environment which supported corrosion, a series of analyses were conducted by GE Nuclear Energy in the early 1990s. These analyses examined the effects of the degradation on the structural integrity. The current study adopts many of the same assumptions and data used in the previous GE study. However, the additional computational recourses available today enable the construction of a larger and more sophisticated structural model.

  3. Biofouling monitoring and control program at the Boston Edison Pilgrim Nuclear Station: A twelve year history

    SciTech Connect

    McDonald, D.J.; Armstrong, W.J.; Carucci, C.A.

    1996-08-01

    This paper reviews the history of the Biofouling Monitoring and Control Program at the Boston Edison Company Pilgrim Nuclear Power Station. The program was initially developed in 1982 in response to serious operations, maintenance and performance related problems due to biofouling in both the circulating and service water systems. Although implemented seven years prior to federal mandates under GL 89-13, this program also satisfies regulatory criteria for biofouling monitoring and control of nuclear service water systems. Since its inception, the impact of macrofouling on plant operation and availability has been significantly reduced. Stringent monitoring for blue mussels, installation of mechanical barriers to horseshoe crabs, improvements in screens, screenwash and debris removal systems, and an on-going commitment to biofouling control have reduced the number of condenser backwashes per year from > 40 (1989) to < 10. Depending on conditions and timing of a backwash, the resulting economic gain from this improvement alone can be 1.5 to more than 4 million dollars a year. Other improvements in related components and the service water system have also resulted in reduced maintenance related problems and an additional cost benefit to the plant. 13 refs., 6 figs., 1 tab.

  4. Monitoring the critical radiation exposure pathways at a BWR nuclear power station.

    PubMed

    Golden, J C; Chandrasekaran, E S; Kahn, B

    1982-06-01

    Iodine-131 in milk and gamma radiation from radionuclides in air in the environment of a 3-unit nuclear power station were measured at the levels predicted for airborne effluent. These measurements were part of a modified environmental radiological monitoring program to confirm the population doses computed from radionuclide release rates and environmental transfer models. The limits of detection were lowered relative to conventional monitoring programs by analyzing 21 L samples of milk for 131I and by determining external gamma radiation with a system that combined use of thermoluminescent dosimeters, pressurized ionization chambers, and NaI(T1) survey meters. For monitoring periods slightly longer than 6 months, during a time when fallout from atmospheric nuclear tests contributed very little, the average measured 131I concentration in milk was 0.1 pCi/L for cows on a nearby pasture and 0.02 pCi/L for cows at a more distant control location, compared to predicted values of 0.07 and 0.02 pCi/L, respectively; the average radiation exposure from airborne radionuclides measured at 16 nearby dosimeter locations was 7 mR, compared to the average of predicted values of 4 mR.

  5. The Role of Open Stations in Underground Nuclear Test Treaty Monitoring

    NASA Astrophysics Data System (ADS)

    van der Vink, G. E.; van der Vink, G. E.

    2001-05-01

    Although the International Monitoring System is fixed by the treaty, seismic stations will continue to be installed around the world in regional networks designed for earthquake hazard assessment and scientific research. For many areas of the world, the high-density coverage of these regional networks will inevitably provide a capability that far surpasses that of the official treaty monitoring system. It is quite likely, therefore, that if evidence of a clandestine nuclear weapon test is discovered, it will be with data collection facilities that were never specifically intended for nuclear monitoring. Global communication networks will provide open access to thousands of resources that can be used to monitor environmental factors and help characterize a suspicious seismic event. When such events occur, Internet sites containing the relevant (and irrelevant) data are likely to appear long before intelligence information can be digested by governments or before memos can work their way through official channels. Competitive news organizations will not wait for the carefully crafted prose of official press releases before pursuing alternative technical judgments and scientific opinions. The future challenge for treaty monitoring may no longer be the acquisition of data, but rather the integration of the vast and continually evolving array of global information sources into their analytical systems. The new challenge for seismology is to maintain the culture of free and open data exchange within this new environment, despite the inevitable controversies and misuse.

  6. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    SciTech Connect

    GREENE,G.A.; GUPPY,J.G.

    1998-08-01

    This is the final report on the INSP project entitled, ``Kola Confinement Leaktightness'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.1. This project was initiated in February 1993 to assist the Russians to reduce risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Units 1 and 2, through upgrades in the confinement performance to reduce the uncontrolled leakage rate. The major technical objective of this-project was to improve the leaktightness of the Kola NPP VVER confinement boundaries, through the application of a variety of sealants to penetrations, doors and hatches, seams and surfaces, to the extent that current technology permitted. A related objective was the transfer, through training of Russian staff, of the materials application procedures to the staff of the Kola NPP. This project was part of an overall approach to minimizing uncontrolled releases from the Kola NPP VVER440/230s in the event of a serious accident, and to thereby significantly mitigate the consequences of such an accident. The US provided materials, application technology, and applications equipment for application of sealant materials, surface coatings, potting materials and gaskets, to improve the confinement leaktightness of the Kola VVER-440/23Os. The US provided for training of Russian personnel in the applications technology.

  7. Advanced nuclear reactor public opinion project. Interim report

    SciTech Connect

    Benson, B.

    1991-07-25

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

  8. Resource Letter MP-1: The Manhattan Project and related nuclear research

    NASA Astrophysics Data System (ADS)

    Reed, B. Cameron

    2005-09-01

    This Resource Letter provides a guide to literature on the Manhattan Project and related nuclear research. Books and journal articles are cited for the following topics: general works, technical works, biographical and autobiographical works, the German nuclear program, and technical papers of historical interest. A list of videos and websites dealing with the Manhattan Project, nuclear weapons, and nuclear issues is also given.

  9. Space power stations - Space construction, transportation, and pre-development, space project requirements

    NASA Technical Reports Server (NTRS)

    Piland, R.

    1977-01-01

    Several features of solar energy space power stations are discussed. An end-to-end analysis of a system using silicon solar cells is reviewed, and the merits of construction in low earth orbit and in geosynchronous orbit are compared. A suggested space construction procedure, described in detail, would use a 'beam builder', an automated machine, to fabricate the first sublevel truss structural members from strip stock material that is stored on reels. An assembly jig would then be used to position a number of beam builders in the proper location and to support the beams as they are produced to facilitate joining them to form the final space power station structure. Space projects for evaluating the construction concept are proposed, and a possible space construction sequence is considered. Space transportation that would be required in conjunction with the space power station is described.

  10. 75 FR 14634 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit Nos. 1, 2, and 3; Environmental...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-26

    ...-49, issued to Dominion Nuclear Connecticut, Inc. (DNC or the licensee) for operation of Millstone... with certain new requirements contained in 10 CFR 73.55 by the March 31, 2010, deadline. DNC has... beyond the date required by 10 ] CFR part 73, for certain alarm station requirements. DNC has...

  11. [Influence of working shift on nervous system functional state in operators of control unit in nuclear power station].

    PubMed

    Laskova, I V

    2009-01-01

    Operators of control unit in nuclear power station, if after the working shift, were diagnosed as having changes of cerebral functions and vegetative regulation, with sometimes increased blood pressure up to the level of cerebrovascular disease risk, and with higher spectral density of main EEG rhythms intensity.

  12. 78 FR 6839 - Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1, 2, and 3 Denial of Amendment to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-31

    ... COMMISSION Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1, 2, and 3 Denial of Amendment to... Commission (NRC) has denied a request by Duke Energy Carolinas, LLC, (licensee) for an amendment to Renewed... required dates to meet certain conditions associated with the transition of the plant's fire...

  13. 78 FR 45575 - Duke Energy Carolinas, LLC; Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-29

    ... COMMISSION [Docket Nos.: 72-1004, 72-40, 50-269, 50-270, 50-287; and NRC-2013- 0135] Duke Energy Carolinas, LLC; Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel Storage Installation AGENCY... response to a request submitted by Duke Energy Carolinas, LLC., on August 13, 2012, for the Oconee...

  14. Next Generation Nuclear Plant Project 2009 Status Report

    SciTech Connect

    Larry Demick; Jim Kinsey; Keith Perry; Dave Petti

    2010-05-01

    The mission of the NGNP Project is to broaden the environmental and economic benefits of nuclear energy technology to the United States and other economies by demonstrating its applicability to market sectors not served by light water reactors (LWRs). Those markets typically use fossil fuels to fulfill their energy needs, and high temperature gas-cooled reactors (HTGRs) like the NGNP can reduce this dependence and the resulting carbon footprint.

  15. Government research and development summaries: Nuclear project briefs. Irregular

    SciTech Connect

    Not Available

    1994-01-01

    Nuclear, Te, Ti Project Briefs describe the status of all R D program submitted to the Power Information Center by the government sponsors in energy conversion from fission, fusion, and radioisotope power sources and other thermal systems that use thermionic systems. These briefs also follow related investigations of plasma dynamics. The document is not to be reproduced, in whole or in part, for dissemination outside your own organization nor may it be reproduced for advertising or sales promotion purposes.

  16. PROGRESS REPORT: COFIRING PROJECTS FOR WILLOW ISLAND AND ALBRIGHT GENERATING STATIONS

    SciTech Connect

    K. Payette; D. Tillman

    2001-07-01

    During the period April 1, 2001--June 30, 2001, Allegheny Energy Supply Co., LLC (Allegheny) accelerated construction of the Willow Island cofiring project, completed the installation of foundations for the fuel storage facility, the fuel receiving facility, and the processing building. Allegheny received all processing equipment to be installed at Willow Island. Allegheny completed the combustion modeling for the Willow Island project. During this time period construction of the Albright Generating Station cofiring facility was completed, with few items left for final action. The facility was dedicated at a ceremony on June 29. Initial testing of cofiring at the facility commenced. This report summarizes the activities associated with the Designer Opportunity Fuel program, and demonstrations at Willow Island and Albright Generating Stations. It details the construction activities at both sites along with the combustion modeling at the Willow Island site.

  17. Accident at the Fukushima Dai-ichi Nuclear Power Stations of TEPCO —Outline & lessons learned—

    PubMed Central

    TANAKA, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others. PMID:23138450

  18. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report Sep-Nov 81

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1982-06-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. In the fall of 1981, Teredo bartschi remained in Oyster Creek despite continuous prolonged outages of the Oyster Creek Nuclear Generating Station.

  19. Steam Dryer Segmentation and Packaging at Grand Gulf Nuclear Station - 13577

    SciTech Connect

    Kreitman, Paul J.; Sirianni, Steve R.; Pillard, Mark M.

    2013-07-01

    Entergy recently performed an Extended Power Up-rate (EPU) on their Grand Gulf Nuclear Station, near Port Gibson, Mississippi. To support the EPU, a new Steam Dryer Assembly was installed during the last refueling outage. Due to limited access into the containment, the large Replacement Steam Dryer (RSD) had to be brought into the containment in pieces and then final assembly was completed on the refueling floor before installation into the reactor. Likewise, the highly contaminated Original Steam Dryer (OSD) had to be segmented into manageable sections, loaded into specially designed shielded containers, and rigged out of containment where they will be safely stored until final disposal is accomplished at an acceptable waste repository. Westinghouse Nuclear Services was contracted by Entergy to segment, package and remove the OSD from containment. This work was performed on critical path during the most recent refueling outage. The segmentation was performed underwater to minimize radiation exposure to the workers. Special hydraulic saws were developed for the cutting operations based on Westinghouse designs previously used in Sweden to segment ABB Reactor Internals. The mechanical cutting method was selected because of its proven reliability and the minimal cutting debris that is generated by the process. Maintaining stability of the large OSD sections during cutting was accomplished using a custom built support stand that was installed into the Moisture Separator Pool after the Moisture Separator was installed back in the reactor vessel. The OSD was then moved from the Steam Dryer Pool to the Moisture Separator Pool for segmentation. This scenario resolved the logistical challenge of having two steam dryers and a moisture separator in containment simultaneously. A water filtration/vacuum unit was supplied to maintain water clarity during the cutting and handling operations and to collect the cutting chips. (authors)

  20. Radiation Dose Reduction Efficiency of Buildings after the Accident at the Fukushima Daiichi Nuclear Power Station

    PubMed Central

    Monzen, Satoru; Hosoda, Masahiro; Osanai, Minoru; Tokonami, Shinji

    2014-01-01

    Numerous radionuclides were released from the Fukushima Daiichi Nuclear Power Station (F1-NPS) in Japan following the magnitude 9.0 earthquake and tsunami on March 11, 2011. Local residents have been eager to calculate their individual radiation exposure. Thus, absorbed dose rates in the indoor and outdoor air at evacuation sites in the Fukushima Prefecture were measured using a gamma-ray measuring devices, and individual radiation exposure was calculated by assessing the radiation dose reduction efficiency (defined as the ratio of absorbed dose rate in the indoor air to the absorbed dose rate in the outdoor air) of wood, aluminum, and reinforced concrete buildings. Between March 2011 and July 2011, dose reduction efficiencies of wood, aluminum, and reinforced concrete buildings were 0.55±0.04, 0.15±0.02, and 0.19±0.04, respectively. The reduction efficiency of wood structures was 1.4 times higher than that reported by the International Atomic Energy Agency. The efficiency of reinforced concrete was similar to previously reported values, whereas that of aluminum structures has not been previously reported. Dose reduction efficiency increased in proportion to the distance from F1-NPS at 8 of the 18 evacuation sites. Time variations did not reflect dose reduction efficiencies at evacuation sites although absorbed dose rates in the outdoor air decreased. These data suggest that dose reduction efficiency depends on structure types, levels of contamination, and evacuee behaviors at evacuation sites. PMID:24999992

  1. Direction on characterization of fuel debris for defueling process in Fukushima Daiichi Nuclear Power Station

    SciTech Connect

    Yano, Kimihiko; Kitagaki, Toru; Ikeuchi, Hirotomo; Wakui, Ryohei; Higuchi, Hidetoshi; Kaji, Naoya; Koizumi, Kenji; Washiya, Tadahiro

    2013-07-01

    For the decommissioning of Fukushima Daiichi Nuclear Power Station (1F), defueling of the fuel debris in the reactor core of Units 1-3 is planned to start within 10 years. Preferential items in the characterization of the fuel debris were identified for this work, in which the procedure and handling tools were assumed on the basis of information on 1F and experience after the Three Mile Island Unit 2 (TMI-2) accident. The candidates for defueling tools for 1F were selected from among the TMI- 2 defueling tools. It was found that they could be categorized into six groups according to their operating principles. The important properties of the fuel debris for defueling were selected considering the effect of the target materials on the tool performance. The selected properties are shape, size, density, thermal conductivity, heat capacity, melting point, hardness, elastic modulus, and fracture toughness. Of these properties, the mechanical properties (hardness, elastic modulus, fracture toughness) were identified as preferential items, because too few data on these characteristics of fuel debris are available in past severe accident studies. (authors)

  2. Nuclear Simulation and Radiation Physics Investigations of the Target Station of the European Spallation Neutron Source

    SciTech Connect

    Filges, Detlef; Neef, Ralf-Dieter; Schaal, Hartwig

    2000-10-15

    The European Spallation Neutron Source (ESS) delivers high-intensity pulsed particle beams with 5-MW average beam power at 1.3-GeV incident proton energy. This causes sophisticated demands on material and geometry choices and a very careful optimization of the whole target system. Therefore, complex and detailed particle transport models and computer code systems have been developed and used to study the nuclear assessment of the ESS target system. The purpose here is to describe the methods of calculation mainly based on the Monte Carlo code to show the performance of the ESS target station. The interesting results of the simulations of the mercury target system are as follows: time-dependent neutron flux densities, energy deposition and heating, radioactivity and afterheat, materials damage by radiation, and high-energy source shielding. The results are discussed in great detail. The validity of codes and models, further requirements to improve the methods of calculation, and the status of running and planned experiments are given also.

  3. Radiation dose reduction efficiency of buildings after the accident at the Fukushima Daiichi Nuclear Power Station.

    PubMed

    Monzen, Satoru; Hosoda, Masahiro; Osanai, Minoru; Tokonami, Shinji

    2014-01-01

    Numerous radionuclides were released from the Fukushima Daiichi Nuclear Power Station (F1-NPS) in Japan following the magnitude 9.0 earthquake and tsunami on March 11, 2011. Local residents have been eager to calculate their individual radiation exposure. Thus, absorbed dose rates in the indoor and outdoor air at evacuation sites in the Fukushima Prefecture were measured using a gamma-ray measuring devices, and individual radiation exposure was calculated by assessing the radiation dose reduction efficiency (defined as the ratio of absorbed dose rate in the indoor air to the absorbed dose rate in the outdoor air) of wood, aluminum, and reinforced concrete buildings. Between March 2011 and July 2011, dose reduction efficiencies of wood, aluminum, and reinforced concrete buildings were 0.55 ± 0.04, 0.15 ± 0.02, and 0.19 ± 0.04, respectively. The reduction efficiency of wood structures was 1.4 times higher than that reported by the International Atomic Energy Agency. The efficiency of reinforced concrete was similar to previously reported values, whereas that of aluminum structures has not been previously reported. Dose reduction efficiency increased in proportion to the distance from F1-NPS at 8 of the 18 evacuation sites. Time variations did not reflect dose reduction efficiencies at evacuation sites although absorbed dose rates in the outdoor air decreased. These data suggest that dose reduction efficiency depends on structure types, levels of contamination, and evacuee behaviors at evacuation sites.

  4. An aerial radiological survey of the Pilgrim Station Nuclear Power Plant and surrounding area, Plymouth, Massachusetts

    SciTech Connect

    Proctor, A.E.

    1997-06-01

    Terrestrial radioactivity surrounding the Pilgrim Station Nuclear Power Plant was measured using aerial radiolog- ical survey techniques. The purpose of this survey was to document exposure rates near the plant and to identify unexpected, man-made radiation sources within the survey area. The surveyed area included land areas within a three-mile radius of the plant site. Data were acquired using an airborne detection system that employs sodium iodide, thallium-activated detectors. Exposure rate and photopeak counts were computed from these data and plotted on aerial photographs of the survey area. Several ground-based exposure measurements were made for comparison with the,aerial survey results. Exposure rates in areas surrounding the plant site varied from 6 to 10 microroentgens per hour, with exposure rates below 6 microroentgens per hour occurring over bogs and marshy areas. Man-made radiation was found to be higher than background levels at the plant site. Radation due to nitrogen-1 6, which is produced in the steam cycle of a boiling-water reactor, was the primaty source of activity found at the plant site. Cesium-137 activity at levels slightly above those expected from natural fallout was found at isolated locations inland from the plant site. No other detectable sources of man-made radioactivity were found.

  5. ASSESSMENT OF RADIONUCLIDE RELEASE FROM CONTAMINATED CONCRETE AT THE YANKEE NUCLEAR POWER STATION.

    SciTech Connect

    SULLIVAN, T.

    2004-03-01

    Yankee Atomic Energy Company (YAEC) is considering allowing portions of existing structures at the Yankee Nuclear Power Station (YNPS) to remain on site at the time of license termination. Accordingly, release of residual radioactive contaminants (i.e., H-3, C-14, Co-60, Ni-63, Sr-90, and Cs-137) from remaining subsurface concrete structures (Darman, 2004) and dose due to that release must be evaluated. Analyses were performed using DUST-MS to assess the rate of release for each radionuclide from the concrete, based upon an assumed concentration of 1 pCi/g and a concrete density of 2.5 g/cm{sup 3}. Using the same assumptions that were applied to the soil DCGL calculation (and where appropriate, the same input parameters), RESRAD was used to calculate the dose from water pathways. Values for selected RESRAD input parameters were chosen to match the release rate calculated by DUST-MS. The results indicated that Cs-137 yielded the highest dose.

  6. HT to HTO conversion and field experiments near Darlington Nuclear Power Generating Station (DNPGS) site.

    PubMed

    Kim, S B; Stuart, M; Bredlaw, M; Festarini, A; Beaton, D

    2014-06-01

    The Canadian input parameters related to tritiated hydrogen gas (HT) used in tritium dose models are currently based on experiments performed at the Chalk River Laboratories (CRL) site in 1986, 1987 and 1994. There is uncertainty in how well other sites experiencing atmospheric HT releases are represented by these data. In order to address this uncertainty, HT to HTO conversion factors were evaluated at different locations near the Darlington Nuclear Power Generating Station (DNPGS) site using various experimental approaches. These were D2 gas exposure chamber experiments, atmospheric tritium measurements, and HTO and OBT measurements in vegetation and soil. In addition to these field experiments, chamber experiments were conducted using HT gas on field soil samples. The suggested Canadian input parameters for atmospheric tritium releases estimate the total fraction of HT oxidized in air and in soil, at the site, to be up to a maximum of 2.4%. Based on the more limited data obtained near DNPGS in early spring, this fraction would likely be closer to 0.5%. The result suggests that current parameters provide a conservative estimate for the DNPGS site.

  7. Radiation situation in Kamchatka after the Fukushima nuclear power station accident

    NASA Astrophysics Data System (ADS)

    Sidorin, A. I.

    2013-12-01

    The chronology of events in Kamchatka related to the threat of radioactive contamination of the territory as a result of the Fukushima-1 nuclear power station (NPS) accident in Japan is briefly reviewed based on the published data. The accident happened on March 11, 2011, after a strong earthquake near the coast of Japan and the giant tsunami followed by the earthquake. The power supply was damaged and, as a result, the cooling system of NPS reactors was destroyed. Although the reactors did not explode, radioactive emissions from the damaged NPS discharged into the atmosphere and spread over large areas by the air flows. Information about the radiation situation in Kamchatka is controversial. Therefore, the author carried out regular monitoring of the radiation background during a hiking trip in Kamchatka in August 2011. The data are presented in this paper. It was concluded that the radiation background along the route of the trip was consistent (within the accuracy of measurement methods) with the normal values of a natural background. A thorough analysis of air, soil, food samples, etc., is required for a more detailed study to identify the presence of radionuclides in the atmospheric emissions from the damaged NPS in Japan.

  8. Anisotropic structure of the Pannonian basin: Reprocessing SKS splitting data for the CBP project stations

    NASA Astrophysics Data System (ADS)

    Qorbani, Ehsan; Bokelmann, Götz; Kovács, Istvan; Falus, György

    2014-05-01

    The Carpathian-Pannonian region (CPR) is the northeastern end of the Alpine mountain belt. In the western Alps, available results of anisotropy investigations (shear wave splitting) show clear belt-parallel anisotropy (fast orientation). In the eastern Alps this pattern not only is broken but also does not follow the strike of Carpathians and Dinarides. This study is aimed at evaluating the seismic anisotropy of the upper mantle beneath the CPR concentrating on the eastward elongation of the fast anisotropic pattern of the eastern Alps. We use data recorded by the temporary stations, set up for the Carpathian Basin Project (CBP), extending from the Vienna basin through Hungary into Serbia. Initial results from the CBP project (Stuart et al., 2007; Kovács et al., 2012) presented the average fast anisotropy directions for the Carpathian-Pannonian region including a subset of permanent broadband stations in the eastern Alps. While some of the results agree with another recently published anisotropy analysis of the Eastern Alps (Bokelmann et al., 2013), some don`t. For this reason, the study at hand was primarily concerned with understanding observed differences in fast orientations and also with possible geodynamic interpretations. With this intention, we reprocess data from 45 temporary CBP stations consisting recorded waveform of teleseismic events with magnitude greater than 6.0 that have occurred in the distance range from 90° to 130° between 2005 and 2007. We utilize the minimum energy method (Silver and Chan, 1991) to measure the splitting delay time and fast axis polarization direction, and show the individual measurements of anisotropic parameters at single stations. The dominant fast polarization orientation is NW-SE for the Hungarian part of the stations as well as at the stations located in the easternmost of the Pannonian Basin. This orientation turns more into WNW-ESE at the stations situated in Austria, mostly NW of the Vienna basin. Apart from

  9. Status of the nuclear measurement stations for the process control of spent fuel reprocessing at AREVA NC/La Hague

    SciTech Connect

    Eleon, Cyrille; Passard, Christian; Hupont, Nicolas; Estre, Nicolas; Battel, Benjamin; Doumerc, Philippe; Dupuy, Thierry; Batifol, Marc; Grassi, Gabriele

    2015-07-01

    Nuclear measurements are used at AREVA NC/La Hague for the monitoring of spent fuel reprocessing. The process control is based on gamma-ray spectroscopy, passive neutron counting and active neutron interrogation, and gamma transmission measurements. The main objectives are criticality and safety, online process monitoring, and the determination of the residual fissile mass and activities in the metallic waste remained after fuel shearing and dissolution (empty hulls, grids, end pieces), which are put in radioactive waste drums before compaction. The whole monitoring system is composed of eight measurement stations which will be described in this paper. The main measurement stations no. 1, 3 and 7 are needed for criticality control. Before fuel element shearing for dissolution, station no. 1 allows determining the burn-up of the irradiated fuel by gamma-ray spectroscopy with HP Ge (high purity germanium) detectors. The burn-up is correlated to the {sup 137}Cs and {sup 134}Cs gamma emission rates. The fuel maximal mass which can be loaded in one bucket of the dissolver is estimated from the lowest burn-up fraction of the fuel element. Station no. 3 is dedicated to the control of the correct fuel dissolution, which is performed with a {sup 137}Cs gamma ray measurement with a HP Ge detector. Station no. 7 allows estimating the residual fissile mass in the drums filled with the metallic residues, especially in the hulls, from passive neutron counting (spontaneous fission and alpha-n reactions) and active interrogation (fission prompt neutrons induced by a pulsed neutron generator) with proportional {sup 3}He detectors. The measurement stations have been validated for the reprocessing of Uranium Oxide (UOX) fuels with a burn-up rate up to 60 GWd/t. This paper presents a brief overview of the current status of the nuclear measurement stations. (authors)

  10. 75 FR 52374 - National Environmental Policy Act; NASA Glenn Research Center Plum Brook Station Wind Farm Project

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-25

    ... Environmental Policy Act; NASA Glenn Research Center Plum Brook Station Wind Farm Project AGENCY: National... scoping and prepare an Environmental Impact Statement (EIS) for the NASA GRC Plum Brook Station Wind Farm... scoping is for NASA to obtain public comments on construction and operation of the wind farm. The...

  11. 77 FR 69506 - Exelon Generation Company, LLC., Oyster Creek Nuclear Generating Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-19

    ... erroneous information. FOR FURTHER INFORMATION CONTACT: John G. Lamb, Office of Nuclear Reactor Regulation.... For the Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. BILLING CODE 7590-01-P...

  12. 78 FR 71675 - License Amendment Application for Vermont Yankee Nuclear Power Station

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-29

    ... 20852. FOR FURTHER INFORMATION CONTACT: Douglas Pickett, Office of Nuclear Reactor Regulation, U.S..., Office of Nuclear Reactor Regulation. BILLING CODE 7590-01-P ... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  13. Optical Time Projection Chamber for imaging nuclear decays

    NASA Astrophysics Data System (ADS)

    Miernik, K.; Dominik, W.; Czyrkowski, H.; Dabrowski, R.; Fomitchev, A.; Golovkov, M.; Janas, Z.; Kuśmierz, W.; Pfützner, M.; Rodin, A.; Stepantsov, S.; Slepniev, R.; Ter-Akopian, G. M.; Wolski, R.

    2007-10-01

    We present a novel type of a Time Projection Chamber in which tracks of charged particles ionizing an active gas volume are recorded by means of optical signals. By combining a CCD camera image with the electron drift-time profile measured by a photomultiplier, it is possible to reconstruct trajectories of particles in three dimensions. The chamber was developed to study exotic nuclear decays in which charged particles are emitted. The results of first measurements will be demonstrated in which beta-delayed protons from 13O, the two-alpha decay of 8Be, and the triple-alpha decay of 12C excited states were recorded.

  14. Environmental Assessment for the Warren Station externally fired combined cycle demonstration project

    SciTech Connect

    1995-04-01

    The proposed Penelec project is one of 5 projects for potential funding under the fifth solicitation under the Clean Coal Technology program. In Penelec, two existing boilers would be replaced at Warren Station, PA; the new unit would produce 73 MW(e) in a combined cycle mode (using both gas-fired and steam turbines). The project would fill the need for a full utility-size demonstration of externally fire combined cycle (EFCC) technology as the next step toward commercialization. This environmental assessment was prepared for compliance with NEPA; its purpose is to provide sufficient basis for determining whether to prepare an environmental impact statement or to issue a finding of no significant impact. It is divided into the sections: purpose and need for proposed action; alternatives; brief description of affected environment; environmental consequences, including discussion of commercial operation beyond the demonstration period.

  15. NASA Systems Autonomy Demonstration Project - Development of Space Station automation technology

    NASA Technical Reports Server (NTRS)

    Bull, John S.; Brown, Richard; Friedland, Peter; Wong, Carla M.; Bates, William

    1987-01-01

    A 1984 Congressional expansion of the 1958 National Aeronautics and Space Act mandated that NASA conduct programs, as part of the Space Station program, which will yield the U.S. material benefits, particularly in the areas of advanced automation and robotics systems. Demonstration programs are scheduled for automated systems such as the thermal control, expert system coordination of Station subsystems, and automation of multiple subsystems. The programs focus the R&D efforts and provide a gateway for transfer of technology to industry. The NASA Office of Aeronautics and Space Technology is responsible for directing, funding and evaluating the Systems Autonomy Demonstration Project, which will include simulated interactions between novice personnel and astronauts and several automated, expert subsystems to explore the effectiveness of the man-machine interface being developed. Features and progress on the TEXSYS prototype thermal control system expert system are outlined.

  16. Comparison of MELCOR modeling techniques and effects of vessel water injection on a low-pressure, short-term, station blackout at the Grand Gulf Nuclear Station

    SciTech Connect

    Carbajo, J.J.

    1995-06-01

    A fully qualified, best-estimate MELCOR deck has been prepared for the Grand Gulf Nuclear Station and has been run using MELCOR 1.8.3 (1.8 PN) for a low-pressure, short-term, station blackout severe accident. The same severe accident sequence has been run with the same MELCOR version for the same plant using the deck prepared during the NUREG-1150 study. A third run was also completed with the best-estimate deck but without the Lower Plenum Debris Bed (BH) Package to model the lower plenum. The results from the three runs have been compared, and substantial differences have been found. The timing of important events is shorter, and the calculated source terms are in most cases larger for the NUREG-1150 deck results. However, some of the source terms calculated by the NUREG-1150 deck are not conservative when compared to the best-estimate deck results. These results identified some deficiencies in the NUREG-1150 model of the Grand Gulf Nuclear Station. Injection recovery sequences have also been simulated by injecting water into the vessel after core relocation started. This marks the first use of the new BH Package of MELCOR to investigate the effects of water addition to a lower plenum debris bed. The calculated results indicate that vessel failure can be prevented by injecting water at a sufficiently early stage. No pressure spikes in the vessel were predicted during the water injection. The MELCOR code has proven to be a useful tool for severe accident management strategies.

  17. PRELIMINARY NUCLEAR CRITICALITY NUCLEAR SAFETY EVLAUATION FOR THE CONTAINER SURVEILLANCE AND STORAGE CAPABILITY PROJECT

    SciTech Connect

    Low, M; Matthew02 Miller, M; Thomas Reilly, T

    2007-04-30

    Washington Safety Management Solutions (WSMS) provides criticality safety services to Washington Savannah River Company (WSRC) at the Savannah River Site. One activity at SRS is the Container Surveillance and Storage Capability (CSSC) Project, which will perform surveillances on 3013 containers (hereafter referred to as 3013s) to verify that they meet the Department of Energy (DOE) Standard (STD) 3013 for plutonium storage. The project will handle quantities of material that are greater than ANS/ANSI-8.1 single parameter mass limits, and thus required a Nuclear Criticality Safety Evaluation (NCSE). The WSMS methodology for conducting an NCSE is outlined in the WSMS methods manual. The WSMS methods manual currently follows the requirements of DOE-O-420.1B, DOE-STD-3007-2007, and the Washington Savannah River Company (WSRC) SCD-3 manual. DOE-STD-3007-2007 describes how a NCSE should be performed, while DOE-O-420.1B outlines the requirements for a Criticality Safety Program (CSP). The WSRC SCD-3 manual implements DOE requirements and ANS standards. NCSEs do not address the Nuclear Criticality Safety (NCS) of non-reactor nuclear facilities that may be affected by overt or covert activities of sabotage, espionage, terrorism or other security malevolence. Events which are beyond the Design Basis Accidents (DBAs) are outside the scope of a double contingency analysis.

  18. Extreme Light Infrastructure - Nuclear Physics Eli-Np Project

    NASA Astrophysics Data System (ADS)

    Gales, S.

    2015-06-01

    The development of high power lasers and the combination of such novel devices with accelerator technology has enlarged the science reach of many research fields, in particular High energy, Nuclear and Astrophysics as well as societal applications in Material Science, Nuclear Energy and Medicine. The European Strategic Forum for Research Infrastructures (ESFRI) has selected a proposal based on these new premises called "ELI" for Extreme Light Infrastructure. ELI will be built as a network of three complementary pillars at the frontier of laser technologies. The ELI-NP pillar (NP for Nuclear Physics) is under construction near Bucharest (Romania) and will develop a scientific program using two 10 PW class lasers and a Back Compton Scattering High Brilliance and Intense Low Energy Gamma Beam , a marriage of Laser and Accelerator technology at the frontier of knowledge. In the present paper, the technical description of the facility, the present status of the project as well as the science, applications and future perspectives will be discussed.

  19. 76 FR 1197 - Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-07

    ... Operations Branch, Division of License Renewal, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory... Branch, Division of License Renewal, Office of Nuclear Reactor Regulation. BILLING CODE 7590-01-P ... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  20. Sorption (Kd) measurements in support of dose assessments for Zion Nuclear Station Decommissioning

    SciTech Connect

    Yim S. P.; Sullivan T.; Milian, L.

    2012-12-12

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with “clean” concrete demolition debris from the above grade parts of the facility. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) was performed to provide site-specific data for performance assessment calculations to support the request to terminate the NRC license and allow unrestricted use of the facility. Specifically, this study measured the distribution coefficient for five radionuclides of concern using site-specific soils and groundwater. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the soil or concrete that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides of concern are Fe-55, Co-60, Ni-63, Sr-90, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90. Site-specific soils included disturbed sand (sand removed during construction and used as backfill), native sand, silt/clay and silt. In addition, concrete cores from the Unit-1 Containment Building and the Crib House were broken into particles less than 2 mm in size and tested to obtain distribution coefficients for the five nuclides.

  1. Ada compiler evaluation on the Space Station Freedom Software Support Environment project

    NASA Technical Reports Server (NTRS)

    Badal, D. L.

    1989-01-01

    This paper describes the work in progress to select the Ada compilers for the Space Station Freedom Program (SSFP) Software Support Environment (SSE) project. The purpose of the SSE Ada compiler evaluation team is to establish the criteria, test suites, and benchmarks to be used for evaluating Ada compilers for the mainframes, workstations, and the realtime target for flight- and ground-based computers. The combined efforts and cooperation of the customer, subcontractors, vendors, academia and SIGAda groups made it possible to acquire the necessary background information, benchmarks, test suites, and criteria used.

  2. A novel design project for space solar power station (SSPS-OMEGA)

    NASA Astrophysics Data System (ADS)

    Yang, Yang; Zhang, Yiqun; Duan, Baoyan; Wang, Dongxu; Li, Xun

    2016-04-01

    The space solar power station (SSPS) capable of providing earth with primary power has been researched for 50 years. The SSPS is a tremendous design involving optics, mechanics, electromagnetism, thermology, control, and other disciplines. This paper presents a novel design project for SSPS named OMEGA. The space segment of the proposed GEO-based SSPS is composed of four main parts, such as spherical solar power collector, hyperboloid photovoltaic (PV) cell array, power management and distribution (PMAD) and microwave transmitting antenna. Principle of optics, structure configuration, wired and wireless power transmissions are presented.

  3. Uranium from German Nuclear Power Projects of the 1940s— A Nuclear Forensic Investigation

    PubMed Central

    Mayer, Klaus; Wallenius, Maria; Lützenkirchen, Klaus; Horta, Joan; Nicholl, Adrian; Rasmussen, Gert; van Belle, Pieter; Varga, Zsolt; Buda, Razvan; Erdmann, Nicole; Kratz, Jens-Volker; Trautmann, Norbert; Fifield, L Keith; Tims, Stephen G; Fröhlich, Michaela B; Steier, Peter

    2015-01-01

    Here we present a nuclear forensic study of uranium from German nuclear projects which used different geometries of metallic uranium fuel.3b,d, 4 Through measurement of the 230Th/234U ratio, we could determine that the material had been produced in the period from 1940 to 1943. To determine the geographical origin of the uranium, the rare-earth-element content and the 87Sr/86Sr ratio were measured. The results provide evidence that the uranium was mined in the Czech Republic. Trace amounts of 236U and 239Pu were detected at the level of their natural abundance, which indicates that the uranium fuel was not exposed to any major neutron fluence. PMID:26501922

  4. NASA systems autonomy demonstration project: Advanced automation demonstration of Space Station Freedom thermal control system

    NASA Technical Reports Server (NTRS)

    Dominick, Jeffrey; Bull, John; Healey, Kathleen J.

    1990-01-01

    The NASA Systems Autonomy Demonstration Project (SADP) was initiated in response to Congressional interest in Space station automation technology demonstration. The SADP is a joint cooperative effort between Ames Research Center (ARC) and Johnson Space Center (JSC) to demonstrate advanced automation technology feasibility using the Space Station Freedom Thermal Control System (TCS) test bed. A model-based expert system and its operator interface were developed by knowledge engineers, AI researchers, and human factors researchers at ARC working with the domain experts and system integration engineers at JSC. Its target application is a prototype heat acquisition and transport subsystem of a space station TCS. The demonstration is scheduled to be conducted at JSC in August, 1989. The demonstration will consist of a detailed test of the ability of the Thermal Expert System to conduct real time normal operations (start-up, set point changes, shut-down) and to conduct fault detection, isolation, and recovery (FDIR) on the test article. The FDIR will be conducted by injecting ten component level failures that will manifest themselves as seven different system level faults. Here, the SADP goals, are described as well as the Thermal Control Expert System that has been developed for demonstration.

  5. Colorado School of Mines low energy nuclear physics project

    SciTech Connect

    Cecil, F.E.

    1991-01-02

    A major accomplishment of this project in the past year is the completion of a fairly comprehensive paper describing the survey of radiative capture reactions of protons on light nuclei at low energies. In addition we have completed a preliminary set of measurements of (d,p)/(d,{alpha}) cross section ratios on the charge symmetric nuclei {sup 6}Li and {sup 10}B as a test of the Oppenheimer-Phillips effect. While the {sup 6}Li data remain inconclusive, the {sup 10}B data show solid evidence for the Oppenheimer-Phillips enhancement of the (d,p) reaction relative to the (d,{alpha}) reaction for deuteron bombarding energies below about 100 keV. We have continued our investigation of fusion reaction products from deuterium-metal systems at room temperatures with the startling observation of intense burst of energetic charged particles from deuterium gas loaded thin titaium foils subject to non-equilibrium thermal and electrical conditions. We have completed two projects involving the application of the low energy particle accelerator to material science problems; firstly a study of the transformation of crystalline to amorphous Fe-Zr systems by proton irradiation and secondly the effects of ion bombardment on the critical temperature of YBCO high-temperature superconductors. Finally we have made progress in several instrumentation projects which will be used in some of the up-coming measurements of nuclear cross sections at very low energies.

  6. Project of a Near-Real-Time Sismo-acoustic Submarine Station for offshore monitoring (NRTSSS)

    NASA Astrophysics Data System (ADS)

    D'Anna, G.; Calore, D.; Mangano, G.; D'Alessandro, A.; Favali, P.

    2011-12-01

    The INGV seismic network ensures reliable and continuous monitoring of the Italian territory. However, the peculiarity of the Italian peninsula, characterised by an intense offshore geodynamic and seismic activity, requires the extension of the seismic monitoring to the sea. The aim of this project is: - to identify bottleneck is related to the construction, installation and use of underwater seismic station; - to define the most appropriate and low-cost architecture to guarantee the minimum functionality required for a seismic station. In order to obtain reliable seafloor seismic signals integrated to land-based network, the requirements to be fulfill are: - an acceptable coupling with the seabed; - the orientation of the components with respect to the magnetic North and to the verticality; - the correct time stamp of the data; - the data transfer to the land for the integration. Currently, the optimal solution for offshore seismic station is a cable connection to power and real-time data transfer, like the case of Western Ionian Sea cabled observatory, one of the operative node of the EMSO research infrastructure (European Multidisciplinary Seafloor and water column Observatory, http://emso-eu.org). But in the Mediterranean many seismic areas are located a few tens-hundreds of miles from the coast and cabled solutions are not feasible essentially for economic reasons. For this kind of installations EMSO research infrastructure foresees no-cabled solution, that requires a surface buoy deployed in the vicinity seafloor modules.This project plans to develop a surface buoy equipped with autonomous power supply system to power also the seafloor platforms and two-way communication system enabling the data transfer through latest generation of broadband radio communication or satellite link (Fig. 1). All the components of the prototype system are described.

  7. 77 FR 64834 - Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-23

    ... information. ] FOR FURTHER INFORMATION CONTACT: John G. Lamb, Office of Nuclear Reactor Regulation, U.S.... For the Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. BILLING CODE 7590-01-P...

  8. 75 FR 47856 - Nebraska Public Power District: Cooper Nuclear Station; Notice of Availability of the Final...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-09

    ... Reactor Regulation, U.S. Nuclear Regulatory Commission, Mail Stop O-11F1, Washington, DC 20555-0001. Ms.... Imboden, Chief, Environmental Review Branch, Division of License Renewal, Office of Nuclear Reactor... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  9. Proceedings of the nuclear criticality technology safety project

    SciTech Connect

    Sanchez, R.G.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

  10. Imaging nuclear decays with Optical Time Projection Chamber

    NASA Astrophysics Data System (ADS)

    Miernik, K.; Dominik, W.; Janas, Z.; Pfützner, M.; Bingham, C.; Czyrkowski, H.; Ćwiok, M.; Darby, I.; Dȧbrowski, R.; Fomitchev, A.; Gintei, T.; Golovkov, M.; Grzywacz, R.; Karny, M.; Korgul, A.; Kuśmierz, W.; Liddick, S.; Rajabali, M.; Rodin, A.; Rykaczewski, K.; Stepantsov, S.; Slepniev, R.; Stolz, A.; Ter-Akopian, G. M.; Wolski, R.

    2007-11-01

    A novel type of gaseous ionization detector—Optical Time Projection Chamber (OTPC)—developed to study rare nuclear decays is presented. The OTPC records tracks of charged particles ionizing a counting gas by optical imaging of the light generated by electrons multiplied in the amplification structures. By combining an electron drift-time profile measured by a photomultiplier and a CCD camera image we reconstruct three-dimensional trajectories of particles, energies and charges. The capabilities of the OTPC detector to study various decay modes are demonstrated by observation of beta-delayed proton emission from 13O, two-alpha break-up of 8Be, triple-alpha decay of 12C excited states and two-proton radioactivity of 45Fe.

  11. Compiling Utility Requirements For New Nuclear Power Plant Project

    SciTech Connect

    Patrakka, Eero

    2002-07-01

    Teollisuuden Voima Oy (TVO) submitted in November 2000 to the Finnish Government an application for a Decision-in-Principle concerning the construction of a new nuclear power plant in Finland. The actual investment decision can be made first after a positive decision has been made by the Government and the Parliament. Parallel to the licensing process, technical preparedness has been upheld so that the procurement process can be commenced without delay, when needed. This includes the definition of requirements for the plant and preliminary preparation of bid inquiry specifications. The core of the technical requirements corresponds to the specifications presented in the European Utility Requirement (EUR) document, compiled by major European electricity producers. Quite naturally, an amount of modifications to the EUR document are needed that take into account the country- and site-specific conditions as well as the experiences gained in the operation of the existing NPP units. Along with the EUR-related requirements concerning the nuclear island and power generation plant, requirements are specified for scope of supply as well as for a variety of issues related to project implementation. (author)

  12. Thermal hydraulic feasibility assessment for the Spent Nuclear Fuel Project

    SciTech Connect

    Heard, F.J.; Cramer, E.R.; Beaver, T.R.; Thurgood, M.J.

    1996-01-01

    A series of scoping analyses have been completed investigating the thermal-hydraulic performance and feasibility of the Spent Nuclear Fuel Project (SNFP) Integrated Process Strategy (IPS). The SNFP was established to develop engineered solutions for the expedited removal, stabilization, and storage of spent nuclear fuel from the K Basins at the U.S. Department of Energy`s Hanford Site in Richland, Washington. The subject efforts focused on independently investigating, quantifying, and establishing the governing heat production and removal mechanisms for each of the IPS operations and configurations, obtaining preliminary results for comparison with and verification of other analyses, and providing technology-based recommendations for consideration and incorporation into the design bases for the SNFP. The goal was to develop a series fo thermal-hydraulic models that could respond to all process and safety-related issues that may arise pertaining to the SNFP. A series of sensitivity analyses were also performed to help identify those parameters that have the greatest impact on energy transfer and hence, temperature control. It is anticipated that the subject thermal-hydraulic models will form the basis for a series of advanced and more detailed models that will more accurately reflect the thermal performance of the IPS and alleviate the necessity for some of the more conservative assumptions and oversimplifications, as well as form the basis for the final process and safety analyses.

  13. Tracy Power Station -- Unit No. 4, Pinon Pine Power Project Public Design Report

    SciTech Connect

    1994-12-01

    This Public Design Report describes the Pinon Pine Project which will be located at the Sierra Pacific Power Company`s (SPPCO) Tracy Station near Reno, Nevada. The integrated gasification combined-cycle (IGCC) plant is designed to process 880 tones per day (TPD) of bituminous coal producing approximately 107 gross megawatts of electric power (MWe). This project is receiving cost-sharing from the US Department of Energy (DOE) in accordance with DOE Cooperative Agreement DE-FC2192MC29309. The plant incorporates the Kellogg-Rust-Westinghouse (KRW) fluidized bed gasification technology which produces a low-Btu gas which is used as fuel in a combined cycle power plant which has been modified to accommodate the fuel gas produced by an air-blown gasifier. The gasification system also includes hot gas removal of particulates and sulfur compounds from the fuel gas resulting in a plant with exceptionally low atmospheric emissions. Desulfurization is accomplished by a combination of limestone injection into the KRW fluidized bed gasifier and by a transport reactor system. Particulate removal is accomplished by high efficiency cyclones and a barrier filter. The Pinon Pine Project Schedule is divided into three phases. Phase I includes permitting and preliminary design. Phase II, which overlaps Phase I, covers detailed design, procurement, and construction. Phase III will cover the initial operation and demonstration portion of the project.

  14. 78 FR 33121 - Staff Requirements-SECY-12-0168-Calvert Cliffs 3 Nuclear Project, LLC & UniStar Nuclear Operating...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-03

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Staff Requirements--SECY-12-0168--Calvert Cliffs 3 Nuclear Project, LLC & UniStar Nuclear.... On March 11, 2013, in SRM-12-0168, ``Calvert Cliffs 3 Nuclear Project, LLC & UniStar...

  15. Spent nuclear fuel project high-level information management plan

    SciTech Connect

    Main, G.C.

    1996-09-13

    This document presents the results of the Spent Nuclear Fuel Project (SNFP) Information Management Planning Project (IMPP), a short-term project that identified information management (IM) issues and opportunities within the SNFP and outlined a high-level plan to address them. This high-level plan for the SNMFP IM focuses on specific examples from within the SNFP. The plan`s recommendations can be characterized in several ways. Some recommendations address specific challenges that the SNFP faces. Others form the basis for making smooth transitions in several important IM areas. Still others identify areas where further study and planning are indicated. The team`s knowledge of developments in the IM industry and at the Hanford Site were crucial in deciding where to recommend that the SNFP act and where they should wait for Site plans to be made. Because of the fast pace of the SNFP and demands on SNFP staff, input and interaction were primarily between the IMPP team and members of the SNFP Information Management Steering Committee (IMSC). Key input to the IMPP came from a workshop where IMSC members and their delegates developed a set of draft IM principles. These principles, described in Section 2, became the foundation for the recommendations found in the transition plan outlined in Section 5. Availability of SNFP staff was limited, so project documents were used as a basis for much of the work. The team, realizing that the status of the project and the environment are continually changing, tried to keep abreast of major developments since those documents were generated. To the extent possible, the information contained in this document is current as of the end of fiscal year (FY) 1995. Programs and organizations on the Hanford Site as a whole are trying to maximize their return on IM investments. They are coordinating IM activities and trying to leverage existing capabilities. However, the SNFP cannot just rely on Sitewide activities to meet its IM requirements

  16. Water supply for the Nuclear Rocket Development Station at the U.S. Atomic Energy Commission's Nevada Test Site

    USGS Publications Warehouse

    Young, Richard Arden

    1972-01-01

    The Nuclear Rocket Development Station, in Jackass Flats, occupies about 123 square miles in the southwestern part of the U.S. Atomic Energy Commission's Nevada Test Site. Jackass Flats, an intermontane valley bordered by highlands on all sides except for a drainage outlet in the southwestern corner, has an average annual rainfall of 4 inches. Jackass Flats is underlain by alluvium, colluvium, and volcanic rocks of Cenozoic age and, at greater depth, by sedimentary rocks of Paleozoic age. The alluvium and the colluvium lie above the saturated zone throughout nearly all of Jackass Flats. The Paleozoic sedimentary rocks contain limestone and dolomite units that are excellent water producers elsewhere ; however, these units are too deep in Jackass Flats to be economic sources of water. The only important water-producing unit known in the vicinity of the Nuclear Rocket Development Station is a welded-tuff aquifer, the Topopah Spring Member of the Paintbrush Tuff, which receives no significant recharge. This member contains about 500 feet of highly fractured rock underlying an area 11 miles long and 3 miles wide in western Jackass Flats. Permeability of the aquifer is derived mostly from joints and fractures; however, some permeability may be derived from gas bubbles in the upper part of the unit. Transmissivity, obtained from pumping tests, ranges from 68,000 to 488,000 gallons per day per foot. Volume of the saturated part of the aquifer is about 3.5 cubic miles, and the average specific yield probably ranges from 1 to 5 percent. The volume of ground water in storage is probably within the range of 37-187 billion gallons. This large amount of water should be sufficient to supply the needs of the Nuclear Rocket Development Station for many years. Water at the Nuclear Rocket Development Station is used for public supply, construction, test-cell coolant, exhaust cooling, and thermal shielding during nuclear reactor and engine testing, and washdown. Present (1967) average

  17. The Sky Polarization Observatory (SPOrt): a project to measure the diffused sky polarization from the International Space Station Alpha (ISSA)

    NASA Astrophysics Data System (ADS)

    Cortiglioni, S.

    1999-07-01

    The Sky Polarization Observatory (SPOrt), a project to measure the diffused sky polarization in the frequency range of 22-90 GHz from the International Space Station, is described in its current configuration. Some preliminary considerations about the general topic of polarization in radiometric observations are made, in order to introduce the importance of polarimetric measurements in the more general context of Cosmic Microwave Background observations. The International Space Station is also introduced as a quite good opportunity to address such problematics.

  18. Analysis of Digitized Seismograms from Russian Geophysical Survey Stations of Soviet Peaceful Nuclear Explosions

    DTIC Science & Technology

    2009-09-30

    and Chukotka regions. The Magadan region profile indicates velocities slower than those found from Kimberlite -4. the closest of the old PNE profiles...Figure 7) indicates velocities essentially identical to those from the Kimberlite -4 profile in the Siberian Platform, which includes stations Yakutsk...and Khandyga. The Siberian Platform portion of the Magadan profile intersects the Kimberlite -4 profile between the Neva site and station Yakutsk, thus

  19. Formation of a nuclear reactor's molten core bath in a crucible-type corium catcher for a nuclear power station equipped with VVER reactors

    NASA Astrophysics Data System (ADS)

    Beshta, S. V.; Vitol', S. A.; Granovskii, V. S.; Kalyago, E. K.; Kovtunova, S. V.; Krushinov, E. V.; Sulatskaya, M. B.; Sulatskii, A. A.; Khabenskii, V. B.; Al'Myashev, V. I.; Gusarov, V. V.

    2011-05-01

    Results from a calculation study on analyzing the formation of a melt bath in a crucible-type catcher for the conditions of a severe accident at a nuclear power station equipped with VVER-1000 reactors are presented. It is shown that the heat loads exerted on the water-cooled walls of the corium catcher shell are limited to a permissible level at which the necessary margins to nucleate boiling crisis and to destruction are ensured under the conditions of thermal and mechanical loading of the shell. An important role of sacrificial material in the efficient operation of the corium catcher is pointed out.

  20. GULF OF MEXICO SEAFLOOR STABILITY AND GAS HYDRATE MONITORING STATION PROJECT

    SciTech Connect

    J. Robert Woolsey; Thomas M. McGee; Robin C. Buchannon

    2004-11-01

    The gas hydrates research Consortium (HRC), established and administered at the University if Mississippi's Center for Marine Research and Environmental Technology (CMRET) has been active on many fronts in FY 03. Extension of the original contract through March 2004, has allowed completion of many projects that were incomplete at the end of the original project period due, primarily, to severe weather and difficulties in rescheduling test cruises. The primary objective of the Consortium, to design and emplace a remote sea floor station for the monitoring of gas hydrates in the Gulf of Mexico by the year 2005 remains intact. However, the possibility of levering HRC research off of the Joint Industries Program (JIP) became a possibility that has demanded reevaluation of some of the fundamental assumptions of the station format. These provisions are discussed in Appendix A. Landmark achievements of FY03 include: (1) Continuation of Consortium development with new researchers and additional areas of research contribution being incorporated into the project. During this period, NOAA's National Undersea Research Program's (NURP) National Institute for Undersea Science and Technology (NIUST) became a Consortium funding partner, joining DOE and Minerals Management Service (MMS); (2) Very successful annual and semiannual meetings in Oxford Mississippi in February and September, 2003; (3) Collection of piston cores from MC798 in support of the effort to evaluate the site for possible monitoring station installation; (4) Completion of the site evaluation effort including reports of all localities in the northern Gulf of Mexico where hydrates have been documented or are strongly suspected to exist on the sea floor or in the shallow subsurface; (5) Collection and preliminary evaluation of vent gases and core samples of hydrate from sites in Green Canyon and Mississippi Canyon, northern Gulf of Mexico; (6) Monitoring of gas activity on the sea floor, acoustically and thermally

  1. Projective virtual reality in space applications: a telerobotic ground station for a space mission

    NASA Astrophysics Data System (ADS)

    Freund, Eckhard; Rossmann, Juergen; Schluse, Michael

    2000-10-01

    Commanding complex robotic systems over long distances in an intuitive manner requires new techniques of man-machine- interaction. A first disadvantage of conventional approaches is that the user has to be a robotic expert because he directly has to command the robots. He often is part of the real-time control loop while moving the robot and thus has to cope with long delays. Experience with space robot missions showed that it is very difficult to control a robot just by camera images. At the IRF, a new approach to overcome such problems was developed. By means of Projective Virtual Reality, we introduce a new, intuitive way of man-machine communication based on a combination of action planning and Virtual Reality methods. Using data-helmet and data-glove the user can immerse into the virtual world and interact with the virtual objects as he would do in reality. The Virtual Reality System derives the user's intention from his actions and then projects the tasks in to the physical world by means of robots. The robots carry out the action physically that is equivalent to the user's action in the virtual world. The developed Projective Virtual Reality System is of especially great use for space applications. During the joint project GETEX (German ETS-VII Experiment), the IRF realized the telerobotic ground station for the free flying robot ERA on board the Japanese satellite ETS-VII. During the mission in April 1999 the Virtual Reality based command interface turned out to be an ideally suited platform for the intuitive commanding and supervision of the robot in space. During the mission, it first had to be verified that the system is fully operational, but then out Japanese colleagues allowed to take the full control over the real robot by the Projective Virtual Reality System. The final paper will describe key issues of this approach and the results and experiences gained during the GETEX mission.

  2. Constellation nuclear instrument analysis required in support of the Extended Power Up-rate for Ginna Station

    SciTech Connect

    Guider, J.; Quinn, E. L.

    2006-07-01

    The purpose of this paper is to provide an overview of the Instrumentation and Control design changes required for the Extended Power Up-rate (EPU) at the R.E. Ginna Nuclear Station in Ontario, N.Y. Ginna is a pressurized-water reactor (PWR) plant of the Westinghouse 2-loop design. The request for the EPU was filed on July 7, 2005 and approved by NRC on July 11, 2006 and included an increase in the maximum steady-state reactor core power level from 1520 megawatts thermal to 1775 MWt, which is an increase of approximately 17%. (authors)

  3. Simulator verification effort at the South Texas project electric generating station

    SciTech Connect

    Bellmore, P.E.; Albury, C.R.

    1987-01-01

    This paper presents the work being done at Houston Lighting and Power Company to verify the South Texas Project Electric Generating Station (STPEGS) simulator. The purpose of that work is to assure that the STPEGS simulator adequately reflects plant response during normal and abnormal transients. An enhanced understanding of the engineering and organizational needs of a simulator verification program is significant. This paper presents the techniques used to develop a best-estimate model. The best-estimate model generates plant response data for comparison with the STPEGS simulator. A typical licensing model is inadequate for this work because of the conservative assumptions in the model. The authors examine, in this paper, the interaction between the various groups responsible for simulator verification.

  4. Nuclear Power 2010 Program Dominion Virginia Power Cooperative Project U.S. Department of Energy Cooperative Agreement DE-FC07-05ID14635 Construction and Operating License Demonstration Project Final Report

    SciTech Connect

    Eugene S. Grecheck David P. Batalo

    2010-11-30

    This report serves to summarize the major activities completed as part of Virginia Electric and Power Company's North Anna construction and operating license demonstration project with DOE. Project successes, lessons learned, and suggestions for improvement are discussed. Objectives of the North Anna COL project included preparation and submittal of a COLA to the USNRC incorporating ESBWR technology for a third unit a the North Anna Power Station site, support for the NRC review process and mandatory hearing, obtaining NRC approval of the COLA and issuance of a COL, and development of a business case necessary to support a decision on building a new nuclear power plant at the North Anna site.

  5. RADIOLOGICAL SURVEY STATION DEVELOPMENT FOR THE PIT DISASSEMBLY AND CONVERSION PROJECT

    SciTech Connect

    Dalmaso, M.; Gibbs, K.; Gregory, D.

    2011-05-22

    The Savannah River National Laboratory (SRNL) has developed prototype equipment to demonstrate remote surveying of Inner and Outer DOE Standard 3013 containers for fixed and transferable contamination in accordance with DOE Standard 3013 and 10 CFR 835 Appendix B. When fully developed the equipment will be part of a larger suite of equipment used to package material in accordance with DOE Standard 3013 at the Pit Disassembly and Conversion Project slated for installation at the Savannah River Site. The prototype system consists of a small six-axis industrial robot with an end effector consisting of a force sensor, vacuum gripper and a three fingered pneumatic gripper. The work cell also contains two alpha survey instruments, swipes, swipe dispenser, and other ancillary equipment. An external controller interfaces with the robot controller, survey instruments and other ancillary equipment to control the overall process. SRNL is developing automated equipment for the Pit Disassembly and Conversion (PDC) Project that is slated for the Savannah River Site (SRS). The equipment being developed is automated packaging equipment for packaging plutonium bearing materials in accordance with DOE-STD-3013-2004. The subject of this paper is the development of a prototype Radiological Survey Station (RSS). Other automated equipment being developed for the PDC includes the Bagless transfer System, Outer Can Welder, Gantry Robot System (GRS) and Leak Test Station. The purpose of the RSS is to perform a frisk and swipe of the DOE Standard 3013 Container (either inner can or outer can) to check for fixed and transferable contamination. This is required to verify that the contamination levels are within the limits specified in DOE-STD-3013-2004 and 10 CFR 835, Appendix D. The surface contamination limit for the 3013 Outer Can (OC) is 500 dpm/100 cm2 (total) and 20 dpm/100 cm2 (transferable). This paper will concentrate on the RSS developments for the 3013 OC but the system for the

  6. A pilot application of risk-based methods to establish in-service inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station

    SciTech Connect

    Vo, T.; Gore, B.; Simonen, F.; Doctor, S.

    1994-08-01

    As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory Commission, the Pacific Northwest Laboratory is developing a method that uses risk-based approaches to establish in-service inspection plans for nuclear power plant components. This method uses probabilistic risk assessment (PRA) results and Failure Modes and Effects Analysis (FEMA) techniques to identify and prioritize the most risk-important systems and components for inspection. The Surry Nuclear Power Station Unit 1 was selected for pilot applications of this method. The specific systems addressed in this report are the reactor pressure vessel, the reactor coolant, the low-pressure injection, and the auxiliary feedwater. The results provide a risk-based ranking of components within these systems and relate the target risk to target failure probability values for individual components. These results will be used to guide the development of improved inspection plans for nuclear power plants. To develop inspection plans, the acceptable level of risk from structural failure for important systems and components will be apportioned as a small fraction (i.e., 5%) of the total PRA-estimated risk for core damage. This process will determine target (acceptable) risk and target failure probability values for individual components. Inspection requirements will be set at levels to assure that acceptable failure probabilistics are maintained.

  7. A feasibility assessment of installation, operation and disposal options for nuclear reactor power system concepts for a NASA growth space station

    NASA Technical Reports Server (NTRS)

    Bloomfield, Harvey S.; Heller, Jack A.

    1987-01-01

    A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth space station architecture was conducted to address a variety of installation, operational disposition, and safety issues. A previous NASA sponsored study, which showed the advantages of space station - attached concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide the feasibility of each combination.

  8. Evaluation of nuclear facility decommissioning projects. Project summary report, Elk River Reactor

    SciTech Connect

    Miller, R.L.; Adams, J.A.

    1982-12-01

    This report summarizes information concerning the decommissioning of the Elk River Reactor. Decommissioning data from available documents were input into a computerized data-handling system in a manner that permits specific information to be readily retrieved. The information is in a form that assists the Nuclear Regulatory Commission in its assessment of decommissioning alternatives and ALARA methods for future decommissionings projects. Samples of computer reports are included in the report. Decommissioning of other reactors, including NRC reference decommissioning studies, will be described in similar reports.

  9. Biodosimetry of restoration workers for the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi nuclear power station accident.

    PubMed

    Suto, Yumiko; Hirai, Momoki; Akiyama, Miho; Kobashi, Gen; Itokawa, Masanari; Akashi, Makoto; Sugiura, Nobuyuki

    2013-10-01

    The biological dose of nuclear workers engaged in emergency response tasks at Tokyo Electric Power Company (TEPCO) Fukushima Daiichi Nuclear Power Station was estimated in the present study. As the national core center for radiation emergency medical preparedness in Japan, the National Institute of Radiological Sciences (NIRS) received all individuals who were suspected of being overexposed to acute radiation. In the course of health examinations at NIRS, biological dosimetry was performed by the dicentric chromosome assay (DCA). Twelve individuals were examined from 21 March-1 July 2011. The results indicated that the estimated exposure doses for all individuals were lower than 30 mGy, with the mean value of about 101 mGy. These results by DCA were in accordance with those obtained by physical dosimetry based on personal dosimeter recording assessment. The results corroborate the fact that no acute radiation syndrome was observed among the workers examined.

  10. How Space Radiation Risk from Galactic Cosmic Rays at the International Space Station Relates to Nuclear Cross Sections

    NASA Technical Reports Server (NTRS)

    Lin, Zi-Wei; Adams, J. H., Jr.

    2005-01-01

    Space radiation risk to astronauts is a major obstacle for long term human space explorations. Space radiation transport codes have thus been developed to evaluate radiation effects at the International Space Station (ISS) and in missions to the Moon or Mars. We study how nuclear fragmentation processes in such radiation transport affect predictions on the radiation risk from galactic cosmic rays. Taking into account effects of the geomagnetic field on the cosmic ray spectra, we investigate the effects of fragmentation cross sections at different energies on the radiation risk (represented by dose-equivalent) from galactic cosmic rays behind typical spacecraft materials. These results tell us how the radiation risk at the ISS is related to nuclear cross sections at different energies, and consequently how to most efficiently reduce the physical uncertainty in our predictions on the radiation risk at the ISS.

  11. XOQDOQ: computer program for the meteorological evaluation of routine effluent releases at nuclear power stations. Final report

    SciTech Connect

    Sagendorf, J.F.; Goll, J.T.; Sandusky, W.F.

    1982-09-01

    Provided is a user's guide for the US Nuclear Regulatory Commission's (NRC) computer program X0QDOQ which implements Regulatory Guide 1.111. This NUREG supercedes NUREG-0324 which was published as a draft in September 1977. This program is used by the NRC meteorology staff in their independent meteorological evaluation of routine or anticipated intermittent releases at nuclear power stations. It operates in a batch input mode and has various options a user may select. Relative atmospheric dispersion and deposition factors are computed for 22 specific distances out to 50 miles from the site for each directional sector. From these results, values for 10 distance segments are computed. The user may also select other locations for which atmospheric dispersion deposition factors are computed. Program features, including required input data and output results, are described. A program listing and test case data input and resulting output are provided.

  12. Resource Letter MP-2: The Manhattan project and related nuclear research

    NASA Astrophysics Data System (ADS)

    Reed, B. Cameron

    2011-02-01

    This Resource Letter is a supplement to my earlier Resource Letter MP-1 and provides further sources on the Manhattan Project and related nuclear research. Books and journal articles are cited for the following topics: General works, technical works, biographical and autobiographical works, foreign wartime programs and allied intelligence, technical papers of historical interest, and postwar policy and technical developments. I also give a list of videos and websites dealing with the Manhattan Project, nuclear weapons, and nuclear issues.

  13. Nuclear Science and Physics Data from the Isotopes Project, Lawrence Berkeley National Laboratory (LBNL)

    DOE Data Explorer

    The Isotopes Project pages at Lawrence Berkeley National Laboratory have been a source of nuclear data and reference information since the mid-nineties. Almost all of the data, the results of analyses, the specialized charts and interfaces, and the extensive bibiographic references are fed to the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory and maintained there. The Isotope Project pages at LBNL provide a glimpse of early versions for many of the nuclear data resources.

  14. National Center for Nuclear Security: The Nuclear Forensics Project (F2012)

    SciTech Connect

    Klingensmith, A. L.

    2012-03-21

    These presentation visuals introduce the National Center for Nuclear Security. Its chartered mission is to enhance the Nation’s verification and detection capabilities in support of nuclear arms control and nonproliferation through R&D activities at the NNSS. It has three focus areas: Treaty Verification Technologies, Nonproliferation Technologies, and Technical Nuclear Forensics. The objectives of nuclear forensics are to reduce uncertainty in the nuclear forensics process & improve the scientific defensibility of nuclear forensics conclusions when applied to nearsurface nuclear detonations. Research is in four key areas: Nuclear Physics, Debris collection and analysis, Prompt diagnostics, and Radiochemistry.

  15. Analysis of data from sensitive U.S. monitoring stations for the Fukushima Dai-ichi nuclear reactor accident.

    PubMed

    Biegalski, S R; Bowyer, T W; Eslinger, P W; Friese, J A; Greenwood, L R; Haas, D A; Hayes, J C; Hoffman, I; Keillor, M; Miley, H S; Moring, M

    2012-12-01

    The March 11, 2011 9.0 magnitude undersea megathrust earthquake off the coast of Japan and subsequent tsunami waves triggered a major nuclear event at the Fukushima Dai-ichi nuclear power station. At the time of the event, units 1, 2, and 3 were operating and units 4, 5, and 6 were in a shutdown condition for maintenance. Loss of cooling capacity to the plants along with structural damage caused by the earthquake and tsunami resulted in a breach of the nuclear fuel integrity and release of radioactive fission products to the environment. Fission products started to arrive in the United States via atmospheric transport on March 15, 2011 and peaked by March 23, 2011. Atmospheric activity concentrations of (131)I reached levels of 3.0×10(-2) Bqm(-3) in Melbourne, FL. The noble gas (133)Xe reached atmospheric activity concentrations in Ashland, KS of 17 Bqm(-3). While these levels are not health concerns, they were well above the detection capability of the radionuclide monitoring systems within the International Monitoring System of the Comprehensive Nuclear-Test-Ban Treaty.

  16. Analysis of data from sensitive U.S. monitoring stations for the Fukushima Dai-ichi nuclear reactor accident

    SciTech Connect

    Biegalski, Steven R.; Bowyer, Ted W.; Eslinger, Paul W.; Friese, Judah I.; Greenwood, Lawrence R.; Haas, Derek A.; Hayes, James C.; Hoffman, Ian; Keillor, Martin E.; Miley, Harry S.; Morin, Marc P.

    2012-12-01

    The March 11, 2011 9.0 magnitude undersea megathrust earthquake off the coast of Japan and subsequent tsunami waves triggered a major nuclear event at the Fukushima Dai-ichi nuclear power station. At the time of the event, units 1, 2, and 3 were operating and units 4, 5, and 6 were in a shutdown condition for maintenance. Loss of cooling capacity to the plants along with structural damage caused by the earthquake and tsunami resulted in a breach of the nuclear fuel integrity and release of radioactive fission products to the environment. Fission products started to arrive in the United States via atmospheric transport on March 15, 2011 and peaked by March 23, 2011. Atmospheric activity concentrations of 131I reached levels of 3.0 * 10*2 Bqm*3 in Melbourne, FL. The noble gas 133Xe reached atmospheric activity concentrations in Ashland, KS of 17 Bqm*3. While these levels are not health concerns, they were well above the detection capability of the radionuclide monitoring systems within the International Monitoring System of the Comprehensive Nuclear-Test-Ban Treaty.

  17. Nuclear criticality safety program for environmental restoration projects

    SciTech Connect

    Marble, R.C.; Brown, T.D.

    1994-05-01

    The Fernald Environmental Management Project (FEMP), formerly known as the Feed Materials Production Center (FMPC), is located on a 1050 acre site approximately twenty miles northwest of Cincinnati, Ohio. The production area of the site covers approximately 136 acres in the central portion of the site. Surrounding the core production area is a buffer consisting of leased grazing land, reforested land, and unused areas. The uranium processing facility was designed and constructed in the early 1950s. During the period from 1952 to 1989 the site produced uranium feed material and uranium products used in the United States weapons complex. Production at the site ended in 1989, when the site was shut down for what was expected to be a short period of time. However, the FUTC was permanently shut down in 1991, and the site`s mission was changed from production to environmental restoration. The objective of this paper is to give an update on activities at the Fernald Site and to describe the Nuclear Criticality Safety issues that are currently being addressed.

  18. Meet the Maximally Exposed Member of the Public: The Service Station Attendant for Spent Nuclear Fuel Going to Yucca Mountain

    SciTech Connect

    Collins, H. E.; Gathers, R.; Halstead, R. J.

    2002-02-28

    According to the 1999 Draft Environmental Impact Statement (DEIS) for the proposed Yucca Mountain repository site, members of the public along transportation routes by which spent nuclear fuel (SNF) and high-level radioactive waste (HLW) is shipped will receive annual radiation doses less than 100 mrem/yr, the international (ICRP) and national (Department of Energy, Nuclear Regulatory Commission) radiation limit for members of the public. For the ''Mostly Truck'' national transportation scenario, the DEIS specifically concludes that the maximally exposed member of the public, a service station attendant along the primary shipping route will receive no more than 100 mrem/yr, or 2.4 rem over 24 years. Based on the assumptions in the DEIS scenarios, however, it is highly likely that service station attendants along shipping routes will be called upon to fuel and service the rigs carrying SNF and HLW to Yucca Mountain. After reevaluating the DEIS, and making realistic alternative assumptions where necessary, the authors conclude that these attendants are likely to receive substantially more than 100 mrem/yr external dose, and perhaps several times that dose (up to 500 mrem/yr), unless mitigating measures are adopted. This is particularly true in Western states where refueling opportunities are limited, and the distances between fuel sources in rural areas may be up to 100 miles.

  19. A collaborative network middleware project by Lambda Station, TeraPaths, and Phoebus

    SciTech Connect

    Bobyshev, A.; Bradley, S.; Crawford, M.; DeMar, P.; Katramatos, D.; Shroff, K.; Swany, M.; Yu, D.; /Brookhaven

    2010-01-01

    The TeraPaths, Lambda Station, and Phoebus projects, funded by the US Department of Energy, have successfully developed network middleware services that establish on-demand and manage true end-to-end, Quality-of-Service (QoS) aware, virtual network paths across multiple administrative network domains, select network paths and gracefully reroute traffic over these dynamic paths, and streamline traffic between packet and circuit networks using transparent gateways. These services improve network QoS and performance for applications, playing a critical role in the effective use of emerging dynamic circuit network services. They provide interfaces to applications, such as dCache SRM, translate network service requests into network device configurations, and coordinate with each other to setup up end-to-end network paths. The End Site Control Plane Subsystem (ESCPS) builds upon the success of the three projects by combining their individual capabilities into the next generation of network middleware. ESCPS addresses challenges such as cross-domain control plane signalling and interoperability, authentication and authorization in a Grid environment, topology discovery, and dynamic status tracking. The new network middleware will take full advantage of the perfSONAR monitoring infrastructure and the Inter-Domain Control plane efforts and will be deployed and fully vetted in the Large Hadron Collider data movement environment.

  20. The NASA/DOE/DOD nuclear rocket propulsion project - FY 1991 status

    NASA Technical Reports Server (NTRS)

    Clark, John S.; Miller, Thomas J.

    1991-01-01

    NASA has initiated planning and critical technology development for nuclear rocket propulsion systems for Space Exploration Initiative missions to the moon and to Mars. Interagency agreements are being negotiated between NASA, the Department of Energy, and the Department of Defense for joint technology development activities. This paper summarizes the activities of the NASA project planning team in FY 1990 that led to the draft Nuclear Propulsion Project Plan, outlines the FY 1991 Interagency activities, and describes the current status of the project plan.

  1. Removal of the steam generators and pressurizer at the Yankee Nuclear Power Station

    SciTech Connect

    Holmgren, B.W.; Parker, J.E.

    1995-10-01

    Nuclear Steam Supply System (NSSS) components can be safely and economically removed from shutdown nuclear facilities. In many cases, intact removal of contaminated components is less costly and results in less radiation exposure to personnel than segmented removal. Component removal activities can be conducted prior to Decommissioning Plan approval, provided that the activities are within the bounds of the 10CFR50 operating license and 10CFR50.59, the removal work does not increase the total cost of decommissioning, and does not foreclose the release of the site for unrestricted use. The average citizen appears to be comfortable with the decommissioning process for nuclear power plants, provided the facts are made known. Many anti-nuclear activists, however, do not want nuclear plants to be dismantled right away. Their preference is to place these plants in a SAFSTOR mode for 50 years or more to lower exposure risks to workers and the public. In the case of Yankee Rowe, SAFSTOR will do little to reduce worker and public risk. It could, however, dramatically drive up the cost of decommissioning -- costs which the public pays. The commercial nuclear industry must continue to address the public`s legitimate concerns and respond to misleading antinuclear attacks with facts and information. State and local governments are becoming more interested in nuclear plant decommissioning planning. This trend is likely to continue as more nuclear plants face the end of operation. As several states move toward construction of low-level waste disposal facilities, this may have a positive effect on that process. The need exists for consensus on these facilities which must include provisions for large waste forms such as NSSS components.

  2. Evaluation of the prompt alerting systems at four nuclear power stations

    SciTech Connect

    Towers, D.A.; Anderson, G.S.; Keast, D.N.; Kenoyer, J.L.; Desrosiers, A.E.

    1982-09-01

    This report presents evaluations of the prompt notification siren systems at the following four US nuclear power facilities: Trojan, Three Mile Island, Indian Point, and Zion. The objective of these evaluations was to provide examples of an analytical procedure for predicting siren-system effectiveness under specific conditions in the 10-mile emergency planning zone (EPZ) surrounding nuclear power plants. This analytical procedure is discussed in report No. PNL-4227.

  3. Overview of Nuclear Energy: Present and Projected Use

    SciTech Connect

    Alexander Stanculescu

    2011-09-01

    Several factors will influence the contribution of nuclear energy to the future energy mix. Among them, the most important are the degree of global commitment to greenhouse gas reduction, continued vigilance in safety and safeguards, technological advances, economic competitiveness and innovative financing arrangements for new nuclear power plant constructions, the implementation of nuclear waste disposal, and, last but not least, public perception, information and education. The paper presents an overview of the current nuclear energy situation, possible development scenarios, of reactor technology, and of non-electric applications of nuclear energy.

  4. Overview of nuclear energy: Present and projected use

    NASA Astrophysics Data System (ADS)

    Stanculescu, Alexander

    2012-06-01

    Several factors will influence the contribution of nuclear energy to the future energy mix. Among them, the most important are the degree of global commitment to greenhouse gas reduction, continued vigilance in safety and safeguards, technological advances, economic competitiveness and innovative financing arrangements for new nuclear power plant constructions, the implementation of nuclear waste disposal, and, last but not least, public perception, information and education. The paper presents an overview of the current nuclear energy situation, possible development scenarios, of reactor technology, and of non-electric applications of nuclear energy.

  5. An underground nuclear power station using self-regulating heat-pipe controlled reactors

    DOEpatents

    Hampel, V.E.

    1988-05-17

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working fluid in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast- acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor. 5 figs.

  6. Underground nuclear power station using self-regulating heat-pipe controlled reactors

    DOEpatents

    Hampel, Viktor E.

    1989-01-01

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

  7. Project Dawdler: a Proposal in Response to a Low Reynolds Number Station Keeping Mission

    NASA Technical Reports Server (NTRS)

    Bartilotti, Rich; Coakley, Jill; Golla, Warren; Scamman, Glenn; Tran, Hoa T.; Trippel, Chris

    1990-01-01

    In direct response to Request for Proposals: Flight at very low Reynolds numbers - a station keeping mission, the members of Design Squad E present Project Dawdler: a remotely-piloted airplane supported by an independently controlled take-off cart. A brief introduction to Project Dawdler's overall mission and design, is given. The Dawdler is a remotely-piloted airplane designed to fly in an environmentally-controlled closed course at a Reynolds number of 10(exp 5) and at a cruise velocity of 25 ft/s. The two primary goals were to minimize the flight Reynolds number and to maximize the loiter time. With this in mind, the general design of the airplane was guided by the belief that a relatively light aircraft producing a fairly large amount of lift would be the best approach. For this reason the Dawdler utilizes a canard rather than a conventional tail for longitudinal control, primarily because the canard contributes a positive lift component. The Dawdler also has a single vertical tail mounted behind the wing for lateral stability, half of which is used as a rudder for yaw control. Due to the fact that the power required to take-off and climb to altitude is much greater than that required for cruise flight and simple turning maneuvers, it was decided that a take-off cart be used. Based on the current design, there are two unknowns which could possibly threaten the success of Project Dawdler. First, the effect of the fully-movable canard with its large appropriation of total lift on the performance of the plane, and secondly, the ability of the take-off procedure to go as planned are examined. These are questions which can only be answered by a prototype.

  8. Project Title: Nuclear Astrophysics Data from Radioactive Beam Facilities

    SciTech Connect

    Alan A. Chen

    2008-03-27

    The scientific aims of this project have been the evaluation and dissemination of key nuclear reactions in nuclear astrophysics, with a focus on ones to be studied at new radioactive beam facilities worldwide. These aims were maintained during the entire funding period from 2003 - 2006. In the following, a summary of the reactions evaluated during this period is provided. Year 1 (2003-04): {sup 21}Na(p,{gamma}){sup 22}Mg and {sup 18}Ne({alpha},p){sup 21}Na - The importance of the {sup 21}Na(p,{gamma}){sup 22}Mg and the {sup 18}Ne({alpha},p){sup 21}Na reactions in models of exploding stars has been well documented: the first is connected to the production of the radioisotope {sup 22}Na in nova nucleosynthesis, while the second is a key bridge between the Hot-CNO cycles and the rp-process in X-ray bursts. By the end of Summer 2004, our group had updated these reaction rates to include all published data up to September 2004, and cast the reaction rates into standard analytical and tabular formats with the assistance of Oak Ridge National Laboratory's computational infrastructure for reaction rates. Since September 2004, ongoing experiments on these two reactions have been completed, with our group's participation in both: {sup 21}Na(p,{gamma}){sup 22}Mg at the TRIUMF-ISAC laboratory (DRAGON collaboration), and 18Ne({alpha},p){sup 21}Na at Argonne National Laboratory (collaboration with Ernst Rehm, Argonne). The data from the former was subsequently published and included in our evaluation. Publication from the latter still awaits independent confirmation of the experimental results. Year 2 (2004-05): The 25Al(p,{gamma}){sup 26}Si and {sup 13}N(p,{gamma})14O reactions - For Year 2, we worked on evaluations of the {sup 25}Al(p,{gamma}){sup 26}Si and {sup 13}N(p,{gamma}){sup 14}O reactions, in accordance with our proposed deliverables and following similar standard procedures to those used in Year 1. The {sup 25}Al(p,{gamma}){sup 26}Si reaction is a key uncertainty in

  9. Nuclear economics 2000: Deterministic and probabilistic projections of nuclear and coal electric power generation costs for the year 2000

    SciTech Connect

    Williams, K.A.; Delene, J.G.; Fuller, L.C.; Bowers, H.I.

    1987-06-01

    The total busbar electric generating costs were estimated for locations in ten regions of the United States for base-load nuclear and coal-fired power plants with a startup date of January 2000. For the Midwest region a complete data set that specifies each parameter used to obtain the comparative results is supplied. When based on the reference set of input variables, the comparison of power generation costs is found to favor nuclear in most regions of the country. Nuclear power is most favored in the northeast and western regions where coal must be transported over long distances; however, coal-fired generation is most competitive in the north central region where large reserves of cheaply mineable coal exist. In several regions small changes in the reference variables could cause either option to be preferred. The reference data set reflects the better of recent electric utility construction cost experience (BE) for nuclear plants. This study assumes as its reference case a stable regulatory environment and improved planning and construction practices, resulting in nuclear plants typically built at the present BE costs. Today's BE nuclear-plant capital investment cost model is then being used as a surrogate for projected costs for the next generation of light-water reactor plants. An alternative analysis based on today's median experience (ME) nuclear-plant construction cost experience is also included. In this case, coal is favored in all ten regions, implying that typical nuclear capital investment costs must improve for nuclear to be competitive.

  10. Nuclear and in-source laser spectroscopy with the ISAC yield station

    SciTech Connect

    Kunz, Peter Bricault, Pierre; Dombsky, Marik; Lassen, Jens; Teigelhöfer, Andrea; Heggen, Henning; Andreoiu, Corina; Wong, Fiona

    2014-05-15

    A new decay station has been built for the ISAC facility at TRIUMF for the rapid and reliable characterization of radioactive ion beam (RIB) compositions and intensities with the capability of simultaneously collecting α, β, and γ decay data from RIB with intensities between a few and ≈10{sup 11} ions per second. It features user-friendly control, data acquisition, and analysis software. The analysis of individual decay time structures allows the unambiguous assignment of α and γ lines even with substantial isobaric contamination present. The capability for accurate half-life measurements is demonstrated with the example of {sup 46}K. The coupling of the yield station to the laser ion source, TRILIS, allows the correlation of radiometric data with automated laser frequency scans. First results of in-source laser spectroscopy measurements on astatine are discussed.

  11. Nuclear and in-source laser spectroscopy with the ISAC yield station

    NASA Astrophysics Data System (ADS)

    Kunz, Peter; Andreoiu, Corina; Bricault, Pierre; Dombsky, Marik; Lassen, Jens; Teigelhöfer, Andrea; Heggen, Henning; Wong, Fiona

    2014-05-01

    A new decay station has been built for the ISAC facility at TRIUMF for the rapid and reliable characterization of radioactive ion beam (RIB) compositions and intensities with the capability of simultaneously collecting α, β, and γ decay data from RIB with intensities between a few and ≈1011 ions per second. It features user-friendly control, data acquisition, and analysis software. The analysis of individual decay time structures allows the unambiguous assignment of α and γ lines even with substantial isobaric contamination present. The capability for accurate half-life measurements is demonstrated with the example of 46K. The coupling of the yield station to the laser ion source, TRILIS, allows the correlation of radiometric data with automated laser frequency scans. First results of in-source laser spectroscopy measurements on astatine are discussed.

  12. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study

    SciTech Connect

    Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F.

    1987-08-01

    Pacific Northwest Laboratory evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume I, reviews diesel-generator experience to identify the systems and components most subject to aging degradation and isolates the major causes of failure that may affect future operational readiness. Evaluations show that as plants age, the percent of aging-related failures increases and failure modes change. A compilation is presented of recommended corrective actions for the failures identified. This study also includes a review of current, relevant industry programs, research, and standards. Volume II reports the results of an industry-wide workshop held on May 28 and 29, 1986 to discuss the technical issues associated with aging of nuclear service emergency diesel generators.

  13. Hanford K Basins spent nuclear fuels project update

    SciTech Connect

    Hudson, F.G.

    1997-10-17

    Twenty one hundred metric tons of spent nuclear fuel are stored in two concrete pools on the Hanford Site, known as the K Basins, near the Columbia River. The deteriorating conditions of the fuel and the basins provide engineering and management challenges to assure safe current and future storage. DE and S Hanford, Inc., part of the Fluor Daniel Hanford, Inc. lead team on the Project Hanford Management Contract, is constructing facilities and systems to move the fuel from current wet pool storage to a dry interim storage facility away from the Columbia River, and to treat and dispose of K Basins sludge, debris and water. The process starts in the K Basins where fuel elements will be removed from existing canisters, washed, and separated from sludge and scrap fuel pieces. Fuel elements will be placed in baskets and loaded into Multi-Canister Overpacks (MCOs) and into transportation casks. The MCO and cask will be transported into the Cold Vacuum Drying Facility, where free water within the MCO will be removed under vacuum at slightly elevated temperatures. The MCOs will be sealed and transported via the transport cask to the Canister Storage Building (CSB) in the 200 Area for staging prior to hot conditioning. The conditioning step to remove chemically bound water is performed by holding the MCO at 300 C under vacuum. This step is necessary to prevent excessive pressure buildup during interim storage that could be caused by corrosion. After conditioning, MCOs will remain in the CSB for interim storage until a national repository is completed.

  14. [Transport processes of low-level radioactive liquid effluent of nuclear power station in closed water body].

    PubMed

    Wu, Guo-Zheng; Xu, Zong-Xue

    2012-07-01

    The transport processes of low-level radioactive liquid effluent of Xianning nuclear power station in the closed water body Fushui Reservoir are simulated using the EFDC model. Six nuclides concentration distribution with different half-lives in the reservoir are analyzed under the condition of 97% guarantee rate incoming water and four-running nuclear power units. The results show that the nuclides concentration distribution is mainly affected by the flow field of the reservoir and the concentration is decided by the half-lives of nuclide and the volume of incoming water. In addition, the influence region is enlarged as increasing of half-life and tends to be stable when the half-life is longer than 5 years. Moreover, the waste water discharged from the outlet of the nuclear power plant has no effect on the water-intake for the outlet located at the upstream of the water-intake and the flow field flows to the dam of the reservoir.

  15. The radioisotope complex project "RIC-80" at the Petersburg Nuclear Physics Institute.

    PubMed

    Panteleev, V N; Barzakh, A E; Batist, L Kh; Fedorov, D V; Ivanov, V S; Moroz, F V; Molkanov, P L; Orlov, S Yu; Volkov, Yu M

    2015-12-01

    The high current cyclotron C-80 capable of producing 40-80 MeV proton beams with a current of up to 200 μA has been constructed at Petersburg Nuclear Physics Institute. One of the main goals of the C-80 is the production of a wide spectrum of medical radionuclides for diagnostics and therapy. The project development of the radioisotope complex RIC-80 (radioisotopes at the cyclotron C-80) at the beam of C-80 has been completed. The RIC-80 complex is briefly discussed in this paper. The combination of the mass-separator with the target-ion source device, available at one of the new target stations for on-line or semi on-line production of a high purity separated radioisotopes, is explored in greater detail. The results of target and ion source tests for a mass-separator method for the production of high purity radioisotopes (82)Sr and (223,224)Ra are also presented.

  16. The radioisotope complex project “RIC-80” at the Petersburg Nuclear Physics Institute

    SciTech Connect

    Panteleev, V. N. Barzakh, A. E.; Batist, L. Kh.; Fedorov, D. V.; Ivanov, V. S.; Moroz, F. V.; Molkanov, P. L.; Orlov, S. Yu.; Volkov, Yu. M.

    2015-12-15

    The high current cyclotron C-80 capable of producing 40-80 MeV proton beams with a current of up to 200 μA has been constructed at Petersburg Nuclear Physics Institute. One of the main goals of the C-80 is the production of a wide spectrum of medical radionuclides for diagnostics and therapy. The project development of the radioisotope complex RIC-80 (radioisotopes at the cyclotron C-80) at the beam of C-80 has been completed. The RIC-80 complex is briefly discussed in this paper. The combination of the mass-separator with the target-ion source device, available at one of the new target stations for on-line or semi on-line production of a high purity separated radioisotopes, is explored in greater detail. The results of target and ion source tests for a mass-separator method for the production of high purity radioisotopes {sup 82}Sr and {sup 223,224}Ra are also presented.

  17. Summary of ground motion prediction results for Nevada Test Site underground nuclear explosions related to the Yucca Mountain project

    SciTech Connect

    Walck, M.C.

    1996-10-01

    This report summarizes available data on ground motions from underground nuclear explosions recorded on and near the Nevada Test Site, with emphasis on the ground motions recorded at stations on Yucca Mountain, the site of a potential high-level radioactive waste repository. Sandia National Laboratories, through the Weapons Test Seismic Investigations project, collected and analyzed ground motion data from NTS explosions over a 14-year period, from 1977 through 1990. By combining these data with available data from earlier, larger explosions, prediction equations for several ground motion parameters have been developed for the Test Site area for underground nuclear explosion sources. Also presented are available analyses of the relationship between surface and downhole motions and spectra and relevant crustal velocity structure information for Yucca Mountain derived from the explosion data. The data and associated analyses demonstrate that ground motions at Yucca Mountain from nuclear tests have been at levels lower than would be expected from moderate to large earthquakes in the region; thus nuclear explosions, while located relatively close, would not control seismic design criteria for the potential repository.

  18. Steam Pressure-Reducing Station Safety and Energy Efficiency Improvement Project

    SciTech Connect

    Lower, Mark D; Christopher, Timothy W; Oland, C Barry

    2011-06-01

    The Facilities and Operations (F&O) Directorate is sponsoring a continuous process improvement (CPI) program. Its purpose is to stimulate, promote, and sustain a culture of improvement throughout all levels of the organization. The CPI program ensures that a scientific and repeatable process exists for improving the delivery of F&O products and services in support of Oak Ridge National Laboratory (ORNL) Management Systems. Strategic objectives of the CPI program include achieving excellence in laboratory operations in the areas of safety, health, and the environment. Identifying and promoting opportunities for achieving the following critical outcomes are important business goals of the CPI program: improved safety performance; process focused on consumer needs; modern and secure campus; flexibility to respond to changing laboratory needs; bench strength for the future; and elimination of legacy issues. The Steam Pressure-Reducing Station (SPRS) Safety and Energy Efficiency Improvement Project, which is under the CPI program, focuses on maintaining and upgrading SPRSs that are part of the ORNL steam distribution network. This steam pipe network transports steam produced at the ORNL steam plant to many buildings in the main campus site. The SPRS Safety and Energy Efficiency Improvement Project promotes excellence in laboratory operations by (1) improving personnel safety, (2) decreasing fuel consumption through improved steam system energy efficiency, and (3) achieving compliance with applicable worker health and safety requirements. The SPRS Safety and Energy Efficiency Improvement Project being performed by F&O is helping ORNL improve both energy efficiency and worker safety by modifying, maintaining, and repairing SPRSs. Since work began in 2006, numerous energy-wasting steam leaks have been eliminated, heat losses from uninsulated steam pipe surfaces have been reduced, and deficient pressure retaining components have been replaced. These improvements helped ORNL

  19. 77 FR 62539 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit 2, Revocation of Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-15

    ... Background Dominion Nuclear Connecticut, Inc., (DNC or the licensee) is the holder of Facility Operating... granted DNC's request. \\1\\ Agencywide Document Access and Management System (ADAMS) Accession No... circumstances were present. Therefore, the Commission granted DNC an exemption from the requirements of 10...

  20. 77 FR 39746 - Dominion Nuclear Connecticut, Inc. Millstone Power Station, Unit 2; Environmental Assessment and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-05

    ...,'' for Facility Operating License No. DPR-65 issued to Dominion Nuclear Connecticut, Inc. (DNC or the.... Environmental Assessment Identification of the Proposed Action DNC proposed that the NRC grant exemptions to... certain requirements of 10 CFR part 50, appendix R, Section III.G.2. DNC proposed a number of OMAs in...

  1. 75 FR 67406 - Exelon Nuclear Texas Holdings, LLC; Victoria County Station Early Site Permit Application; Notice...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-02

    ... of Intent To Prepare an Environmental Impact Statement and Conduct Scoping Process Exelon Nuclear... scoping process as defined in 10 CFR 51.29. The NRC has invited the U.S. Army Corps of Engineers...). Pursuant to 36 CFR 800.8(c), the NRC staff intends to use the process and documentation for the...

  2. A Radiological Assessment Skills Training Program for the Radiation Worker at Shoreham Nuclear Power Station.

    ERIC Educational Resources Information Center

    Engel, Leonard, Jr.

    Radiation workers, by law, have the responsibility to maintain their exposure to radiation levels as low as possible. This responsibility has not been accepted. Instead, they have relied solely on the policing action of health physics (HP) technicians, thereby delegating their lawful responsibility. Continued overexposure in the U.S. nuclear power…

  3. 77 FR 26318 - Duke Energy Carolinas, LLC., Oconee Nuclear Station, Units 1, 2, and 3 Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-03

    ... materials of pressure-retaining components of the reactor coolant pressure boundary of light water nuclear... anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be... Pressure Vessel Code (Code), Code Case N- 629, ``Use of Fracture Toughness Test Data to Establish...

  4. 75 FR 9955 - Entergy Operations, Inc.; Grand Gulf Nuclear Station, Unit 1; Environmental Assessment and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-04

    ... factors, such as limited vendor resources. Environmental Impacts of the Proposed Action The NRC has... of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an... no significant impact. Environmental Assessment Identification of the Proposed Action The...

  5. 77 FR 36302 - Yankee Atomic Electric Company, Yankee Nuclear Power Station, Confirmatory Order Modifying...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-18

    ... Atomic submitted a letter to the U.S. Nuclear Regulatory Commission (NRC or the Commission) (Agencywide... Influence (FOCI) application filed with the NRC on January 3, 2012, and also provided in a letter to the NRC..., letter, contains provisions related to foreign ownership, control, or domination that include, but...

  6. UNESCO Chemistry Teaching Project in Asia: Experiments on Nuclear Science.

    ERIC Educational Resources Information Center

    Dhabanandana, Salag

    This teacher's guide on nuclear science is divided into two parts. The first part is a discussion of some of the concepts in nuclear chemistry including radioactivity, types of disintegration, radioactive decay and growth, and tracer techniques. The relevant experiments involving the use of radioisotopes are presented in the second part. The…

  7. Pollution prevention opportunity assessment United States Naval Base Norfolk Naval Air Station. Project summary

    SciTech Connect

    Bowman, D.; DeWaters, J.

    1995-09-01

    The purposes of the WREAFS Program are to identify new technologies and techniques for reducing wastes from process operations and other activities at Federal sites, and to enhance the implementation of pollution prevention/waste minimization through technology transfer. New techniques and technologies for reducing waste generation are identified through waste minimization opportunity assessments and may be further evaluated through joint research, development, and demonstration projects. A cooling tower is an enclosed device designed for the evaporative cooling of water by direct contact with air. Cooling towers are used in conjunction with air conditioning and industrial process equipment, acting as the heat sink for these systems by providing a continuous source of cool water for process operations. Open-system recirculating cooling towers are typically chosen for operation with air conditioning and refrigeration equipment because they are relatively inexpensive and minimize heat rejection costs while conserving water. All of the cooling towers at the Norfolk Naval Air Station identified in this PPOA are of the recirculating, open-system type. The Navy and EPA are currently evaluating techniques and technologies to reduce wastes generated from cooling tower operations within the Norfolk NAS. Approximately 28 open-system recirculating cooling towers are currently operated at 18 buildings within the NAS. These units range in size from 5 to 300 tons, and are all associated with comfort cooling systems that operate on a seasonal basis (approximately 6 mo/yr).

  8. Calculation Method for the Projection of Future Spent Nuclear Fuel Discharges

    SciTech Connect

    B. McLeod

    2002-02-28

    This report describes the calculation method developed for the projection of future utility spent nuclear fuel (SNF) discharges in regard to their timing, quantity, burnup, and initial enrichment. This projection method complements the utility-supplied RW-859 data on historic discharges and short-term projections of SNF discharges by providing long-term projections that complete the total life cycle of discharges for each of the current U.S. nuclear power reactors. The method was initially developed in mid-1999 to update the SNF discharge projection associated with the 1995 RW-859 utility survey (CRWMS M&O 1996). and was further developed as described in Rev. 00 of this report (CRWMS M&O 2001a). Primary input to the projection of SNF discharges is the utility projection of the next five discharges from each nuclear unit, which is provided via the revised final version of the Energy Information Administration (EIA) 1998 RW-859 utility survey (EIA 2000a). The projection calculation method is implemented via a set of Excel 97 spreadsheets. These calculations provide the interface between receipt of the utility five-discharge projections that are provided in the RW-859 survey, and the delivery of projected life-cycle SNF discharge quantities and characteristics in the format requisite for performing logistics analysis to support design of the Civilian Radioactive Waste Management System (CRWMS). Calculation method improvements described in this report include the addition of a reactor-specific maximum enrichment-based discharge burnup limit. This limit is the consequence of the enrichment limit, currently 5 percent. which is imposed as a Nuclear Regulatory Commission (NRC) license condition on nuclear fuel fabrication plants. In addition, the calculation method now includes the capability for projecting future nuclear plant power upratings, consistent with many such recent plant uprates and the prospect of additional future uprates. Finally. this report summarizes the

  9. Evaluation on the environmental radioactivity in Shanghai city during the normal operational condition of Qinshan nuclear power station.

    PubMed

    Lu, Heqing; Wang, Qiang

    2013-08-01

    The objective of this work was to evaluate the impact of environmental radioactivity in Shanghai from the operation of Qinshan Nuclear Power Station (QNPS). The levels of terrestrial gamma radiation and radioactivities in the drinking water, main food and soils in the Jinshan area where is only 38 km far away from the QNPS were continuously measured in the past 19 y. Both the levels of terrestrial gamma radiation and the radioactivities in the samples were on the normal background levels. No significant changes were found before and after the running of QNPS. The annual public exposure to the terrestrial gamma radiation was estimated to be ∼0.1 mSv, and the annual exposure from intakes of (90)Sr and (137)Cs in food was ∼0.5 μSv. In the past 19 y, no significant impact on the environmental radioactivity in Shanghai was observed due to the operation of QNPS.

  10. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    SciTech Connect

    MITCHELL, R.M.

    2000-10-12

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

  11. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    SciTech Connect

    MITCHELL, R.M.

    2000-09-28

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

  12. Iterative ct reconstruction from few projections for the nondestructive post irradiation examination of nuclear fuel assemblies

    NASA Astrophysics Data System (ADS)

    Abir, Muhammad Imran Khan

    The core components (e.g. fuel assemblies, spacer grids, control rods) of the nuclear reactors encounter harsh environment due to high temperature, physical stress, and a tremendous level of radiation. The integrity of these elements is crucial for safe operation of the nuclear power plants. The Post Irradiation Examination (PIE) can reveal information about the integrity of the elements during normal operations and off?normal events. Computed tomography (CT) is a tool for evaluating the structural integrity of elements non-destructively. CT requires many projections to be acquired from different view angles after which a mathematical algorithm is adopted for reconstruction. Obtaining many projections is laborious and expensive in nuclear industries. Reconstructions from a small number of projections are explored to achieve faster and cost-efficient PIE. Classical reconstruction algorithms (e.g. filtered back projection) cannot offer stable reconstructions from few projections and create severe streaking artifacts. In this thesis, conventional algorithms are reviewed, and new algorithms are developed for reconstructions of the nuclear fuel assemblies using few projections. CT reconstruction from few projections falls into two categories: the sparse-view CT and the limited-angle CT or tomosynthesis. Iterative reconstruction algorithms are developed for both cases in the field of compressed sensing (CS). The performance of the algorithms is assessed using simulated projections and validated through real projections. The thesis also describes the systematic strategy towards establishing the conditions of reconstructions and finds the optimal imaging parameters for reconstructions of the fuel assemblies from few projections.

  13. Performance testing of the environmental TLD system for the Three Mile Island Nuclear Station.

    PubMed

    Toke, L F; Carson, B H; Baker, G G; McBride, M H; Plato, P A; Miklos, J A

    1984-05-01

    Panasonic UD-801 thermoluminescent dosimeters ( TLDs ) containing two calcium sulfate phosphors were tested under Performance Specification 3.1 established by the American National Standard Institute ( ANSI75 ) and in the U.S. Nuclear Regulatory Commission's Regulatory Guide 4.13 ( NRC77 ). The specific qualifying tests included TLD uniformity, reproducibility, energy dependence and directional dependence. The overall measurement uncertainties and associated confidence levels are within the prescribed guidelines defined in the qualifying requirements for environmental TLDs .

  14. Nuclear propulsion technology development - A joint NASA/Department of Energy project

    NASA Technical Reports Server (NTRS)

    Clark, John S.

    1992-01-01

    NASA-Lewis has undertaken the conceptual development of spacecraft nuclear propulsion systems with DOE support, in order to establish the bases for Space Exploration Initiative lunar and Mars missions. This conceptual evolution project encompasses nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems. A technology base exists for NTP in the NERVA program files; more fundamental development efforts are entailed in the case of NEP, but this option is noted to offer greater advantages in the long term.

  15. EMSP project summary (Project ID: 60077): Development of nuclear analysis capabilities for DOE waste management activities

    SciTech Connect

    Parks, C.V.; Rearden, B.T.; DeHart, M.D.; Broadhead, B.L.; Hopper, C.M.; Petrie, L.M.

    2000-02-01

    The objective of this project is to develop and demonstrate prototypical analysis capabilities that can be used by nuclear safety analysis practitioners to: (1) demonstrate a more thorough understanding of the underlying physics phenomena that can lead to improved reliability and defensibility of safety evaluations; and (2) optimize operations related to the handling, storage, transportation, and disposal of fissile material and DOE spent fuel. To address these problems, this project has been investigating the implementation of sensitivity and uncertainty methods within existing Monte Carlo codes used for criticality safety analyses. It is also investigating the use of a new deterministic code that allows for specification of arbitrary grids to accurately model geometric details required in a criticality safety analysis. This capability can facilitate improved estimations of the required subcritical margin and potentially enable the use of a broader range of experiments in the validation process. The new arbitrary-grid radiation transport code will also enable detailed geometric modeling valuable for improved accuracy in application to a myriad of other problems related to waste characterization. Application to these problems will also be explored.

  16. Effects of the Chernobyl and Fukushima nuclear accidents on atmospheric electricity parameters recorded at Polish observation stations

    NASA Astrophysics Data System (ADS)

    Kubicki, Marek; Baranski, Piotr; Odzimek, Anna; Michnowski, Stanislaw; Myslek-Laurikainen, Bogna

    2013-04-01

    We analyse the atmospheric electricity parameters, measured at Polish geophysical stations in Swider, Poland, and Hornsund, Spitsbergen, in connection with the radioactive incident in Fukushima, Japan, beginning on 11 March 2011, following the 9.0 earthquake and tsunami. We compare our results with the situation during and after the Chernobyl disaster on April 26, 1986, when the radioactive fallout detected at Swider increased in the last week of April 1986, from 4.111 to 238.7 Bq/m2 and up to 967.0 Bq/m2 in the second week of May 1986 - what was more than 235 times greater than the values measured prior to that accident. Besides the electric field especially the electric conductivity is very sensitive to the radioactive contamination of the air. Thus we postulate that these two measurements should be run at geophysical stations over the world and used as a relatively simple and low-cost tool for continuous monitoring of possible hazard caused by nuclear power plant accidents.

  17. 76 FR 17460 - South Texas Project Nuclear Operating Company; Establishment of Atomic Safety and Licensing Board

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-29

    ... COMMISSION South Texas Project Nuclear Operating Company; Establishment of Atomic Safety and Licensing Board..., 2.318, and 2.321, notice is hereby given that an Atomic Safety and Licensing Board (Board) is being...: Ronald M. Spritzer, Chair, Atomic Safety and Licensing Board Panel, U.S. Nuclear Regulatory...

  18. The key to superior water chemistry at a PWR nuclear station

    SciTech Connect

    Dolan, R.; Miller, L.K.; Olejar, L.L.; Salem, E.

    1983-01-01

    This paper demonstrates how a condensate polishing unit can be successfully used to treat the feedwater for circulating-type pressurized water reactors (PWRs). Water chemistry at the Salem Generating Station, a two-unit, four-loop Westinghouse PWR located in New Jersey, is discussed. Topics considered include a plant description and the history of early operation, the role of constant surveillance, makeup water quality, the effect of freezing on gel-type anion exchange resin, a total organic carbon (TOC) survey, steam generator chemistry, steam generator inspection, condensate polisher operation, and management philosophy. The SEPREX condensate polishing process, in which the complete separation of the anion exchange resin from the cation exchange resin is achieved by flotation separation, is examined. It is concluded that the utilization of a condensate polishing process such as SEPREX provides the operating personnel at the plant with the necessary means to maintain the minimum desired level of contaminants within the steam generator.

  19. Nuclear Propulsion in Space (1968)

    SciTech Connect

    2012-06-23

    Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

  20. Nuclear Propulsion in Space (1968)

    ScienceCinema

    None

    2016-07-12

    Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

  1. Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations

    SciTech Connect

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W.; Morcos, N.

    1992-01-01

    The effects of varying pH and leachant compositions on the physical stability and leachability of radionuclides and chelating agents were determined for cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small scale waste-form specimens were collected during waste solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station. The collected specimens were leach tested, and their compressive strength was measured in accordance with the Nuclear Regulatory Commission's Technical Position on Waste Form'' (Revision 1), from the Low-Level Waste Management Branch. Leachates from these studies were analyzed for radionuclides, selected transition metals, and chelating agents to assess the leachability of these waste form constituents. Leachants used for the study were deionized water, simulated seawater, and groundwater compositions similar to those found at Barnwell, South Carolina and Hanford, Washington. Results of this study indicate that initial leachant pH does not affect leachate pH or releases from cement-solidified decontamination ion-exchange resin waste forms. However, differences in leachant composition and the presence of chelating agents may affect the releases of radionuclides and chelating agents. In addition, results from this study indicate that the cumulative releases of radionuclides and chelating agents observed for forms that disintegrated were similar to those for forms that maintained their general physical integrity.

  2. Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations

    SciTech Connect

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W.; Morcos, N.

    1992-08-01

    The effects of varying pH and leachant compositions on the physical stability and leachability of radionuclides and chelating agents were determined for cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small scale waste-form specimens were collected during waste solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station. The collected specimens were leach tested, and their compressive strength was measured in accordance with the Nuclear Regulatory Commission`s ``Technical Position on Waste Form`` (Revision 1), from the Low-Level Waste Management Branch. Leachates from these studies were analyzed for radionuclides, selected transition metals, and chelating agents to assess the leachability of these waste form constituents. Leachants used for the study were deionized water, simulated seawater, and groundwater compositions similar to those found at Barnwell, South Carolina and Hanford, Washington. Results of this study indicate that initial leachant pH does not affect leachate pH or releases from cement-solidified decontamination ion-exchange resin waste forms. However, differences in leachant composition and the presence of chelating agents may affect the releases of radionuclides and chelating agents. In addition, results from this study indicate that the cumulative releases of radionuclides and chelating agents observed for forms that disintegrated were similar to those for forms that maintained their general physical integrity.

  3. Comparison and evaluation of nuclear power plant options for geosynchronous power stations

    NASA Technical Reports Server (NTRS)

    Williams, J. R.

    1975-01-01

    The suitability of eleven types of nuclear fission reactors in combination with five potential energy conversion systems for use in geosynchronous power plants is evaluated. Gas turbine, potassium Rankine liquid metal MHD, and thermionic energy conversion systems are considered. The existing technology of reactors in near-term, intermediate-term, and long-term classes is discussed, together with modifications for use in large-scale power production in space. Unless the temperature is high enough for MHD, reactors which heat gases are generally more suitable for use with gas turbines. Those which heat liquid metals will be more useful for potassium Rankine or liquid metal MHD conversion systems.

  4. [Discirculatory encephalopathy in liquidators of the Chernobyl nuclear power station: a twenty-year study].

    PubMed

    Podsonnaia, I V; Shumakher, G I; Golovin, V A

    2009-01-01

    A comparative twenty-year study of 536 liquidators of the Chernobyl nuclear disaster and 436 patients without radiation anamnesis has been carried out. Discirculatory encephalopathy (DE) was more often developed in subjects exposed to radiation at the age 30 years. Compared to individuals from the general population, it is characterized by the earlier onset, malignant progression, rapid increase of signs of cerebral affection during the first two years after exposure to radiation, stability of clinical symptoms during the following 5-6 years and further progressive cerebral decompensation with early autonomic dysfunction, psychoorganic syndrome, epilepsy. Moreover, severe stroke is a common complication of DE in liquidators.

  5. Technical evaluation of RETS-required reports for Fort St. Vrain Nuclear Generating Station

    SciTech Connect

    Young, T E; Magleby, E H

    1985-06-14

    A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 6 refs.

  6. ENVIRONMENTAL RESEARCH BRIEF: WASTE REDUCTION ACTIVITIES AND OPTIONS FOR A NUCLEAR POWERED ELECTRICAL GENERATING STATION.

    EPA Science Inventory

    The U.S. Environmental Protection Agency (EPA) funded a project with the New Jersey Department of Environmental Protection and Energy (NJDEPE) to assist in conducting waste minimization assessments at thirty small- to medium-sized businesses in the state of New Jersey. One of th...

  7. Decay Data Evaluation Project: Evaluation of (52)Fe nuclear decay data.

    PubMed

    Luca, Aurelian

    2016-03-01

    Within the Decay Data Evaluation Project (DDEP) and the IAEA Coordinated Research Project no. F41029, the evaluation of the nuclear decay data of (52)Fe, a radionuclide of interest in nuclear medicine, was performed. The main nuclear decay data evaluated are: the half-life, decay energy, energies and probabilities of the electron capture and β(+) transitions, internal conversion coefficients and gamma-ray energies and emission intensities. This new evaluation, made using the DDEP methodology and tools, was included in the DDEP database NUCLEIDE.

  8. The Communication of Information Such as Evacuation Orders at the Time of a Nuclear Power Station Accident

    PubMed Central

    HATANAKA, Takashi; YOSHIDA, Sumito; OJINO, Mayo; ISHII, Masami

    2014-01-01

    This research was carried out from the perspective that the damage to the people of Fukushima and others from the Fukushima Daiichi Nuclear Power Station (NPS) accident was an “information disaster.” It evaluated the critical problems raised by and actual condition analysis on the process of events in the Fukushima Daiichi NPS disaster and responses of the governments and others, notification of the occurrence of the accident and evacuation order by the national and local governments and the evacuation of residents, and guidance for distribution and intake of stable iodine tablets. The research aimed to provide a basis for the implementation of effective distribution and intake of stable iodine tablets and responses to the “information disaster” in the nuclear power disaster. On March 15 at the time that the most radioactive substances were dispersed, even when the average wind speed at the site area was 1.6 m/s, the radioactive substances had reached the outer boundary of Urgent Protective action planning Zone (UPZ, the region with a radius of 30 km) within about five hours. Because of this, every second counted in the provision of information about the accident and the issuance of evacuation orders. This study evaluated the actual condition of information provision by the national government and others from the perspective of this awareness of the importance of time. On the basis of the results of this kind of consideration, we come to the following recommendations: The Nuclear Emergency Response Guidelines and the system for communication of information to medical providers should be revised. The national government should make preparations for the effective advance distribution and intake of stable iodine tablets. PMID:26557446

  9. The accident at TEPCO's Fukushima-Daiichi Nuclear Power Station: What went wrong and what lessons are universal?

    NASA Astrophysics Data System (ADS)

    Omoto, Akira

    2013-12-01

    After a short summary of the nuclear accident at the Fukushima Daiichi Nuclear Power Station, this paper discusses “what went wrong” by illustrating the problems of the specific layers of defense-in-depth (basic strategy for assuring nuclear safety) and “what lessons are universal.” Breaches in the multiple layers of defense were particularly significant in respective protection (a) against natural disasters (first layer of defense) as well as (b) against severe conditions, specifically in this case, a complete loss of AC/DC power and isolation from the primary heat sink (fourth layer of defense). Confusion in crisis management by the government and insufficient implementation of offsite emergency plans revealed problems in the fifth layer of defense. By taking into consideration managerial and safety culture that might have relevance to this accident, in the author's view, universal lessons are as follows: Resilience: the need to enhance organizational capabilities to respond, monitor, anticipate, and learn in changing conditions, especially to prepare for the unexpected. This includes increasing distance to cliff edge by knowing where it exists and how to increase safety margin. Responsibility: the operator is primarily responsible for safety, and the government is responsible for protecting public health and environment. For both, their right decisions are supported by competence, knowledge, and an understanding of the technology, as well as humble attitudes toward the limitations of what we know and what we can learn from others. Social license to operate: the need to avoid, as much as possible regardless of its probability of occurrence, the reasonably anticipated environmental impact (such as land contamination), as well as to build public confidence/trust and a renewed liability scheme.

  10. Variation after projection with a triaxially deformed nuclear mean field

    NASA Astrophysics Data System (ADS)

    Gao, Zao-Chun; Horoi, Mihai; Chen, Y. S.

    2015-12-01

    We implemented a variation after projection (VAP) algorithm based on a triaxially deformed Hartree-Fock-Bogoliubov vacuum state. This is the first projected mean field study that includes all the quantum numbers (except parity), i.e., spin (J ), isospin (T ), and mass number (A ). Systematic VAP calculations with JTA projection have been performed for the even-even s d -shell nuclei with the USDB Hamiltonian. All the VAP ground state energies are within 500 keV above the exact shell model values. Our VAP calculations show that the spin projection has two important effects: (1) the spin projection is crucial in achieving good approximation of the full shell model calculation; (2) the intrinsic shapes of the VAP wave functions with spin projection are always triaxial, while the Hartree-Fock-Bogoliubov methods likely provide axial intrinsic shapes. Finally, our analysis suggests that one may not be possible to associate an intrinsic shape to an exact shell model wave function.

  11. Optimization of the calibration graph for the determination of anions in the heat carrier of a nuclear power station by two-column ion chromatography

    SciTech Connect

    Bragina, N.V.; Karpyuk, A.D.

    1995-10-01

    Methods upgrading the reliability of analyzing Cl{sup -} and SO{sub 4}{sup 2-} ions in the heat carrier of a nuclear power station are considered. The use of a multilevel calibration plot and eluent-modifying additives is shown to provide reliable determination of the above-mentioned ions in the range of 0.5-20 {mu}g/liter.

  12. Overview of implementing a project control system in the nuclear utility industry

    SciTech Connect

    Cooprider, D.H. )

    1994-03-01

    During the late 1980s, a metamorphosis began at Florida Power and Light Company (FPL). A strategic step in nuclear engineering's efforts to become more cost effective began in January 1990. A project control department was formed. The initial mission was to provide support for nuclear engineering design activities associated with FPL's two twin-unit nuclear power generation facilities - Turkey Point and St. Lucie. Later, the goal expanded to include the division's materials management, nuclear licensing, and information management departments. The project control group was organized along the lines of the organizations served. Separate dedicated groups were established for each plant. Since most engineering activity was based at the Juno Beach headquarters, the project control staff also was based there.

  13. Memorandum of Understanding (MOU) Completion and Acceptance of the Spent Nuclear Fuel (SNF) Project

    SciTech Connect

    NISHIKAWA, L.D.

    1999-11-23

    This Memorandum of Understanding (MOU) is written to provide clear direction with respect to roles, responsibilities, obligations, and expectations of each organization identified. It functions as an agreement between the Operations, Construction Projects and Startup Organizations within the Spent Nuclear Fuels Project.

  14. The controlled ecological life support system Antarctic analog project: Analysis of wastewater from the South Pole Station, Antarctica, volume 1

    NASA Technical Reports Server (NTRS)

    Flynn, Michael T.; Bubenheim, David L.; Straight, Christian L.; Belisle, Warren

    1994-01-01

    The Controlled Ecological Life Support system (CELSS) Antarctic Analog Project (CAAP) is a joint National Science Foundation (NSF) and NASA project for the development, deployment and operation of CELSS technologies at the Amundsen-Scott South Pole Station. NASA goals are operational testing of CELSS technologies and the conduct of scientific studies to facilitate technology selection and system design. The NSF goals are that the food production, water purification, and waste treatment capabilities which will be provided by CAAP will improve the quality of life for the South Pole inhabitants, reduce logistics dependence, and minimize environmental impacts associated with human presence on the polar plateau. This report presents an analysis of wastewater samples taken from the Amundsen-Scott South Pole Station, Antarctica. The purpose of the work is to develop a quantitative understanding of the characteristics of domestic sewage streams at the South Pole Station. This information will contribute to the design of a proposed plant growth/waste treatment system which is part of the CELSS Antarctic Analog Project (CAAP).

  15. The NASA Advanced Exploration Systems Nuclear Thermal Propulsion Project

    NASA Technical Reports Server (NTRS)

    Houts, Michael G.; Mitchell, Doyce P.; Kim, Tony; Emrich, William J.; Hickman, Robert R.; Gerrish, Harold P.; Doughty, Glen; Belvin, Anthony; Clement, Steven; Borowski, Stanley K.; Scott, John; Power, Kevin P.

    2015-01-01

    The fundamental capability of Nuclear Thermal Propulsion (NTP) is game changing for space exploration. A first generation NTP system could provide high thrust at a specific impulse (Isp) above 900 s, roughly double that of state of the art chemical engines. Characteristics of fission and NTP indicate that useful first generation systems will provide a foundation for future systems with extremely high performance. The role of a first generation NTP in the development of advanced nuclear propulsion systems could be analogous to the role of the DC-3 in the development of advanced aviation systems.

  16. Accelerated Closure of the Spent Nuclear Fuel (SNF) project

    SciTech Connect

    RUTHERFORD, W.W.

    2001-02-01

    The K East and K West Basins, built in the early 1950s, have been used to store irradiated nuclear fuel from the Hanford N Reactor. This fuel, which is referred to as spent nuclear fuel (SNF), has been stored underwater since 1975 in KE Basin and since 1981 in KW Basin. There are 54,000 N Reactor fuel assemblies in 3,800 canisters in the K West Basin, and 51,000 fuel assemblies in 3,700 canisters in the K East Basin that total 2,100 metric tons of SNF.

  17. Projecting labor demand and worker immigration at nuclear power plant construction sites: an evaluation of methodology

    SciTech Connect

    Herzog, H.W. Jr; Schlottmann, A.M.; Schriver, W.R.

    1981-12-01

    The study evaluates methodology employed for the projection of labor demand at, and worker migration to, nuclear power plant construction sites. In addition, suggestions are offered as to how this projection methodology might be improved. The study focuses on projection methodologies which forecast either construction worker migration or labor requirements of alternative types of construction activity. Suggested methodological improvements relate both to institutional factors within the nuclear power plant construction industry, and to a better use of craft-specific data on construction worker demand/supply. In addition, the timeliness and availability of the regional occupational data required to support, or implement these suggestions are examined.

  18. The Feed Materials Program of the Manhattan Project: A Foundational Component of the Nuclear Weapons Complex

    NASA Astrophysics Data System (ADS)

    Reed, B. Cameron

    2014-12-01

    The feed materials program of the Manhattan Project was responsible for procuring uranium-bearing ores and materials and processing them into forms suitable for use as source materials for the Project's uranium-enrichment factories and plutonium-producing reactors. This aspect of the Manhattan Project has tended to be overlooked in comparison with the Project's more dramatic accomplishments, but was absolutely vital to the success of those endeavors: without appropriate raw materials and the means to process them, nuclear weapons and much of the subsequent cold war would never have come to pass. Drawing from information available in Manhattan Engineer District Documents, this paper examines the sources and processing of uranium-bearing materials used in making the first nuclear weapons and how the feed materials program became a central foundational component of the postwar nuclear weapons complex.

  19. Aberrant "Barbed-Wire" Nuclear Projections of Neutrophils in Trisomy 18 (Edwards Syndrome).

    PubMed

    Kahwash, Basil M; Nowacki, Nicholas B; Kahwash, Samir B

    2015-01-01

    We discuss the significance of neutrophils with increased, aberrant nuclear projections mimicking "barbed-wire" in a newborn child with trisomy 18 (T18). Increased, aberrant nuclear projections have been previously reported in trisomy of the D group of chromosomes (chromosomes 13, 14, and 15), and we report similar findings in a patient with T18. The peripheral blood smear showed relative neutrophilia with the majority (37%) of neutrophils showing two or more thin, rod-shaped or spike-shaped, and often pedunculated aberrant nuclear projections. The number of projections ranged from 2 to 6 per cell, averaged 2 per affected neutrophil, and ranged in length from 0.22 μm to 0.83 μm. This case confirms that the morphologic finding described is not restricted to trisomy of one of the chromosomes in group D, as implied in the literature.

  20. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, December 1981-February 1982

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1982-08-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. In the winter of 1981, the generating station experienced a prolonged outage. The reproductive cycle of the shipworms was not extended. Teredo bartschi was very abundant at one station in Oyster Creek and moderately abundant at a second, but did not exist elsewhere in Barnegat Bay. Some specimens of Teredo bartschi contained larvae in the gills in February. According to laboratory experiments, Teredo navalis is able to remain active at temperatures as low as 4/sup 0/C, whereas T. bartschi ceases activity (withdraws its siphons) at about 13/sup 0/C. 12 tables.

  1. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, March-May 1982

    SciTech Connect

    Hoagland, K.E.

    1982-11-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. The adult population of Teredo bartschi survived the winter and spring of 1981-1982 better than it did previous cold periods without a thermal effluent. Lack of an effluent was due to a prolonged outage of the generating station. There was no spring outbreak of shipworms. The introduced species appears established at one station near but outside of Oyster Creek. Three teredinid species coexist in Oyster Creek. Larvae of T. bartschi and T. navalis have similar responses to reduced salinity. Bankia gouldi is the fastest-growing of the teredinids found in New Jersey, and as the lowest annual mortality.

  2. Nuclear and fundamental physics instrumentation for the ANS project

    SciTech Connect

    Robinson, S.J.; Raman, S.; Arterburn, J.; McManamy, T.; Peretz, F.J.; Faust, H.; Piotrowski, A.E.

    1996-05-01

    This report summarizes work carried out during the period 1991-1995 in connection with the refinement of the concepts and detailed designs for nuclear and fundamental physics research instrumentation at the proposed Advanced Neutron source at Oak Ridge National Laboratory. Initially, emphasis was placed on refining the existing System Design Document (SDD-43) to detail more accurately the needs and interfaces of the instruments that are identified in the document. The conceptual designs of these instruments were also refined to reflect current thinking in the field of nuclear and fundamental physics. In particular, the on-line isotope separator (ISOL) facility design was reconsidered in the light of the development of interest in radioactive ion beams within the nuclear physics community. The second stage of this work was to define those instrument parameters that would interface directly with the reactor systems so that these parameters could be considered for the ISOL facility and particularly for its associated ion source. Since two of these options involved ion sources internal to the long slant beam tube, these were studied in detail. In addition, preliminary work was done to identify the needs for the target holder and changing facility to be located in the tangential through-tube. Because many of the planned nuclear and fundamental physics instruments have similar needs in terms of detection apparatus, some progress was also made in defining the parameters for these detectors. 21 refs., 32 figs., 2 tabs.

  3. Know Nukes: A Nuclear Power Issues Curriculum Project.

    ERIC Educational Resources Information Center

    Butterfield, Charlie; McCandless, Marjorie

    Classroom activities are presented to help teachers introduce general controversial issues and specific issues on nuclear power in their high school science, social studies, and English classes. Objectives are to help students understand the various techniques of persuasion; the relationship between bias, persuasion, and fact; how these techniques…

  4. Fuel Retrieval Sub (FRS) Project Decapping Station Performance Test Data Report

    SciTech Connect

    THIELGES, J.R.

    2000-01-13

    This document is to provide the test data report for Decapping Station Performance Testing. These performance tests were full scale and viewed as a continuation of development testing performed earlier (SNF-2710). A prototype decapping station confinement box was tested, along with some special tools required for the process, providing assurance that the fuel handling equipment will operate as designed, allowing for release of the FRS equipment for installation.

  5. Pu isotopes in the western North Pacific Ocean before the accident at Fukushima Dai-ichi Nuclear Power Station

    NASA Astrophysics Data System (ADS)

    Yamada, M.; Zheng, J.; Aono, T.

    2011-12-01

    Anthropogenic radionuclides such as Pu-239 (half-life: 24100 yr), Pu-240 (half-life: 6560 yr) and Pu-241 (half-life: 14.325 yr) mainly have been released into the environment as the result of atmospheric nuclear weapons testing. In the North Pacific Ocean, two distinct sources of Pu isotopes can be identified; i.e., the global stratospheric fallout and close-in tropospheric fallout from nuclear weapons testing at the Pacific Proving Grounds in the Marshall Islands. The atom ratio of Pu-240/Pu-239 is a powerful fingerprint to identify the sources of Pu in the ocean. The Pu-240/Pu-239 atom ratios in seawater and marine sediment samples collected in the western North Pacific before the accident at Fukushima Dai-ichi Nuclear Power Station will provide useful background data for understanding the process controlling Pu transport and for distinguishing future Pu sources. The atom ratios of Pu-240/Pu-239 in water columns from the Yamato and Tsushima Basins in the Japan Sea were significantly higher than the mean global fallout ratio of 0.18; however, there were no temporal variation of atom ratios during the period from 1984 to 1993 in the Japan Sea. The total Pu-239+240 inventories in the whole water columns were approximately doubled during the period from 1984 to 1993 in the two basins. The atom ratio of Pu-240/Pu-239 in surface water from Sagami Bay, western North Pacific Ocean, was 0.224 and showed no notable variation from the surface to the bottom with the mean atom ratio being 0.234. The atom ratios for the Pacific coast, near the Rokkasho nuclear fuel reprocessing plant, were approximately the same as the 0.224 ratio obtained from Sagami Bay, western North Pacific margin. The atom ratios in the surficial sediments from Sagami Bay ranged from 0.229 to 0.247. The mean atom ratio in the sediment columns in the East China Sea ranged from 0.248 for the Changjiang estuary to 0.268 for the shelf edge. The observed atom ratios were significantly higher than the mean

  6. Organohalogen products from chlorination of cooling water at nuclear power stations

    SciTech Connect

    Bean, R.M.

    1983-10-01

    Eight nuclear power units at seven locations in the US were studied to determine the effects of chlorine, added as a biocide, on the composition of cooling water discharge. Water, sediment and biota samples from the sites were analyzed for total organic halogen and for a variety of organohalogen compounds. Haloforms were discharged from all plants studied, at concentrations of a few ..mu..g/L (parts-per-billion). Evidence was obtained that power plants with cooling towers discharge a significant portion of the haloforms formed during chlorination to the atmosphere. A complex mixture of halogenated phenols was found in the cooling water discharges of the power units. Cooling towers can act to concentrate halogenated phenols to levels approaching those of the haloforms. Examination of samples by capillary gas chromatography/mass spectrometry did not result in identification of any significant concentrations of lipophilic base-neutral compounds that could be shown to be formed by the chlorination process. Total concentrations of lipophilic (Bioabsorbable) and volatile organohalogen material discharged ranged from about 2 to 4 ..mu..g/L. Analysis of sediment samples for organohalogen material suggests that certain chlorination products may accumulate in sediments, although no tissue bioaccumulation could be demonstrated from analysis of a limited number of samples. 58 references, 25 figures, 31 tables.

  7. Environmental radiological studies downstream from the Rancho Seco Nuclear Power Generating Station, 1985

    SciTech Connect

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Brunk, J.L.; Jokela, T.A.

    1986-02-06

    Information compiled in 1985 while assessing the environmental impact of radionuclides previously discharged with aqueous releases from the Rancho Seco Nuclear Power Generating Plant is presented. In October 1984, the quantities of gamma-emitting radionuclides in water discharged to Clay Creek from the plant were reduced below operationally defined detection limits for liquid effluents. However, radionuclides previously discharged persist in the downstream environment and are found in many aquatic dietary components. /sup 134/Cs and /sup 137/Cs are the primary gamma-emitting radionuclides detected in the edible flesh of different fish, crayfish, and frogs. Coefficients for exponential equations are generated, from a least square analysis, that relate the change in concentration of /sup 137/Cs in fish to distance downstream and time between March and October 1985. Concentrations of /sup 137/Cs in surface creek sediments also decreased in the downstream direction much in the same manner as concentrations decreased in fish. However, there was no significant difference in the radiocesium concentrations in surface sediements collected from comparable locations during both 1984 and 1985.

  8. New idea of geomagnetic monitoring through ENA detection from the International Space Station: ENAMISS project

    NASA Astrophysics Data System (ADS)

    Milillo, Anna; De Angelis, Elisabetta; Orsini, Stefano; Rubini, Alda; Evangelista, Yuri; Mura, Alessandro; Rispoli, Rosanna; Vertolli, Nello; Carrubba, Elisa; Donati, Alessandro; Di Lellis, Andrea Maria; Plainaki, Christina; Lazzarotto, Francesco

    2016-04-01

    Remote sensing of Energetic Neutral Atoms (ENA) in the Earth's environment has been proven to be a successful technique able to provide detailed information on the ring current plasma population at energies below 100 keV. Indeed, the existing space weather databases usually include a good coverage of Sun and solar wind monitoring. The global imaging of the Earth's magnetosphere/ ionosphere is usually obtained by the high-latitudes monitoring of aurorae, ground magnetic field variations and high-latitude radio emissions. The equatorial magnetic field variations on ground, from which the geomagnetic indices like Dst, Sym-H and Asym-H are derived, include the effects of all current systems (i.e. ring current, Chapman -Ferraro current, tails currents, etc...) providing a kind of global information. Nevertheless, the specific information related to the ring current cannot be easily derived from such indices. Only occasional local plasma data are available by orbiting spacecraft. ENA detection is the only way to globally view the ring current populations. Up-to-now this technique has been used mainly from dedicated high altitude polar orbiting spacecraft, which do not allow a continuous and systematic monitoring, and a discrimination of the particle latitude distribution. The Energetic Neutral Atoms Monitor on the International space Station (ENAMISS) project intends to develop an ENA imager and install it on the ISS for continuous monitoring of the spatially distributed ring current plasma population. ISS is the ideal platform to perform continuous ENA monitoring since its particular low altitude and medium/low latitude orbit allows wide-field ENA images of various magnetospheric regions. The calibrated ENA data, the deconvolved ion distributions and ad-hoc ENA-based new geomagnetic indices will be freely distributed to the space weather community. Furthermore, new services based on plasma circulation models, spacecraft surface charging models and radiation dose models

  9. Advanced Elastic/Inelastic Nuclear Data Development Project

    SciTech Connect

    Harmon, Frank; Chowdhury, Partha; Greife, Uwe; Fisher Hicks, Sally; Tsvetkov, Pavel; Rahn Vanhoy, Jeffrey; Hill, Tony; Kawano, Toshihiko; Slaughter, David

    2015-06-08

    The optical model is used to analyze the elastic and inelastic scattering of nucleons, deuterons, hellions, tritons, and alpha particles by the nuclei. Since this paper covers primarily neutron-nucleus scattering, the focus will be limited to only that interaction. For the sake of this model, the nucleus is described as a blob of nuclear matter with properties based upon its number of nucleons. This infers that a single potential can describe the interaction of particles with different energies with different nuclei.

  10. New Generation Nuclear Plant (NGNP) Project, Preliminary Point Design

    SciTech Connect

    F. H. Southworth; P. E. MacDonald; A. M. Baxter; P. D. Bayless; J. M. Bolin; H. D. Gougar; R. L. Moore; A. M. Ougouag; M. B. Richards; R. L. Sant; J. W. Sterbentz; W. K. Terry

    2004-03-01

    This paper provides a preliminary assessment of two possible versions of the Next Generation Nuclear Plant (NGNP), a prismatic fuel type helium gas-cooled reactor and a pebblebed fuel helium gas reactor. Both designs will meet the three basic requirements that have been set for the NGNP: a coolant outlet temperature of 1000 C, passive safety, and a total power output consistent with that expected for commercial high-temperature gas-cooled reactors.

  11. [Peculiarities of the neurological status and electroencephalogram in operators of the control unit of nuclear power station].

    PubMed

    Laskova, I V; Tret'iakova, E E

    2008-01-01

    One hundred and five operators of the control unit of the Kursk nuclear power station (NPS) have been studied: 45 people after the shift (main group) and 60 - in the day off. The shift was found to exert a significant influence on the functional state of the nervous system promoting the development or aggravation of autonomous dysfunction. In some cases, it causes an elevation of blood pressure to the level of risk for cerebral vascular disease. The effect of shift on the cerebral bioelectric activity of NPS operators manifests itself in the decrease of percentage of unchanged EEG, increase of alpha-rhythm spectral power density in the parietal leads and theta-rhythm in the posterior temporal and parietal leads. These changes may be caused by weariness as well as the effects of adverse factors the operators were exposed to at the NPS. The authors suggest to include the methods of evaluating of autonomous dysfunction and recording of alpha-rhythm spectral power density in the parietal leads and theta-rhythm in the posterior temporal and parietal leads in a special clinical examination of NPS operators.

  12. The activity of superoxide dismutase in animal liver and erythrocyte at Sea Area nearby Dayawan Nuclear Power Station

    SciTech Connect

    Cheng, Ge; Cai, Yana; Chen, Huizhen

    1995-11-01

    Many tests, the effect of ionizing radiation on SOD in vivo and vitro, had proved that the irradiation can cause the SOD activity to decrease with the increase of irradiation dose, change some physicochemical properties and structure. This artical was to study the activity of SOD in Fish (Thearpon jorbua) and Toad(Bufo melanostictus) liver erythrocyte at sea area nearby Dayawan Nuclear Power Station (Nps). We found that the SOD activity in fish liver, after NPS revolved one year, was higher than that of before revoling (7.30 {plus_minus} 1.35U/mg protein, 5.49 {plus_minus}1.56 U/mg protein respectively). The SOD activity in the toad liver at NPS revolving one year after was decreased (4.54 {plus_minus} 0.75 U/mg protein 5.68{plus_minus} 1.49U/mg protein P < 0.001) but in erythrocyte increased (2.32 {plus_minus} 0.75 U/mg Hb, 0.70 {plus_minus} 0.33 U/mg Hb P < 0.001). These results indicated that the SOD activity was changed in different with the animal variety. The effect of irradiation on fish at present was absent, on toad need to research in the future.

  13. ASSESSMENT OF RADIONUCLIDE RELEASE FROM INTACT STRUCTURES BACKFILLED WITH CONTAMINATED CONCRETE AT THE YANKEE NUCLEAR POWER STATION.

    SciTech Connect

    SULLIVAN, T.

    2004-09-30

    This calculation determines the release of residual radioactivity (including H-3, C-14, Co-60, Ni-63, Sr-90, and Cs-137), from subsurface structures filled with concrete debris at the Yankee Nuclear Power Station. Analyses were performed to assess the rate of release from the source of contamination and the resulting dose in the groundwater pathway. Two mechanisms were considered, diffusive release from the concrete structures (walls and floors) that remain intact and sorption onto concrete backfill placed within these structures. RESRAD was used to calculate the predicted maximum dose assuming a unit loading of 1 pCi/g on the intact structures. To the extent possible, the same assumptions in the soil DCGL calculations performed for Yankee Atomic were used in the calculation. However, modifications to some input parameter values were needed to represent the geometry of the subsurface facilities, flow through these facilities, and releases from the backfill and intact structures. Input parameters specific to these calculations included the leach rate, disposal geometry, pumping rate, porosity and bulk density. The dose results for a unit loading of 1 pCi/g on intact structures showed that Sr-90 had the highest dose (3.67E-02 mrem/yr).

  14. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Quarterly progress report 1 Dec 80-28 Feb 81

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1981-08-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Relative destructiveness and competition among the species are being analyzed. The native species Teredo navalis and Bankia gouldi coexist with the introduced T. bartschi in Oyster Creek and at the mouth of Forked River. An increase in mortality occurred in January. By February, Teredo bartschi was found only at Bayside.

  15. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Quarterly report, 1 September-30 November 1980

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1981-04-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Relative destructiveness and competition among the species are being analyzed. The native species Teredo navalis and Bankia gouldi coexist with the introduced T. bartschi in Oyster Creek and at the mouth of Forked River.

  16. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report 1 Jun-31 Aug 80

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1981-02-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Relative destructiveness and competition among the species are being analyzed. The native species Teredo navalis and Bankia gouldi coexist with the introduced T. bartschi in Oyster Creek. Teredo bartschi can withstand higher temperatures than the native species, but all species suffer osmotic stress at 6 parts per thousand by weight.

  17. Risk-based inservice testing program modifications at Palo Verde nuclear generating station

    SciTech Connect

    Knauf, S.; Lindenlaub, B.; Linthicum, R.

    1996-12-01

    Arizona Public Service Company (APS) is investigating changes to the Palo Verde Inservice Testing (IST) Program that are intended to result in the reduction of the required test frequency for various valves in the American Society of Mechanical Engineers (ASME) Section XI IST program. The analytical techniques employed to select candidate valves and to demonstrate that these frequency reductions are acceptable are risk based. The results of the Palo Verde probabilistic risk assessment (PRA), updated in June 1994, and the risk significant determination performed as part of the implementation efforts for 10 CFR 50.65 (the maintenance rule) were used to select candidate valves for extended test intervals. Additional component level evaluations were conducted by an `expert panel.` The decision to pursue these changes was facilitated by the ASME Risk-Based Inservice Testing Research Task Force for which Palo Verde is participating as a pilot plant. The NRC`s increasing acceptance of cost beneficial licensing actions and risk-based submittals also provided incentive to seek these changes. Arizona Public Service is pursuing the risk-based IST program modification in order to reduce the unnecessary regulatory burden of the IST program through qualitative and quantitative analysis consistent with maintaining a high level of plant safety. The objectives of this project at Palo Verde are as follows: (1) Apply risk-based technologies to IST components to determine their risk significance (i.e., high or low). (2) Apply a combination of deterministic and risk-based methods to determine appropriate testing requirements for IST components including improvement of testing methods and frequency intervals for high-risk significant components. (3) Apply risk-based technologies to high-risk significant components identified by the {open_quotes}expert panel{close_quotes} and outside of the IST program to determine whether additional testing requirements are appropriate.

  18. Nuclear quadrupole resonance studies project. [spectrometer design and spectrum analysis

    NASA Technical Reports Server (NTRS)

    Murty, A. N.

    1978-01-01

    The participation of undergraduates in nuclear quadrupole resonance research at Grambling University was made possible by NASA grants. Expanded laboratory capabilities include (1) facilities for high and low temperature generation and measurement; (2) facilities for radio frequency generation and measurement with the modern spectrum analyzers, precision frequency counters and standard signal generators; (3) vacuum and glass blowing facilities; and (4) miscellaneous electronic and machine shop facilities. Experiments carried out over a five year period are described and their results analyzed. Theoretical studies on solid state crystalline electrostatic fields, field gradients, and antishielding factors are included.

  19. In-place nuclear reactor vessel annealing demonstration project

    SciTech Connect

    Howell, D.

    1994-09-01

    The objective of this paper was a discussion of the proposed annealing demonstration project at the canceled Marble Hill-1 reactor. The discussion, which was a compilation of transparencies on the noted subject, included overall objectives, scope of work, staging of equipment, and analytical objectives. Current status, including funding was summarized.

  20. Projective measurement of a single nuclear spin qubit by using two-mode cavity QED.

    PubMed

    Eto, Yujiro; Noguchi, Atsushi; Zhang, Peng; Ueda, Masahito; Kozuma, Mikio

    2011-04-22

    We report the implementation of projective measurement on a single 1/2 nuclear spin of the (171)Yb atom by measuring the polarization of cavity-enhanced fluorescence. To obtain cavity-enhanced fluorescence having a nuclear-spin-dependent polarization, we construct a two-mode cavity QED system, in which two cyclic transitions are independently coupled to each of the orthogonally polarized cavity modes, by manipulating the energy level of (171)Yb. This system can associate the nuclear spin degrees of freedom with the polarization of photons, which will facilitate the development of hybrid quantum systems.

  1. Cortical and medullary somatosensory projections to the cochlear nuclear complex in the hedgehog tenrec.

    PubMed

    Wolff, A; Künzle, H

    1997-01-17

    Various tracer substances were injected into the spinal cord, the dorsal column nuclei, the trigeminal nuclear complex and the somatosensory cortex in Madagascan hedgehog tenrecs. With the exception of the cases injected exclusively into the spinal cord all injections gave rise to sparse, but distinct anterograde projections to the cochlear nuclear complex, particularly the granular cell domain within and outside of the dorsal cochlear nucleus. Among these cochlear afferents the projection from the primary somatosensory cortex is the most remarkable because the hedgehog tenrec has one of the lowest encephalisation indices among mammals and a similar cortico-cochlear connection has not been demonstrated so far in other species.

  2. NASA Human Research Program (HRP). International Space Station Medical Project (ISSMP)

    NASA Technical Reports Server (NTRS)

    Sams, Clarence F.

    2009-01-01

    This viewgraph presentation describes the various flight investigations performed on the International Space Station as part of the NASA Human Research Program (HRP). The evaluations include: 1) Stability; 2) Periodic Fitness Evaluation with Oxygen Uptake Measurement; 3) Nutrition; 4) CCISS; 5) Sleep; 6) Braslet; 7) Integrated Immune; 8) Epstein Barr; 9) Biophosphonates; 10) Integrated cardiovascular; and 11) VO2 max.

  3. Summary for the Next Generation Nuclear Plant Project in Review

    SciTech Connect

    L.E. Demick

    2010-09-01

    This paper reports on the major progress that the NGNP Project has made toward developing and commercializing the HTGR technology. Significant R&D progress has been made in addressing key technical issues for qualification of the HTGR fuel and graphite, codification of high temperature materials and verification and validation of design codes. Work is also progressing in heat transfer/transport design and testing and in development of the high temperature steam electrolysis hydrogen production process. A viable licensing strategy has been formulated in coordination with the NRC and DOE. White papers covering key licensing issues have been and will continue to be submitted and necessary discussions of these key issues have begun with the NRC. Continued government support is needed to complete the Project objectives as established in the 2005 Energy Policy Act.

  4. Summary for the Next Generation Nuclear Plant Project in Review

    SciTech Connect

    L.E. Demick

    2010-08-01

    This paper reports on the major progress that the NGNP Project has made toward developing and commercializing the HTGR technology. Significant R&D progress has been made in addressing key technical issues for qualification of the HTGR fuel and graphite, codification of high temperature materials and verification and validation of design codes. Work is also progressing in heat transfer/transport design and testing and in development of the high temperature steam electrolysis hydrogen production process. A viable licensing strategy has been formulated in coordination with the NRC and DOE. White papers covering key licensing issues have been and will continue to be submitted and necessary discussions of these key issues have begun with the NRC. Continued government support is needed to complete the Project objectives as established in the 2005 Energy Policy Act.

  5. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Interim report 1 Sep 79-28 Feb 80

    SciTech Connect

    Hoagland, K.E.; Crocket, L.; Turner, R.D.

    1980-11-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Relative destructiveness and competition among the species are being analyzed. Teredo bartschi caused almost complete destruction of panels in Oyster Creek during the summer of 1979. Reproduction and settlement of this species continued into October. The native species Teredo navalis and Bankia gouldi coexist with T. bartschi in Oyster Creek. The greatest shipworm damage is in Oyster Creek. Heavy mortality occurs in all species during winter, especially in winters such as 1979-80 when the generating station is not operating. Adults of all three species can survive for at least 30 days at salinities from 5 to 45 parts per thousand by weight. They can withstand abrupt salinity changes.

  6. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, 1 March-31 May 1980

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1980-12-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. The native species Teredo navalis and Bankia gouldi coexist with the introduced T. bartschi in Oyster Creek, at the mouth of Forked River and on the coast of the bay between the two creeks. Heavy mortality occurred in all species during winter and spring when the generating station was not operating. Temperature and salinity tolerance tests begun during April and May, 1980, were not completed by the end of May because the adult shipworms proved to be very resistant to drastic changes in these physical parameters.

  7. Radiation processing project at the institute of nuclear energy research

    NASA Astrophysics Data System (ADS)

    Tsai, C. M.; Fu, Y. K.; Wang, Y. H.; Chen, Y. T.; Wei, Y. H.; Lee, K. P.; Wang, Y. K.

    The utilization of scientific approach to preserve and sterilize the agricultural products has long been studied since 1954 and was adopted by several countries gradually since 1958. Starting from July 1977 this Institute began to study the preservation of potatoes and onions with reference to sprout inhibition which is discussed and its economical aspect is evaluated. The design concept of a megacurie 60Co irradiator at this Institute is illustrated. The progress of construction work for the irradiator and the safety device in particular are reported. Current research project on the preservation of agricultural products in this Institute is presented.

  8. Evaluation of the Submerged Demineralizer System (SDS) flowsheet for decontamination of high-activity-level water at the Three Mile Island Unit 2 Nuclear Power Station

    SciTech Connect

    Campbell, D. O.; Collins, E. D.; King, L. J.; Knauer, J. B.

    1980-07-01

    This report discusses the Submerged Demineralizer System (SDS) flowsheet for decontamination of the high-activity-level water at the Three Mile Island Unit 2 Nuclear Power Station was evaluated at Oak Ridge National Laboratory in a study that included filtration tests, ion exchange column tests, and ion exchange distribution tests. The contaminated waters, the SDS flowsheet, and the experiments made are described. The experimental results were used to predict the SDS performance and to indicate potential improvements.

  9. Solid radioactive waste management facility design for managing CANDU{sup R} 600 MW nuclear generating station re-tube/refurbishment Waste Streams

    SciTech Connect

    Pontikakis, N.; Hopkins, J.; Scott, D.; Bajaj, V.; Nosella, L.

    2007-07-01

    The main design features of the re-tube canisters, waste handling equipment and waste containers designed by Atomic Energy of Canada Limited (AECL{sup R}) and implemented in support of the re-tube/refurbishment activities for Candu 600 MW nuclear generating stations are described in this paper. The re-tube/refurbishment waste characterization and the waste management principles, which form the basis of the design activities, are also briefly outlined. (authors)

  10. Fluor Hanford Nuclear Material Stabilization Project Welding Manual

    SciTech Connect

    BERKEY, J.R.

    2000-10-20

    The purpose of this section of the welding manual is to: (1) Provide a general description of the major responsibilities of the organizations involved with welding. (2) Provide general guidance concerning the application of codes related to welding. This manual contains requirements for welding for all Fluor Hanford (FH) welding operators working on the W460 Project, in the Plutonium Finishing Plant (PFP) at the U. S. Department of Energy (DOE) Hanford facilities. These procedures and any additional requirements for these joining processes can be used by all FH welding operators that are qualified. The Welding Procedure Specifications (WPS) found in this document were established from Procedure Qualification Records (PQR) qualified by FH specifically for the W460 Project. PQRs are permanent records of the initial testing and qualification program and are used to backup, and support, the WPS. The identification numbers of the supporting PQR(s) are recorded on each WPS. All PQRs are permanently stored under the supervision of the Fluor Hanford Welding Engineer (FHWE). New PQRs and WPSs will continue to be developed as necessary. The qualification of welders, welding operators and welding procedures will be performed for FH under supervision and concurrent of the FHWE. All new welding procedures to be entered in this manual or welder personnel to be added to the welder qualification database, shall be approved by the FHWE.

  11. Sorption (Kd) measurements on cinder block and grout in support of dose assessments for Zion Nuclear Station decommissioning

    SciTech Connect

    Milian L.; Sullivan T.

    2014-06-24

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with a backfill to provide structural support. Backfills under consideration include “clean” concrete demolition debris from the above grade parts of the facility, a flowable grout, cinder block construction debris and sand. A previous study (Yim, 2012) examined the sorption behavior of five nuclides (Fe-55, Co-60, Ni-63, Sr-85, and Cs-137) on concrete and local soils. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) examines the sorption behavior on cinder block and grout materials. Specifically, this study measured the distribution coefficient for four radionuclides of concern using site-groundwater and cinder block from the Zion site and a flowable grout. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the solid material that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides examined in this set of tests were Co-60, Ni-63, Sr-85, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90.

  12. Nuclear Waste Facing the Test of Time: The Case of the French Deep Geological Repository Project.

    PubMed

    Poirot-Delpech, Sophie; Raineau, Laurence

    2016-12-01

    The purpose of this article is to consider the socio-anthropological issues raised by the deep geological repository project for high-level, long-lived nuclear waste. It is based on fieldwork at a candidate site for a deep storage project in eastern France, where an underground laboratory has been studying the feasibility of the project since 1999. A project of this nature, based on the possibility of very long containment (hundreds of thousands of years, if not longer), involves a singular form of time. By linking project performance to geology's very long timescale, the project attempts "jump" in time, focusing on a far distant future, without understanding it in terms of generations. But these future generations remain measurements of time on the surface, where the issue of remembering or forgetting the repository comes to the fore. The nuclear waste geological storage project raises questions that neither politicians nor scientists, nor civil society, have ever confronted before. This project attempts to address a problem that exists on a very long timescale, which involves our responsibility toward generations in the far future.

  13. Safety Aspects of Nuclear Desalination with Innovative Systems; the EURODESAL Project

    SciTech Connect

    Alessandroni, C.; Cinotti, L.; Mini, G.; Nisan, S.

    2002-07-01

    The proposed paper reports the results of a preliminary investigation on safety impact deriving from the coupling of a desalination plant with a 600 MWe Passive Design PWR like the AP600 Nuclear Power Plant. This evaluation was performed in the frame of the EURODESAL Project of the 5. EURATOM Framework Programme. (authors)

  14. Implementation of IAEA /1/INT/054 Project in Nuclear Analytical Techniques Group of Argentina: Current State

    SciTech Connect

    Sara, Resnizky; Rita, Pla; Alba, Zaretzky

    2008-08-14

    This paper presents the implementation of the training received through the IAEA Project 'Preparation of Reference Materials and Organization of Proficiency Tests Rounds' in the Nuclear Analytical (NAT) Group of CNEA. Special emphasis is done on those activities related to the first Proficiency Test being carried out by the NAT Group.

  15. Multi-Canister overpack pressurization monitoring and control methodology for the spent nuclear fuel project

    SciTech Connect

    Pajunen, A.L., Westinghouse Hanford

    1996-07-19

    A control methodology is developed and monitoring alternatives evaluated for controlling pressurization in a Multi- Canister Overpack for the Hanford Spent Nuclear Fuel Project. Monitoring alternative evaluations include concept description, identification of uncertainties, and identification of experimental work required for implementation. A monitoring alternative is recommended and implementation requirements, risks and start up testing associated with the recommendation are discussed.

  16. Robots in PSE G's nuclear plants - experience and future projections

    SciTech Connect

    Roman, H.T. )

    1992-01-01

    Since the cleanup at Three Mile Island Unit 2 utilities have used robots, specifically teleoperated devices, to save significant human exposure, reduce plant downtime, and improve plant operations. Early work has centered on plant inspection, surveillance, and monitoring tasks, with future efforts likely to be directed toward operation and maintenance tasks. Public Service Electric Gas (PSE G) Company has been a pioneer in the application of this technology, gaining worldwide recognition for its work. PSE G's leadership role in this technology and their nationally recognized Applied Robotics Technology (ART) Facility has served as a model for the national and international utility industries. This paper very briefly explores the growth in utility robotic applications; discusses in detail PSE G's use of robotic devices; examines the role of the ART Facility in PSE G's success; and projects the potential role of robots in the power plant of the future.

  17. SUPPORT OF GULF OF MEXICO HYDRATE RESEARCH CONSORTIUM: ACTIVITIES TO SUPPORT ESTABLISHMENT OF A SEA FLOOR MONITORING STATION PROJECT

    SciTech Connect

    Paul Higley; J. Robert Woolsey; Ralph Goodman; Vernon Asper; Boris Mizaikoff; Angela Davis

    2004-03-01

    A Consortium, designed to assemble leaders in gas hydrates research, has been established at the University of Mississippi's Center for Marine Resources and Environmental Technology, CMRET. The primary objective of the group is to design and emplace a remote monitoring station on the sea floor in the northern Gulf of Mexico by the year 2005, in an area where gas hydrates are known to be present at, or just below, the sea floor. This mission necessitates assembling a station that will monitor physical and chemical parameters of the sea water and sea floor sediments on a more-or-less continuous basis over an extended period of time. Development of the station allows for the possibility of expanding its capabilities to include biological monitoring, as a means of assessing environmental health. Establishment of the Consortium has already succeeded in fulfilling the critical need to coordinate activities, avoid redundancies and communicate effectively among researchers in this relatively new research arena. Complementary expertise, both scientific and technical, has been assembled to innovate research methods and construct necessary instrumentation. As funding for this project, scheduled to commence December 1, 2002, had only been in place for less than half of the reporting period, project progress has been less than for other reporting periods. Nevertheless, significant progress has been made and several cruises are planned for the summer/fall of 2003 to test equipment, techniques and compatibility of systems. En route to reaching the primary goal of the Consortium, the establishment of a monitoring station on the sea floor, the following achievements have been made: (1) Progress on the vertical line array (VLA) of sensors: Software and hardware upgrades to the data logger for the prototype vertical line array, including enhanced programmable gains, increased sampling rates, improved surface communications, Cabling upgrade to allow installation of positioning sensors

  18. "Life without nuclear power": A nuclear plant retirement formulation model and guide based on economics. San Onofre Nuclear Generating Station case: Economic impacts and reliability considerations leading to plant retirement

    NASA Astrophysics Data System (ADS)

    Wasko, Frank

    Traditionally, electric utilities have been slow to change and very bureaucratic in nature. This culture, in and of itself, has now contributed to a high percentage of United States electric utilities operating uneconomical nuclear plants (Crooks, 2014). The economic picture behind owning and operating United States nuclear plants is less than favorable for many reasons including rising fuel, capital and operating costs (EUCG, 2012). This doctoral dissertation is specifically focused on life without nuclear power. The purpose of this dissertation is to create a model and guide that will provide electric utilities who currently operate or will operate uneconomical nuclear plants the opportunity to economically assess whether or not their nuclear plant should be retired. This economic assessment and stakeholder analysis will provide local government, academia and communities the opportunity to understand how Southern California Edison (SCE) embraced system upgrade import and "voltage support" opportunities to replace "base load" generation from San Onofre Nuclear Generating Station (SONGS) versus building new replacement generation facilities. This model and guide will help eliminate the need to build large replacement generation units as demonstrated in the SONGS case analysis. The application of The Nuclear Power Retirement Model and Guide will provide electric utilities with economic assessment parameters and an evaluation assessment progression needed to better evaluate when an uneconomical nuclear plant should be retired. It will provide electric utilities the opportunity to utilize sound policy, planning and development skill sets when making this difficult decision. There are currently 62 nuclear power plants (with 100 nuclear reactors) operating in the United States (EIA, 2014). From this group, 38 are at risk of early retirement based on the work of Cooper (2013). As demonstrated in my model, 35 of the 38 nuclear power plants qualify to move to the economic

  19. The nuclear weapons inheritance project: student-to-student dialogues and interactive peer education in disarmament activism.

    PubMed

    Buhmann, Caecilie Böck

    2007-01-01

    The Nuclear Weapons Inheritance Project is a student run and student initiated project founded in 2001 with the purpose of increasing awareness of health effects of nuclear policies and empowering university students to take action in a local and international context. The project uses dialogues to discuss nuclear disarmament with university students and a method of interactive peer education to train new trainers. The project has met more than 1500 students in nuclear weapon states in dialogue and trained about 400 students from all over the world. This article describes the methods and results of the project and discuss how the experience of the project can be used in other projects seeking to increase awareness of a topic and to initiate action on social injustice.

  20. 76 FR 16012 - STP Nuclear Operating Company, et al. South Texas Project, Units 1 and 2 Notice of Consideration...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-22

    ... COMMISSION STP Nuclear Operating Company, et al. South Texas Project, Units 1 and 2 Notice of Consideration... issued to STP Nuclear Operating Company, et al. (the licensee) for operation of the South Texas Project (STP), Units 1 and 2, located in Matagorda County, Texas. The notice is being reissued in its...

  1. Nuclear weapons at 70: reflections on the context and legacy of the Manhattan Project

    NASA Astrophysics Data System (ADS)

    Reed, B. Cameron

    2015-08-01

    August 2015 marks the 70th anniversary of the atomic bombings of Hiroshima and Nagasaki. These bombs, the products of the United States Army’s Manhattan Project, helped to end World War II and had enormous long-term effects on global political strategies by setting the stage for the Cold War and nuclear proliferation. This article explores the context and legacy of the Manhattan Project. The state of the war in the summer of 1945 is described, as are how the target cities came to be chosen, deliberations surrounding whether the bombs should be used directly or demonstrated first, and the long-term effects of the Project on individual scientists, the relationship between scientists and society, the subsequent development of nuclear arsenals around the world, and the current status of these arsenals and how they might evolve in the future.

  2. Tampa Electric Company`s Polk Power Station Integrated Gasification Combined Cycle Project

    SciTech Connect

    Jenkins, S.D.; Shafer, J.R.

    1994-12-31

    Tampa Electric Company (TEC) is in the construction phase for the new Polk Power Station, Unit {number_sign}1. This will be the first unit at a new site and will use Integrated Gasification Combined Cycle (IGCC) technology for power generation. The unit will utilize oxygen-blown entrained-flow coal gasification, along with combined cycle technology, to provide nominal net 26OMW of generation. As part of the environmental features of this process, the sulfur species in the coal will be recovered as a commercial grade sulfuric acid by-product. The sulfur will be removed from the synthesis gas utilizing a cold gas clean-up system (CGCU).

  3. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    SciTech Connect

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  4. International challenge to predict the impact of radioxenon releases from medical isotope production on a comprehensive nuclear test ban treaty sampling station

    SciTech Connect

    Eslinger, Paul W.; Bowyer, Ted W.; Achim, Pascal; Chai, Tianfeng; Deconninck, Benoit; Freeman, Katie; Generoso, Sylvia; Hayes, Philip; Heidmann, Verena; Hoffman, Ian; Kijima, Yuichi; Krysta, Monika; Malo, Alain; Maurer, Christian; Ngan, Fantine; Robins, Peter; Ross, J. Ole; Saunier, Olivier; Schlosser, Clemens; Schöppner, Michael; Schrom, Brian T.; Seibert, Petra; Stein, Ariel F.; Ungar, Kurt; Yi, Jing

    2016-06-01

    Abstract The International Monitoring System (IMS) is part of the verification regime for the Comprehensive Nuclear-Test-Ban-Treaty Organization (CTBTO). At entry-into-force, half of the 80 radionuclide stations will be able to measure concentrations of several radioactive xenon isotopes produced in nuclear explosions, and then the full network may be populated with xenon monitoring afterward (Bowyer et al., 2013). Fission-based production of 99Mo for medical purposes also releases radioxenon isotopes to the atmosphere (Saey, 2009). One of the ways to mitigate the effect of emissions from medical isotope production is the use of stack monitoring data, if it were available, so that the effect of radioactive xenon emissions could be subtracted from the effect from a presumed nuclear explosion, when detected at an IMS station location. To date, no studies have addressed the impacts the time resolution or data accuracy of stack monitoring data have on predicted concentrations at an IMS station location. Recently, participants from seven nations used atmospheric transport modeling to predict the time-history of 133Xe concentration measurements at an IMS station in Germany using stack monitoring data from a medical isotope production facility in Belgium. Participants received only stack monitoring data and used the atmospheric transport model and meteorological data of their choice. Some of the models predicted the highest measured concentrations quite well (a high composite statistical model comparison rank or a small mean square error with the measured values). The results suggest release data on a 15 min time spacing is best. The model comparison rank and ensemble analysis suggests that combining multiple models may provide more accurate predicted concentrations than any single model. Further research is needed to identify optimal methods for selecting ensemble members and those methods may depend on the specific transport problem. None of the submissions based only

  5. MIT/Draper Technology Development Partnership Project: Systems Analysis and On-Station Propulsion Subsystem Design.

    DTIC Science & Technology

    2007-11-02

    battery . These batteries work on the same principles as the primary Lithium Thionyl Chloride batteries ...ATD project. The battery being used on Draper’s ERGM project is the Eagle-Picher Industries, Inc. MAP-9233, which is a primary Lithium Thionyl ... Chloride Battery with the following characteristics: Table 19: ERGM Battery Characteristics Part No. MAP-9233 Weight (kg) 0.465 Volume (cm3)

  6. Data base on dose reduction research projects for nuclear power plants. Volume 5

    SciTech Connect

    Khan, T.A.; Yu, C.K.; Roecklein, A.K.

    1994-05-01

    This is the fifth volume in a series of reports that provide information on dose reduction research and health physics technology or nuclear power plants. The information is taken from two of several databases maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. The research section of the report covers dose reduction projects that are in the experimental or developmental phase. It includes topics such as steam generator degradation, decontamination, robotics, improvements in reactor materials, and inspection techniques. The section on health physics technology discusses dose reduction efforts that are in place or in the process of being implemented at nuclear power plants. A total of 105 new or updated projects are described. All project abstracts from this report are available to nuclear industry professionals with access to a fax machine through the ACEFAX system or a computer with a modem and the proper communications software through the ACE system. Detailed descriptions of how to access all the databases electronically are in the appendices of the report.

  7. The risk of leukaemia in young children from exposure to tritium and carbon-14 in the discharges of German nuclear power stations and in the fallout from atmospheric nuclear weapons testing.

    PubMed

    Wakeford, Richard

    2014-05-01

    Towards the end of 2007, the results were published from a case-control study (the "KiKK Study") of cancer in young children, diagnosed <5 years of age during 1980-2003 while resident near nuclear power stations in western Germany. The study found a tendency for cases of leukaemia to live closer to the nearest nuclear power station than their matched controls, producing an odds ratio that was raised to a statistically significant extent for residence within 5 km of a nuclear power station. The findings of the study received much publicity, but a detailed radiological risk assessment demonstrated that the radiation doses received by young children from discharges of radioactive material from the nuclear reactors were much lower than those received from natural background radiation and far too small to be responsible for the statistical association reported in the KiKK Study. This has led to speculation that conventional radiological risk assessments have grossly underestimated the risk of leukaemia in young children posed by exposure to man-made radionuclides, and particular attention has been drawn to the possible role of tritium and carbon-14 discharges in this supposedly severe underestimation of risk. Both (3)H and (14)C are generated naturally in the upper atmosphere, and substantial increases in these radionuclides in the environment occurred as a result of their production by atmospheric testing of nuclear weapons during the late 1950s and early 1960s. If the leukaemogenic effect of these radionuclides has been seriously underestimated to the degree necessary to explain the KiKK Study findings, then a pronounced increase in the worldwide incidence of leukaemia among young children should have followed the notably elevated exposure to (3)H and (14)C from nuclear weapons testing fallout. To investigate this hypothesis, the time series of incidence rates of leukaemia among young children <5 years of age at diagnosis has been examined from ten cancer registries

  8. General-purpose heat source project and space nuclear safety fuels program. Progress report, February 1980

    SciTech Connect

    Maraman, W.J.

    1980-05-01

    This formal monthly report covers the studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are: General-Purpose Heat Source Development and Space Nuclear Safety and Fuels. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

  9. Human factors in the management of Becon Construction Company's Heavy Oil Test Station Project. Final report

    SciTech Connect

    Maurer, D.

    1986-11-01

    In January 1986, the Becon Construction Company - an open-shop contractor based in Houston, Texas - mobilized a work force to a construction project location at the Belridge Oil Field, near Bakersfield, California. The construction craftsmen and helpers in Becon's work force were expected to improve their level of productivity as the work proceeded because of the knowledge and skills that they would acquire as a result of the repetitive nature of the work. As it was originally organized, the Becon HOTS project represented almost a pure laboratory environment in which to collect data concerning the learning effect on worker productivity as well as to statistically isolate the impact on productivity of such external factors as weather, absenteeism, turnover, and especially work methods improvement techniques and pay incentives. From the outset of the HOTS project, the project manager had established an accurate system to quantitatively measure and compare the total manhours that each crew - civil, mechanical, electrical, and prefabrication -- performed at individual HOTS construction locations. Additionally, it was initially assumed that the project manager would be relatively free to implement changes to the job site conditions involving incentive pay and work methods improvement. The subsequent effect of these changes on the productivity of separate work crews could then be evaluated in terms of measured manhours per crew per HOTS.

  10. Assessing the possible radiological impact of routine radiological discharges from proposed nuclear power stations in England and Wales.

    PubMed

    Jones, Alison; Jones, Kelly; Holmes, Sheila; Ewers, Leon; Cabianca, Tiberio

    2013-03-01

    The aim of this work is to assess the possible radiological impact on the population of the United Kingdom (UK) from new nuclear power stations proposed for up to eight sites in England and Wales. The radiological impact was measured in terms of collective dose to the UK, European and world populations from a single year's discharge integrated to 500 and 100 000 years and the annual dose to an average member of the UK population (known as the per-caput dose). The doses were calculated for two reactor types, UK EPR™ and AP1000™, using the annual expected discharges estimated by the designers of the reactors and assuming two reactors per site. In addition, typical individual doses to adults living close to the sites were calculated on the basis of continuous discharges for 60 years (the assumed lifetime of the reactors). The dose to a representative person (previously known as the critical group) was not calculated, as this has been done elsewhere. The assessments were carried out using the software program PC-CREAM 08(®) which implements the updated European Commission methodology for assessing the radiological impact of routine releases of radionuclides to the environment. The collective dose truncated to 500 years to the UK population was estimated to be 0.5 manSv assuming UK EPR reactors on all sites and 0.6 manSv assuming AP1000s on three sites with UK EPRs on the other sites. The most significant contribution to the collective dose to the UK population is due to the global circulation of carbon-14 released to the atmosphere. The annual dose to an average member of the UK population from all sites was calculated to be around 10 nSv y(-1) and would therefore contribute little to an individual's total radiation dose. All the calculated doses to a typical adult living near the sites assuming continuous discharges for 60 years were found to be below 1 μSv y(-1).

  11. 78 FR 50458 - Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-19

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee Nuclear Power Station, Pilgrim Nuclear Power Station, Request for Action AGENCY: Nuclear Regulatory...

  12. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, September-November 1981

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1982-06-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. In the fall of 1981, Teredo bartschi remained in Oyster Creek despite continuous prolonged outages of the Oyster Creek Nuclear Generating Station. It did not spread to Forked River or Waretown as it had done in other years when the effluent was present. The peak in larval production and settlement of T. bartschi occurred between September and October. Settlement of shipworms occurred on no monthly panels except those in Oyster Creek during the period of this report. Laboratory experiments revealed that T. bartschi becomes inactive at 5/sup 0/C (24/sup 0///sub 00/) and T. navalis shows signs of osmotic stress below 10/sup 0///sub 00/ at 18/sup 0/C. The shipworms in Barnegat Bay do not show a preference for settling at the mudline when the substrate is not limited.

  13. SUPERCONDUCTING LINAC UPGRADE PLAN FOR THE SECOND TARGET STATION PROJECT AT SNS

    SciTech Connect

    Kim, Sang-Ho; Doleans, Marc; Galambos, John D; Howell, Matthew P; Mammosser, John

    2015-01-01

    The beam power of the Linac for the Second Target Station (STS) at the Spallation Neutron Source (SNS) will be doubled to 2.8 MW. For the energy upgrade, seven additional cryomodules will be installed in the reserved space at the end of the linac tunnel to produce linac output energy of 1.3 GeV. The cryomodules for STS will have the same physical length but will incorporate some design changes based on the lessons learned from operational experience over the last 10 years and from the high beta spare cryomodule developed in house. The average macro-pulse beam current for the STS will be 38 mA which is about a 40 % increase from the present beam current for 1.4 MW operation. Plans for the new cryomodules and for the existing cryomodules to support higher beam current for the STS are presented in this paper.

  14. Prevented Mortality and Greenhouse Gas Emissions From Historical and Projected Nuclear Power

    NASA Technical Reports Server (NTRS)

    Kharecha, Pushker A.; Hansen, James E.

    2013-01-01

    In the aftermath of the March 2011 accident at Japan's Fukushima Daiichi nuclear power plant, the future contribution of nuclear power to the global energy supply has become somewhat uncertain. Because nuclear power is an abundant, low-carbon source of base-load power, it could make a large contribution to mitigation of global climate change and air pollution. Using historical production data, we calculate that global nuclear power has prevented an average of 1.84 million air pollution-related deaths and 64 gigatonnes of CO2-equivalent (GtCO2-eq) greenhouse gas (GHG) emissions that would have resulted from fossil fuel burning. On the basis of global projection data that take into account the effects of the Fukushima accident, we find that nuclear power could additionally prevent an average of 420 000-7.04 million deaths and 80-240 GtCO2-eq emissions due to fossil fuels by midcentury, depending on which fuel it replaces. By contrast, we assess that large-scale expansion of unconstrained natural gas use would not mitigate the climate problem and would cause far more deaths than expansion of nuclear power.

  15. Prevented mortality and greenhouse gas emissions from historical and projected nuclear power.

    PubMed

    Kharecha, Pushker A; Hansen, James E

    2013-05-07

    In the aftermath of the March 2011 accident at Japan's Fukushima Daiichi nuclear power plant, the future contribution of nuclear power to the global energy supply has become somewhat uncertain. Because nuclear power is an abundant, low-carbon source of base-load power, it could make a large contribution to mitigation of global climate change and air pollution. Using historical production data, we calculate that global nuclear power has prevented an average of 1.84 million air pollution-related deaths and 64 gigatonnes of CO2-equivalent (GtCO2-eq) greenhouse gas (GHG) emissions that would have resulted from fossil fuel burning. On the basis of global projection data that take into account the effects of the Fukushima accident, we find that nuclear power could additionally prevent an average of 420,000-7.04 million deaths and 80-240 GtCO2-eq emissions due to fossil fuels by midcentury, depending on which fuel it replaces. By contrast, we assess that large-scale expansion of unconstrained natural gas use would not mitigate the climate problem and would cause far more deaths than expansion of nuclear power.

  16. Feasibility, Design and Construction of a Small Hydroelectric Power Generation Station as a Student Design Project.

    ERIC Educational Resources Information Center

    Peterson, James N.; Hess, Herbert L.

    An undergraduate capstone engineering design project now provides hydroelectric power to a remote wilderness location. Students investigated the feasibility of designing, building, and installing a 4kW hydroelectric system to satisfy the need for electric power to support the research and teaching functions of Taylor Ranch, a university facility…

  17. Oconee Nuclear Station Unit {number_sign}2 Alloy 600 reactor vessel head CRD penetration inspection: Planning strategies and lessons learned

    SciTech Connect

    Arey, M.L. Jr.; Whitaker, D.E.

    1996-12-01

    Leakage from an Electricite de France (EdF) PWR reactor vessel head penetration at Bugey Unit {number_sign}3 was discovered during a hydrostatic test in 1991. The penetration material is Inconel 600 and is common to many other reactor vessel penetrations throughout the world. EdF has reported the cause of the leakage to be a throughwall crack resulting from Primary Water Stress Corrosion Cracking (PWSCC) as determined by metallurgical evaluation. Utilities in Sweden, Japan, Switzerland, Belgium and Spain have also completed inspections of penetrations in the reactor vessel heads. Cracking has been identified in approximately four percent of the additional EdF penetrations inspected and two percent of worldwide penetrations inspected to date. Five US nuclear plants have completed inspections of the control rod drive (CRD) penetrations with two plants finding indications. D.C. Cook and Oconee Nuclear Stations completed inspections in 1994 with each utility identifying one penetration with multiple indications. Point Beach, Palisades, and North Anna Nuclear Stations have completed penetration inspections without identifying any indications. This paper discusses the planning and preparation for the inspection of the CRD penetrations at ONS Unit {number_sign}2.

  18. Integrated Gasification Combined Cycle (IGCC) demonstration project, Polk Power Station -- Unit No. 1. Annual report, October 1993--September 1994

    SciTech Connect

    1995-05-01

    This describes the Tampa Electric Company`s Polk Power Station Unit 1 (PPS-1) Integrated Gasification Combined Cycle (IGCC) demonstration project which will use a Texaco pressurized, oxygen-blown, entrained-flow coal gasifier to convert approximately 2,300 tons per day of coal (dry basis) coupled with a combined cycle power block to produce a net 250 MW electrical power output. Coal is slurried in water, combined with 95% pure oxygen from an air separation unit, and sent to the gasifier to produce a high temperature, high pressure, medium-Btu syngas with a heat content of about 250 Btu/scf (LHV). The syngas then flows through a high temperature heat recovery unit which cools the syngas prior to its entering the cleanup systems. Molten coal ash flows from the bottom of the high temperature heat recovery unit into a water-filled quench chamber where it solidifies into a marketable slag by-product.

  19. Paralleling of two dissimilar main step-up transformers at the South Texas Project Electric Generating Station

    SciTech Connect

    Clark, L.H. ); Sinha, V.P.; Vaccaro, M.P. )

    1990-01-01

    The Main Step-up Transformers (MSTs) for each of the two units at the South Texas Project Electric Generating Station (STPEGS) consist of two parallel three phase transformer banks. As originally installed the transformers were of identical shell for design from a single manufacturer. Recently a high voltage bushing faulted to ground on one of the transformer, resulting in extensive transformer damage both internally and externally. As a result, the damaged transformer could not be repaired in place and required replacement. Since the lead time for an identical new transformer was at least one year and repair could take 6 to 8 months, a search for a compatible transformer was initiated. As a result of this search, four transformers were identified for initial analysis. Each one of these transformers was analyzed to determine which would be the most suitable for the application, from both electrical and physical aspects.

  20. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    SciTech Connect

    Saurwein, John

    2011-07-15

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  1. Improved Construction and Project Management for Future Nuclear Power Plants - Westinghouse Perspective

    SciTech Connect

    Matzie, Regis A.

    2002-07-01

    The economic competitiveness of future nuclear power plants is the key issue to the expansion of this vital technology. The challenge is greater today than it has been because of the worldwide trend of deregulation of the power market. Deregulation favors smaller investments with shorter payback times. However, the key economic parameter is the power generation cost and its competitiveness to other sources of electric generation, principally natural gas and coal. The relative competitiveness of these three fuel types today is largely dictated by the availability of domestic sources of both fuel and technology infrastructure. The competitiveness of new nuclear power plants can be improved in any power market environment first by the features of the design itself, second by the approach to construction, and finally by the project structure used to implement the plant, or more importantly, a series of plants. These three aspects form the cornerstone to a successful resurgence of new nuclear power plant construction. (author)

  2. Operation Hardtack. Project 6. 6. X-band radar determination of nuclear-cloud parameters

    SciTech Connect

    Bastian, C.W.; Robbiani, R.; Hargrave, J.

    1985-09-01

    The general objectives of this project were to make observations with weather Radar Set AN/CPS-9 in order to determine what characteristics and parameters of a nuclear detonation could be detected with X-band radar. The specific objectives were to obtain data that would lead to the determination of the following information relative to the nuclear cloud; rate of rise, rate of horizontal growth, maximum height, maximum diameter, stabilized height, fallout pattern due to the initial cloud formation, and range and azimuth versus time. As a result of this project, it was determined that the AN/CPS-9 radar is well suited for observations of surface or near-surface bursts, as would be expected from a comparison of its performance characteristics with those of other available radar sets.

  3. Resource Letter MP-3: The Manhattan Project and Related Nuclear Research

    NASA Astrophysics Data System (ADS)

    Reed, B. Cameron

    2016-10-01

    This Resource Letter is a supplement to the earlier Resource Letters MP-1 and MP-2, and provides further sources on the Manhattan Project and related research. Books, review papers, journal articles, videos, and websites are cited for the following topics: general works, technical works, biographical and autobiographical works, foreign wartime nuclear programs and related allied intelligence, the use of the bombs against Hiroshima and Nagasaki, technical papers of historical interest, postwar policy and technical developments, and educational materials. Together, these three Resource Letters describe nearly 400 sources of information on the Manhattan Project.

  4. Integrated data base report--1995: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    SciTech Connect

    1996-12-01

    The information in this report summarizes the U.S. Department of Energy (DOE) data base for inventories, projections, and characteristics of domestic spent nuclear fuel and radioactive waste. This report is updated annually to keep abreast of continual waste inventory and projection changes in both the government and commercial sectors. Baseline information is provided for DOE program planning purposes and to support DOE program decisions. Although the primary purpose of this document is to provide background information for program planning within the DOE community, it has also been found useful by state and local governments, the academic community, and some private citizens.

  5. Spent Nuclear Fuel Project technical baseline document. Fiscal year 1995: Volume 1, Baseline description

    SciTech Connect

    Womack, J.C.; Cramond, R.; Paedon, R.J.

    1995-03-13

    This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also.

  6. Vitrified hillforts as anthropogenic analogues for nuclear waste glasses - project planning and initiation

    SciTech Connect

    Sjoblom, Rolf; Weaver, Jamie L.; Peeler, David K.; Mccloy, John S.; Kruger, Albert A.; Ogenhall, E.; Hjarthner-Jolder, E.

    2016-09-27

    Nuclear waste must be deposited in such a manner that it does not cause significant impact on the environment or human health. In some cases, the integrity of the repositories will need to sustain for tens to hundreds of thousands of years. In order to ensure such containment, nuclear waste is frequently converted into a very durable glass. It is fundamentally difficult, however, to assure the validity of such containment based on short-term tests alone. To date, some anthropogenic and natural volcanic glasses have been investigated for this purpose. However, glasses produced by ancient cultures for the purpose of joining rocks in stonewalls have not yet been utilized in spite of the fact that they might offer significant insight into the long-term durability of glasses in natural environments. Therefore, a project is being initiated with the scope of obtaining samples and characterizing their environment, as well as to investigate them using a suite of advanced materials characterization techniques. It will be analysed how the hillfort glasses may have been prepared, and to what extent they have altered under in-situ conditions. The ultimate goals are to obtain a better understanding of the alteration behaviour of nuclear waste glasses and its compositional dependence, and thus to improve and validate models for nuclear waste glass corrosion. The paper deals with project planning and initiation, and also presents some early findings on fusion of amphibolite and on the process for joining the granite stones in the hillfort walls.

  7. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    SciTech Connect

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  8. Dose-projection considerations for emergency conditions at nuclear power plants

    SciTech Connect

    Stoetzel, G.A.; Ramsdell, J.V.; Poeton, R.W.; Powell, D.C.; Desrosiers, A.E.

    1983-05-01

    The purpose of this report is to review the problems and issues associated with making environmental radiation-dose projections during emergencies at nuclear power plants. The review is divided into three areas: source-term development, characterization of atmospheric dispersion and selection of appropriate dispersion models, and development of dosimetry calculations for determining thyroid dose and whole-body dose for ground-level and elevated releases. A discussion of uncertainties associated with these areas is also provided.

  9. Arroyo Mocho Boulder Removal Project: Lawrence Livermore National Laboratory Hetch Hetchy Pump Station

    SciTech Connect

    Burkholder, L; Kato, T; Van Hattem, M

    2007-06-28

    The purpose of this biological assessment is to review the proposed Arroyo Mocho Boulder Removal Project in sufficient detail to determine to what extent the proposed action may affect any of the threatened, endangered, proposed, or sensitive species and designated or proposed critical habitats listed below. In addition, the following information is provided to comply with statutory requirements to use the best scientific and commercial information available when assessing the risks posed to listed and/or proposed species and designated and/or proposed critical habitat by proposed federal actions. This biological assessment is prepared in accordance with legal requirements set forth under regulations implementing Section 7 of the Endangered Species Act (50 CFR 402; 16 U.S.C 1536 (c)). It is our desire for the Arroyo Mocho Boulder Removal Project to receive incidental take coverage for listed species and critical habitat within the greater project area by means of amending the previous formal Section 7 consultation (1-1-04-F-0086) conducted a few hundred meters downstream by Lawrence Livermore National Laboratory (LLNL) in 2002. All conservation measures, terms and conditions, and reporting requirements from the previous Biological Opinion (1-1-04-F-0086) have been adopted for this Biological Assessment and/or amendment.

  10. Evaluation of Maximum Radionuclide Groundwater Concentrations for Basement Fill Model. Zion Station Restoration Project

    SciTech Connect

    Sullivan, Terry

    2014-12-02

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant in order to establish a new water treatment plant. There is some residual radioactive particles from the plant which need to be brought down to levels so an individual who receives water from the new treatment plant does not receive a radioactive dose in excess of 25 mrem/y⁻¹. The objectives of this report are: (a) To present a simplified conceptual model for release from the buildings with residual subsurface structures that can be used to provide an upper bound on contaminant concentrations in the fill material; (b) Provide maximum water concentrations and the corresponding amount of mass sorbed to the solid fill material that could occur in each building for use in dose assessment calculations; (c) Estimate the maximum concentration in a well located outside of the fill material; and (d) Perform a sensitivity analysis of key parameters.

  11. 78 FR 46617 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-01

    ... the Containment Structure for Additional Electrical Penetration Assemblies AGENCY: Nuclear Regulatory... amendments that the application complies with the standards and requirements of the Atomic Energy Act of...

  12. Environmental radionuclide concentrations in the vicinity of the Calvert Cliffs Nuclear Power Plant and the Peach Bottom Atomic Power station: 1995

    SciTech Connect

    Jones, T.S.; Frithsen, J.B.; McLean, R.I.

    1997-02-01

    The Maryland Power Plant Research Program monitors concentrations of natural, weapons, and power plant produced radionuclides in environmental samples collected from the Chesapeake Bay in the vicinity of the Calvert Cliffs Nuclear Power Plant (CCNPP) and from the Susquehanna River-Chesapeake Bay system in the vicinity of Peach Bottom Atomic Power Station (PBAPS). The purpose of this monitoring is to determine the fate, transport, and potential effects of power plant produced radionuclides. Radionuclide concentrations in shellfish, finfish, aquatic vegetation, and sediment were measured using high-resolution gamma spectrometry. Radionuclides in environmental samples originated from natural sources, atmospheric weapons testing, and normal operations of CCNPP and PBAPS.

  13. Radiocesium distribution in the tissues of Japanese Black beef heifers fed fallout-contaminated roughage due to the Fukushima Daiichi Nuclear Power Station accident.

    PubMed

    Sasaki, Keisuke; Hayashi, Masayuki; Narita, Takumi; Motoyama, Michiyo; Oe, Mika; Ojima, Koichi; Nakajima, Ikuyo; Muroya, Susumu; Chikuni, Koichi; Aikawa, Katsuhiro; Ide, Yasuyuki; Nakanishi, Naoto; Suzuki, Nobuaki; Shioya, Shigeru; Takenaka, Akio

    2012-01-01

    This study examined the accumulation and tissue distribution of radioactive cesium nuclides in Japanese Black beef heifers raised on roughage contaminated with radioactive fallout due to the accident at the Fukushima Daiichi Nuclear Power Station on March 2011. Radiocesium feeding increased both (134)Cs and (137)Cs levels in all tissues tested. The kidney had the highest level and subcutaneous adipose had the lowest of radioactive cesium in the tissues. Different radioactive cesium levels were not found among parts of the muscles. These results indicate that radiocesium accumulated highly in the kidney and homogenously in the skeletal muscles in the heifers.

  14. THREE-YEAR RETENTION OF RADIOACTIVE CAESIUM IN THE BODY OF TEPCO WORKERS INVOLVED IN THE FUKUSHIMA DAIICHI NUCLEAR POWER STATION ACCIDENT.

    PubMed

    Nakano, T; Tani, K; Kim, E; Kurihara, O; Sakai, K; Akashi, M

    2016-09-01

    Direct measurements of seven highly exposed workers at the Tokyo Electric Power Company Fukushima Daiichi Nuclear Power Station accident have been performed continuously since June 2011. Caesium clearance in the monitored workers is in agreement with the biokinetic models proposed by the International Commission on Radiological Protection. After 500 d from the initial measurement, however, the caesium clearance slowed. It was thought to be unlikely that additional Cs intake had occurred after the initial intake, as activity in foods was kept low. And, the contribution from the detector over the chest was enhanced with time. This indicates that insoluble Cs particles were inhaled and a long metabolic rate showed.

  15. Fermilab Project X nuclear energy application: Accelerator, spallation target and transmutation technology demonstration

    SciTech Connect

    Gohar, Yousry; Johnson, David; Johnson, Todd; Mishra, Shekhar; /Fermilab

    2011-04-01

    The recent paper 'Accelerator and Target Technology for Accelerator Driven Transmutation and Energy Production' and report 'Accelerators for America's Future' have endorsed the idea that the next generation particle accelerators would enable technological breakthrough needed for nuclear energy applications, including transmutation of waste. In the Fall of 2009 Fermilab sponsored a workshop on Application of High Intensity Proton Accelerators to explore in detail the use of the Superconducting Radio Frequency (SRF) accelerator technology for Nuclear Energy Applications. High intensity Continuous Wave (CW) beam from the Superconducting Radio Frequency (SRF) Linac (Project-X) at beam energy between 1-2 GeV will provide an unprecedented experimental and demonstration facility in the United States for much needed nuclear energy Research and Development. We propose to carry out an experimental program to demonstrate the reliability of the accelerator technology, Lead-Bismuth spallation target technology and a transmutation experiment of spent nuclear fuel. We also suggest that this facility could be used for other Nuclear Energy applications.

  16. Building a Universal Nuclear Energy Density Functional (UNEDF): SciDAC-2 Project

    SciTech Connect

    Carlson, Joe; Furnstahl, Dick; Lusk, Rusty; Nazarewicz, Witek; Ng, Esmond; Thompson, Ian; Vary, James

    2012-06-30

    An understanding of the properties of atomic nuclei is crucial for a complete nuclear theory, for element formation, for properties of stars, and for present and future energy and defense applications. During the period of Dec. 1, 2006 - Jun. 30, 2012, the UNEDF collaboration carried out a comprehensive study of all nuclei based on the most accurate knowledge of the strong nuclear interaction, the most reliable theoretical approaches, the most advanced algorithms, and extensive computational resources, with a view towards scaling to the petaflop platforms and beyond. The long-term vision initiated with UNEDF is to arrive at a comprehensive, quantitative, and unified description of nuclei and their reactions, grounded in the fundamental interactions between the constituent nucleons. We seek to replace current phenomenological models of nuclear structure and reactions with a well-founded microscopic theory that delivers maximum predictive power with well-quantified uncertainties. Specifically, the mission of this project has been three-fold: first, to find an optimal energy density functional (EDF) using all our knowledge of the nucleonic Hamiltonian and basic nuclear properties; second, to apply the EDF theory and its extensions to validate the functional using all the available relevant nuclear structure and reaction data; and third, to apply the validated theory to properties of interest that cannot be measured, in particular the properties needed for reaction theory.

  17. Prognostics and health management (PHM) for astronauts: a collaboration project on the International Space Station

    NASA Astrophysics Data System (ADS)

    Popov, Alexandre; Fink, Wolfgang; Hess, Andrew

    2016-05-01

    Long-duration missions bring numerous risks that must be understood and mitigated in order to keep astronauts healthy, rather than treat a diagnosed health disorder. Having a limited medical support from mission control center on space exploration missions, crew members need a personal health-tracking tool to predict and assess his/her health risks if no preventive measures are taken. This paper refines a concept employing technologies from Prognostics and Health Management (PHM) for systems, namely real-time health monitoring and condition-based health maintenance with predictive diagnostics capabilities. Mapping particular PHM-based solutions to some Human Health and Performance (HH&P) technology candidates, namely by NASA designation, the Autonomous Medical Decision technology and the Integrated Biomedical Informatics technology, this conceptual paper emphasize key points that make the concept different from that of both current conventional medicine and telemedicine including space medicine. The primary benefit of the technologies development for the HH&P domain is the ability to successfully achieve affordable human space missions to Low Earth Orbit (LEO) and beyond. Space missions on the International Space Station (ISS) program directly contribute to the knowledge base and advancements in the HH&P domain, thanks to continued operations on the ISS, a unique human-tended test platform and the only test bed within the space environment. The concept is to be validated on the ISS, the only "test bed" on which to prepare for future manned exploration missions. The paper authors believe that early self-diagnostic coupled with autonomous identification of proper preventive responses on negative trends are critical in order to keep astronauts healthy.

  18. Crustal dynamics project data analysis, 1987. Volume 1: Fixed station VLBI geodetic results, 1979-1986

    NASA Technical Reports Server (NTRS)

    Ryan, J. W.; Ma, C.

    1987-01-01

    The Goddard VLBI group reports the results of analyzing Mark III data sets from fixed observatories through the end of 1986 and available to the Crustal Dynamics Project. All full-day data from POLARIS/IRIS are included. The mobile VLBI sites at Platteville (Colorado), Penticton (British Columbia), and Yellowknife (Northwest Territories) are also included since these occupations bear on the study of plate stability. Two large solutions, GLB121 and GLB122, were used to obtain Earth rotation parameters and baseline evolutions, respectively. Radio source positions were estimated globally while nutation offsets were estimated from each data set. The results include 25 sites and 108 baselines.

  19. Station, local, and public participation plan, Salt Repository Project Office, Deaf Smith County, Texas: Draft

    SciTech Connect

    Not Available

    1987-12-01

    The purpose of the SRPO State, Local, and Public Participation Plan is to provide an ''umbrella'' document for the ongoing and planned institutional involvement. One of the major goals is to develop project-specific outreach and participation programs based on input received from interested parties. DOE's commitment to interaction and information programs is to be demonstrated by conducting activities in an open environment, listening to and understanding the concerns of interested parties, actively involving affected parties in the program, executing faithfully the intent of Congress expressed through the NWPA, and providing equitable treatment for all affected parties. 1 fig., 2 tabs.

  20. 78 FR 6145 - Virgil C. Summer Nuclear Station, Units 2 and 3; Application and Amendment to Facility Combined...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-29

    ... proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of... interface between the nuclear island structures and the supporting soil or rock. The basemat transfers the load of nuclear island structures to the supporting soil or rock. The basemat transmits seismic...

  1. 78 FR 49551 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-14

    ...The U.S. Nuclear Regulatory Commission (NRC) is granting both an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment No. 7 to Combined Licenses (COL), NPF-91 and NPF-92. The COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation,......

  2. 78 FR 5511 - Virgil C. Summer Nuclear Station, Units 2 and 3; Application and Amendment to Facility Combined...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-25

    ... issuance of the proposed license amendment, the Commission will have made findings required by the Atomic... the nuclear island structures and the supporting soil or rock. The basemat transfers the load of nuclear island structures to the supporting soil or rock and transmits seismic motions from the...

  3. 76 FR 72007 - ZionSolutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Security...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-21

    ... Code of Federal Regulations (10 CFR) 50.82(a)(1)(i), the licensee certified to the U.S. Nuclear... effective immediately. Dated at Rockville, Maryland, this 10th day of November 2011. For the U.S. Nuclear... decontamination and dismantlement have begun. Completion of fuel transfer to the independent spent fuel...

  4. International challenge to predict the impact of radioxenon releases from medical isotope production on a comprehensive nuclear test ban treaty sampling station.

    PubMed

    Eslinger, Paul W; Bowyer, Ted W; Achim, Pascal; Chai, Tianfeng; Deconninck, Benoit; Freeman, Katie; Generoso, Sylvia; Hayes, Philip; Heidmann, Verena; Hoffman, Ian; Kijima, Yuichi; Krysta, Monika; Malo, Alain; Maurer, Christian; Ngan, Fantine; Robins, Peter; Ross, J Ole; Saunier, Olivier; Schlosser, Clemens; Schöppner, Michael; Schrom, Brian T; Seibert, Petra; Stein, Ariel F; Ungar, Kurt; Yi, Jing

    2016-06-01

    The International Monitoring System (IMS) is part of the verification regime for the Comprehensive Nuclear-Test-Ban-Treaty Organization (CTBTO). At entry-into-force, half of the 80 radionuclide stations will be able to measure concentrations of several radioactive xenon isotopes produced in nuclear explosions, and then the full network may be populated with xenon monitoring afterward. An understanding of natural and man-made radionuclide backgrounds can be used in accordance with the provisions of the treaty (such as event screening criteria in Annex 2 to the Protocol of the Treaty) for the effective implementation of the verification regime. Fission-based production of (99)Mo for medical purposes also generates nuisance radioxenon isotopes that are usually vented to the atmosphere. One of the ways to account for the effect emissions from medical isotope production has on radionuclide samples from the IMS is to use stack monitoring data, if they are available, and atmospheric transport modeling. Recently, individuals from seven nations participated in a challenge exercise that used atmospheric transport modeling to predict the time-history of (133)Xe concentration measurements at the IMS radionuclide station in Germany using stack monitoring data from a medical isotope production facility in Belgium. Participants received only stack monitoring data and used the atmospheric transport model and meteorological data of their choice. Some of the models predicted the highest measured concentrations quite well. A model comparison rank and ensemble analysis suggests that combining multiple models may provide more accurate predicted concentrations than any single model. None of the submissions based only on the stack monitoring data predicted the small measured concentrations very well. Modeling of sources by other nuclear facilities with smaller releases than medical isotope production facilities may be important in understanding how to discriminate those releases from

  5. Nuclear techniques for the on-line bulk analysis of carbon in coal-fired power stations.

    PubMed

    Sowerby, B D

    2009-09-01

    Carbon trading schemes usually require large emitters of CO(2), such as coal-fired power stations, to monitor, report and be audited on their CO(2) emissions. The emission price provides a significant additional incentive for power stations to improve efficiency. In the present paper, previous work on the bulk determination of carbon in coal is reviewed and assessed. The most favourable method is that based on neutron inelastic scattering. The potential role of on-line carbon analysers in improving boiler efficiency and in carbon accounting is discussed.

  6. Nuclear privatization

    SciTech Connect

    Jeffs, E.

    1995-11-01

    The United Kingdom government announced in May 1995 plans to privatize the country`s two nuclear generating companies, Nuclear Electric and Scottish Nuclear. Under the plan, the two companies will become operating divisions of a unified holding company, to be called British Electric, with headquarters in Scotland. Britain`s nuclear plants were left out of the initial privatization in 1989 because the government believed the financial community would be unwilling to accept the open-ended liability of decommissioning the original nine stations based on the Magnox gas-cooled reactor. Six years later, the government has found a way around this by retaining these power stations in state ownership, leaving the new nuclear company with the eight Advanced Gas-cooled Reactor (AGR) stations and the recently completed Sizewell B PWR stations. The operating Magnox stations are to be transferred to BNFL, which operates two Magnox stations of their own at Calder Hall and Chapelcross.

  7. Characterizing toxic emissions from a coal-fired power plant demonstrating the AFGD ICCT Project and a plant utilizing a dry scrubber/baghouse system: Bailly Station Units 7 and 8 and AFGD ICCT Project. Final report. Final report

    SciTech Connect

    Dismukes, E.B.

    1994-10-20

    This report describes results of assessment of the risk of emissions of hazardous air pollutants at one of the electric power stations, Bailly Station, which is also the site of a Clean Coal Technology project demonstrating the Pure Air Advanced Flue Gas Desulfurization process (wet limestone). This station represents the configuration of no NO{sub x} reduction, particulate control with electrostatic precipitators, and SO{sub 2} control with a wet scrubber. The test was conducted September 3--6, 1993. Sixteen trace metals were determined along with 5 major metals. Other inorganic substances and organic compounds were also determined.

  8. National Account Energy Alliance Final Report for the Basin Electric Project at Northern Border Pipeline Company's Compressor Station #7, North Dakota

    SciTech Connect

    Sweetzer, Richard; Leslie, Neil

    2008-02-01

    A field research test and verification project was conducted at the recovered energy generation plant at Northern Border Pipeline Company Compressor Station #7 (CS#7) near St. Anthony. Recovered energy generation plant equipment was supplied and installed by ORMAT Technologies, Inc. Basin Electric is purchasing the electricity under a purchase power agreement with an ORMAT subsidiary, which owns and operates the plant.

  9. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    SciTech Connect

    L.E. Demick

    2011-10-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  10. 78 FR 79017 - Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Physical...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-27

    ... which will have capabilities for the protection of special nuclear material at fixed sites and in... program, to include a security organization, which will have as its objective to provide high...

  11. Experience in Organization of Urgent Medical Care in Large-Scale Accident Conditions at Nuclear Power Stations

    DTIC Science & Technology

    2001-05-01

    approximately 340 Gwt) which is 17% of the worldwide electricity production level. The Chernobyl Nuclear Disaster with its long-term medico-biological...population to avoid or minimize the risk of their exposure. In October 1986, after the Chernobyl Nuclear Disaster the Federal Center of Radiation...period of their cooperation the Urgent Medical Care Department and the Rapid Response Teams visited the following sites of accidents: "* Chernobyl (a fire

  12. Low Energy Nuclear Reaction Aircraft- 2013 ARMD Seedling Fund Phase I Project

    NASA Technical Reports Server (NTRS)

    Wells, Douglas P.; McDonald, Robert; Campbell, Robbie; Chase, Adam; Daniel, Jason; Darling, Michael; Green, Clayton; MacGregor, Collin; Sudak, Peter; Sykes, Harrison; Waddington, Michael; Fredericks, William J.; Lepsch, Roger A.; Martin, John G.; Moore, Mark D.; Zawodny, Joseph M.; Felder, James L.; Snyder, Christopher A.

    2014-01-01

    This report serves as the final written documentation for the Aeronautic Research Mission Directorate (ARMD) Seedling Fund's Low Energy Nuclear Reaction (LENR) Aircraft Phase I project. The findings presented include propulsion system concepts, synergistic missions, and aircraft concepts. LENR is a form of nuclear energy that potentially has over 4,000 times the energy density of chemical energy sources. It is not expected to have any harmful emissions or radiation which makes it extremely appealing. There is a lot of interest in LENR, but there are no proven theories. This report does not explore the feasibility of LENR. Instead, it assumes that a working system is available. A design space exploration shows that LENR can enable long range and high speed missions. Six propulsion concepts, six missions, and four aircraft concepts are presented. This report also includes discussion of several issues and concerns that were uncovered during the study and potential research areas to infuse LENR aircraft into NASA's aeronautics research.

  13. The International Remote Monitoring Project: Results of the Swedish Nuclear Power Facility field trial

    SciTech Connect

    Johnson, C.S.; af Ekenstam, G.; Sallstrom, M.

    1995-07-01

    The Swedish Nuclear Power Inspectorate (SKI) and the US Department of Energy (DOE) sponsored work on a Remote Monitoring System (RMS) that was installed in August 1994 at the Barseback Works north of Malmo, Sweden. The RMS was designed to test the front end detection concept that would be used for unattended remote monitoring activities. Front end detection reduces the number of video images recorded and provides additional sensor verification of facility operations. The function of any safeguards Containment and Surveillance (C/S) system is to collect information which primarily is images that verify the operations at a nuclear facility. Barseback is ideal to test the concept of front end detection since most activities of safeguards interest is movement of spent fuel which occurs once a year. The RMS at Barseback uses a network of nodes to collect data from microwave motion detectors placed to detect the entrance and exit of spent fuel casks through a hatch. A video system using digital compression collects digital images and stores them on a hard drive and a digital optical disk. Data and images from the storage area are remotely monitored via telephone from Stockholm, Sweden and Albuquerque, NM, USA. These remote monitoring stations operated by SKI and SNL respectively, can retrieve data and images from the RMS computer at the Barseback Facility. The data and images are encrypted before transmission. This paper presents details of the RMS and test results of this approach to front end detection of safeguard activities.

  14. SUPPORT OF GULF OF MEXICO HYDRATE RESEARCH CONSORTIUM: ACTIVITIES TO SUPPORT ESTABLISHMENT OF A SEA FLOOR MONITORING STATION PROJECT

    SciTech Connect

    Paul Higley; J. Robert Woolsey; Ralph Goodman; Vernon Asper; Boris Mizaikoff; Angela Davis

    2005-08-01

    energy supply and normal functioning of the pressure compensated battery even following recharge after the first deployment, (H) Survival of the acoustic modem following both deployments though it was found to have developed a slow leak through the transducer following the second deployment due, presumably, to deployment in excess of 300m beyond its rating. (2) Progress on the Sea Floor Probe: (A) The Sea Floor Probe and its delivery system, the Multipurpose sled have been completed, (B) The probe has been modified to penetrate the <1m blanket of hemipelagic ooze at the water/sea floor interface to provide the necessary coupling of the accelerometer with the denser underlying sediments, (C) The MPS has been adapted to serve as an energy source for both p- and s-wave studies at the station as well as to deploy the horizontal line arrays and the SFP. (3) Progress on the Electromagnetic Bubble Detector and Counter: (A) Components for the prototype have been assembled, including a dedicated microcomputer to control power, readout and logging of the data, all at an acceptable speed, (B) The prototype has been constructed and preliminary data collected, (C) The construction of the field system is underway. (4) Progress on the Acoustic Systems for Monitoring Gas Hydrates: (A) Video recordings of bubbles emitted from a seep in Mississippi Canyon have been made from a submersible dive and the bubbles analyzed with respect to their size, number, and rise rate. These measurements have been used to determine the parameters to build the system capable of measuring gas escaping at the site of the monitoring station, (B) Laboratory tests performed using the project prototype have produced a conductivity data set that is being used to refine parameters of the field model. (5) Progress on the Mid-Infrared Sensor for Continuous Methane Monitoring: (A) Preliminary designs of mounting pieces for electrical components of ''sphereIR'' have been completed using AutoCAD software, (B) The

  15. Idaho Nuclear Technology and Engineering Center Newly Generated Liquid Waste Demonstration Project Feasibility Study

    SciTech Connect

    Herbst, A.K.

    2000-02-01

    A research, development, and demonstration project for the grouting of newly generated liquid waste (NGLW) at the Idaho Nuclear Technology and Engineering Center is considered feasible. NGLW is expected from process equipment waste, decontamination waste, analytical laboratory waste, fuel storage basin waste water, and high-level liquid waste evaporator condensate. The potential grouted waste would be classed as mixed low-level waste, stabilized and immobilized to meet RCRA LDR disposal in a grouting process in the CPP-604 facility, and then transported to the state.

  16. Ion Exchange Technology Development in Support of the Urine Processor Assembly Precipitation Prevention Project for the International Space Station

    NASA Technical Reports Server (NTRS)

    Mitchell, Julie L.; Broyan, James L.; Pickering, Karen D.; Adam, Niklas; Casteel, Michael; Callahan, Michael; Carrier, Chris

    2012-01-01

    In support of the Urine Processor Assembly Precipitation Prevention Project (UPA PPP), multiple technologies were explored to prevent CaSO4 2H2O (gypsum) precipitation during the on-orbit distillation process. Gypsum precipitation currently limits the water recovery rate onboard the International Space Station (ISS) to 70% versus the planned 85% target water recovery rate. Due to its ability to remove calcium cations in pretreated augmented urine (PTAU), ion exchange was selected as one of the technologies for further development by the PPP team. A total of 13 ion exchange resins were evaluated in various equilibrium and dynamic column tests with solutions of dissolved gypsum, urine ersatz, PTAU, and PTAU brine at 85% water recovery. While initial evaluations indicated that the Purolite SST60 resin had the highest calcium capacity in PTAU (0.30 meq/mL average), later tests showed that the Dowex G26 and Amberlite FPC12H resins had the highest capacity (0.5 meq/mL average). Testing at the Marshall Spaceflight Center (MSFC) integrates the ion exchange technology with a UPA ground article under flight-like pulsed flow conditions with PTAU. To date, no gypsum precipitation has taken place in any of the initial evaluations.

  17. Ion Exchange Technology Development in Support of the Urine Processor Assembly Precipitation Prevention Project for the International Space Station

    NASA Technical Reports Server (NTRS)

    Mitchell, Julie L.; Broyan, James L.; Pickering, Karen D.; Adam, Niklas; Casteel, Michael; Callaham, Michael; Carrier, Chris

    2011-01-01

    In support of the Urine Processor Assembly Precipitation Prevention Project (UPA PPP), multiple technologies were explored to prevent CaSO4 dot 2H2O (gypsum) precipitation during the on-orbit distillation process. Gypsum precipitation currently limits the water recovery rate onboard the International Space Station (ISS) to 70% versus the planned 85% target water recovery rate. Due to its advanced performance in removing calcium cations in pretreated augmented urine (PTAU), ion exchange was selected as one of the technologies for further development by the PPP team. A total of 12 ion exchange resins were evaluated in various equilibrium and dynamic column tests with solutions of dissolved gypsum, urine ersatz, PTAU, and PTAU brine at 85% water recovery. While initial evaluations indicated that the Purolite SST60 resin had the highest calcium capacity in PTAU (0.30 meq/mL average), later tests showed that the Dowex G26 and Amberlite FPC12H resins had the highest capacity (0.5 meq/mL average). Further dynamic column testing proved that G26 performance is +/- 10% of that value at flow rates of 0.45 and 0.79 Lph under continuous flow, and 10.45 Lph under pulsed flow. Testing at the Marshall Spaceflight Center (MSFC) integrates the ion exchange technology with a UPA ground article under flight-like pulsed flow conditions with PTAU. To date, no gypsum precipitation has taken place in any of the initial evaluations.

  18. The CELSS Antarctic Analog Project: an advanced life support testbed at the Amundsen-Scott South Pole Station, Antarctica.

    PubMed

    Straight, C L; Bubenheim, D L; Bates, M E; Flynn, M T

    1994-01-01

    The Controlled Ecological Life Support System (CELSS) Antarctic Analog Project (CAAP) is a joint endeavor between the National Science Foundation, Office of Polar Programs (NSF-OPP) and the National Aeronautics and Space Administration (NASA). Its fundamental objective is to develop, deploy and operate a testbed of NASA CELSS technologies and life support approaches at the Amundsen-Scott South Pole Station, located at latitude 90 degrees S, longitude 0 degrees. The goal of NASA's CELSS Program is to develop technologies and systems that will allow spacefaring scientists and explorers to carry out long duration extraterrestrial missions, leading ultimately to permanent habitation of the Solar System, without total dependence on a costly resupply system. A CELSS would do this by providing regenerated life support materials (air, food and water) and by processing "waste" materials into useful resources. This will be accomplished using biological and physical/chemical techniques in a nearly closed environmental habitation system. CELSS technologies also have great implications for application to terrestrial systems with intrinsic transferability to society at large. The CELSS Program intends to provide opportunities for the transfer of these systems and technologies outside the US Space Program, to applications within the American economy as space technology spin-offs.

  19. 76 FR 32994 - Nine Mile Point 3 Nuclear Project, LLC and Unistar Nuclear Operating Services, LLC; Combined...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-07

    ... License Application for Nine Mile Point 3 Nuclear Power Plant; Exemption 1.0 Background Nine Mile Point 3... 52, ``Licenses, Certifications, and Approvals for Nuclear Power Plants.'' This reactor is to be identified as Nine Mile Point 3 Nuclear Power Plant (NMP3NPP), and located adjacent to the current Nine...

  20. Remote sensing monitoring of thermal discharge in Daya Bay Nuclear Power Station based on HJ-1 infrared camera

    NASA Astrophysics Data System (ADS)

    Zhu, Li; Yin, Shoujing; Wu, Chuanqing; Ma, Wandong; Hou, Haiqian; Xu, Jing

    2014-11-01

    In this paper, the method of monitoring coastal areas affected by thermal discharge of nuclear plant by using remote sensing techniques was introduced. The proposed approach was demonstrated in Daya Bay nuclear plant based on HJ-B IRS data. A single channel water temperature inversion algorithm was detailed, considering the satellite zenith angle and water vapor. Moreover the reference background temperature was obtained using the average environmental temperature method. In the case study of Daya Bay nuclear plant, the spatial distribution of thermal pollution was analyzed by taking into account the influence of tidal, wind and so on. According to the findings of this study, the speed and direction of the ebb tide, is not conducive to the diffusion of thermal discharge of DNNP. The vertically thermal diffusion was limited by the shallow water depth near the outlet.

  1. Control room modernization at Finnish nuclear power plants - Two projects compared

    SciTech Connect

    Laarni, J.; Norros, L.

    2006-07-01

    The modernization of automation systems and human-machine interfaces is a current issue at both of the two nuclear power plants (i.e., Fortum's Loviisa plant and TVO's Olkiluoto plant) in Finland. Since the plants have been launched in the 1970's or 1980's, technology is in part old-fashioned and needs to be renewed. At Olkiluoto upgrades of the turbine operator systems have already been conducted; at Loviisa the first phase of the modernization project has just started. Basically, there is a question of the complete digitalization of the information streams at the two plants, and transition from a conventional hard-wired or hybrid control room to a screen-based one. The new human-machine interfaces will comprise new technology, such as PC workstations, soft control, touch screens and large-screen overall displays. The modernization of human-system interfaces is carried out in a stepwise manner at both plants. At both plants the main driver has not been the need to renew the user interfaces of the control room, but the need to upgrade the automation systems. In part because of this, there is a lack of a systematic top-down approach in which different aspects of human factors (HF) engineering are considered in relationship to higher level goals. Our aim here is to give an overview description of the control room modernization projects at the two plants and provide a preliminary evaluation of their progress to date. The projects are also compared, for example, in terms of duration, scope and phasing, and who is responsible for the realization of the project. In addition, we also compare experiences from the Finnish projects to experiences from similar projects abroad. The main part of the data used in this study is based on designers' and project members' interviews. (authors)

  2. Implementation status of the extreme light infrastructure - nuclear physics (ELI-NP) project

    NASA Astrophysics Data System (ADS)

    Gales, S.; Zamfir, N. V.

    2015-02-01

    The Project Extreme Light Infrastructure (ELI) is part of the European Strategic Forum for Research Infrastructures (ESFRI) Roadmap. ELI will be built as a network of three complementary pillars at the frontier of laser technologies. The ELI-NP pillar (NP for Nuclear Physics) is under construction near Bucharest (Romania) and will develop a scientific program using two 10 PW lasers and a Compton back-scattering high-brilliance and intense gamma beam, a marriage of laser and accelerator technology at the frontier of knowledge. In the present paper, the technical description of the facility, the present status of the project as well as the science, applications and future perspectives will be discussed.

  3. Implementation status of the extreme light infrastructure - nuclear physics (ELI-NP) project

    SciTech Connect

    Gales, S. Zamfir, N. V.

    2015-02-24

    The Project Extreme Light Infrastructure (ELI) is part of the European Strategic Forum for Research Infrastructures (ESFRI) Roadmap. ELI will be built as a network of three complementary pillars at the frontier of laser technologies. The ELI-NP pillar (NP for Nuclear Physics) is under construction near Bucharest (Romania) and will develop a scientific program using two 10 PW lasers and a Compton back-scattering high-brilliance and intense gamma beam, a marriage of laser and accelerator technology at the frontier of knowledge. In the present paper, the technical description of the facility, the present status of the project as well as the science, applications and future perspectives will be discussed.

  4. Standardization of Administered Activities in Pediatric Nuclear Medicine: A Report of the First Nuclear Medicine Global Initiative Project, Part 2-Current Standards and the Path Toward Global Standardization.

    PubMed

    Fahey, Frederic H; Bom, Henry Hee-Seung; Chiti, Arturo; Choi, Yun Young; Huang, Gang; Lassmann, Michael; Laurin, Norman; Mut, Fernando; Nuñez-Miller, Rodolfo; O'Keeffe, Darin; Pradhan, Prasanta; Scott, Andrew M; Song, Shaoli; Soni, Nischal; Uchiyama, Mayuki; Vargas, Luis

    2016-07-01

    The Nuclear Medicine Global Initiative (NMGI) was formed in 2012 and consists of 13 international organizations with direct involvement in nuclear medicine. The underlying objectives of the NMGI are to promote human health by advancing the field of nuclear medicine and molecular imaging, encourage global collaboration in education, and harmonize procedure guidelines and other policies that ultimately lead to improvements in quality and safety in the field throughout the world. For its first project, the NMGI decided to consider the issues involved in the standardization of administered activities in pediatric nuclear medicine. It was decided to divide the final report of this project into 2 parts. Part 1 was published in this journal in the spring of 2015. This article presents part 2 of the final report. It discusses current standards for administered activities in children and adolescents that have been developed by various professional organizations. It also presents an evaluation of the current practice of pediatric nuclear medicine specifically with regard to administered activities as determined by an international survey of 313 nuclear medicine clinics and centers from 29 countries. Lastly, it provides recommendations for a path toward global standardization of the administration of radiopharmaceuticals in children.

  5. 78 FR 41117 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-09

    ... Information in Tier 1 Table 3.3-1 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and Combined... to allow a departure from the certification information of Tier 1 of the generic design control... clarity and accuracy of the Tier 1 information located in Table 3.3-1, ``Definition of Wall...

  6. 78 FR 32278 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-29

    ... Information in Tier 1, Table 3.3-1 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and Combined... to allow a departure from the certification information of Tier 1 of the generic design control... County, Georgia. The amendment changes requested improve the clarity and accuracy of the Tier...

  7. 75 FR 16517 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit Nos 1, 2, and 3; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-01

    ... Background Dominion Nuclear Connecticut, Inc. (DNC or the licensee) is the holder of Facility Operating... orders. It is from two of these new requirements that DNC now seeks an exemption from the March 31, 2010... supplemented by letter dated January 12, 2010 (ADAMS Accession No. ML100131115), DNC requested an exemption...

  8. 76 FR 54260 - Dominion Nuclear Connecticut, Inc., Millstone Power Station, Unit Nos. 1, 2, and 3; Environmental...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-31

    ... Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering... issuing a finding of no significant impact. Environmental Assessment Identification of the Proposed Action...) and (d) during declarations of severe weather conditions involving tropical storm or hurricane...

  9. 77 FR 21815 - South Carolina Electric And Gas Company (Virgil C. Summer Nuclear Station Units 2 and 3); Order...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-11

    ...) authorizing operation and construction of nuclear power plants in accordance with the Atomic Energy Act of... in accordance with its statutory authority under Section 161 of the Atomic Energy Act of 1954, as... the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.202, and...

  10. Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

    SciTech Connect

    Suffield, Sarah R.; Fort, James A.; Adkins, Harold E.; Cuta, Judith M.; Collins, Brian A.; Siciliano, Edward R.

    2012-10-01

    As part of the Used Fuel Disposition Campaign of the Department of Energy (DOE), visual inspections and temperature measurements were performed on two storage modules in the Calvert Cliffs Nuclear Power Station’s Independent Spent Fuel Storage Installation (ISFSI). Detailed thermal models models were developed to obtain realistic temperature predictions for actual storage systems, in contrast to conservative and bounding design basis calculations.

  11. Technical Approach and Plan for Transitioning Spent Nuclear Fuel (SNF) Project Facilities to the Environmental Restoration Program

    SciTech Connect

    SKELLY, W.A.

    1999-10-06

    This document describes the approach and process in which the 100-K Area Facilities are to be deactivated and transitioned over to the Environmental Restoration Program after spent nuclear fuel has been removed from the K Basins. It describes the Transition Project's scope and objectives, work breakdown structure, activity planning, estimated cost, and schedule. This report will be utilized as a planning document for project management and control and to communicate details of project content and integration.

  12. Timber Mountain Precipitation Monitoring Station

    SciTech Connect

    Lyles, Brad; McCurdy, Greg; Chapman, Jenny; Miller, Julianne

    2012-01-01

    A precipitation monitoring station was placed on the west flank of Timber Mountain during the year 2010. It is located in an isolated highland area near the western border of the Nevada National Security Site (NNSS), south of Pahute Mesa. The cost of the equipment, permitting, and installation was provided by the Environmental Monitoring Systems Initiative (EMSI) project. Data collection, analysis, and maintenance of the station during fiscal year 2011 was funded by the U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office Environmental Restoration, Soils Activity. The station is located near the western headwaters of Forty Mile Wash on the Nevada Test and Training Range (NTTR). Overland flows from precipitation events that occur in the Timber Mountain high elevation area cross several of the contaminated Soils project CAU (Corrective Action Unit) sites located in the Forty Mile Wash watershed. Rain-on-snow events in the early winter and spring around Timber Mountain have contributed to several significant flow events in Forty Mile Wash. The data from the new precipitation gauge at Timber Mountain will provide important information for determining runoff response to precipitation events in this area of the NNSS. Timber Mountain is also a groundwater recharge area, and estimation of recharge from precipitation was important for the EMSI project in determining groundwater flowpaths and designing effective groundwater monitoring for Yucca Mountain. Recharge estimation additionally provides benefit to the Underground Test Area Sub-project analysis of groundwater flow direction and velocity from nuclear test areas on Pahute Mesa. Additionally, this site provides data that has been used during wild fire events and provided a singular monitoring location of the extreme precipitation events during December 2010 (see data section for more details). This letter report provides a summary of the site location, equipment, and data collected in

  13. Building a Universal Nuclear Energy Density Functional (UNEDF). SciDAC-2 Project

    SciTech Connect

    Vary, James P.; Carlson, Joe; Furnstahl, Dick; Horoi, Mihai; Lusk, Rusty; Nazarewicz, Witek; Ng, Esmond; Thompson, Ian

    2012-09-29

    An understanding of the properties of atomic nuclei is crucial for a complete nuclear theory, for element formation, for properties of stars, and for present and future energy and defense applications. During the period of Dec. 1 2006 – Jun. 30, 2012, the UNEDF collaboration carried out a comprehensive study of all nuclei, based on the most accurate knowledge of the strong nuclear interaction, the most reliable theoretical approaches, the most advanced algorithms, and extensive computational resources, with a view towards scaling to the petaflop platforms and beyond. Until recently such an undertaking was hard to imagine, and even at the present time such an ambitious endeavor would be far beyond what a single researcher or a traditional research group could carry out. The UNEDF SciDAC project has developed several key computational codes and algorithms for reaching the goal of solving the nuclear quantum many-body problem throughout the chart of nuclei. Without such developments, scientific progress would not be possible. In addition the UNEDF SciDAC successfully applied these developments to solve many forefront research problems.

  14. Automated chemical monitoring in new projects of nuclear power plant units

    NASA Astrophysics Data System (ADS)

    Lobanok, O. I.; Fedoseev, M. V.

    2013-07-01

    The development of automated chemical monitoring systems in nuclear power plant units for the past 30 years is briefly described. The modern level of facilities used to support the operation of automated chemical monitoring systems in Russia and abroad is shown. Hardware solutions suggested by the All-Russia Institute for Nuclear Power Plant Operation (which is the General Designer of automated process control systems for power units used in the AES-2006 and VVER-TOI Projects) are presented, including the structure of additional equipment for monitoring water chemistry (taking the Novovoronezh 2 nuclear power plant as an example). It is shown that the solutions proposed with respect to receiving and processing of input measurement signals and subsequent construction of standard control loops are unified in nature. Simultaneous receipt of information from different sources for ensuring that water chemistry is monitored in sufficient scope and with required promptness is one of the problems that have been solved successfully. It is pointed out that improved quality of automated chemical monitoring can be supported by organizing full engineering follow-up of the automated chemical monitoring system's equipment throughout its entire service life.

  15. Proceedings of the Flat-Plate Solar Array Project Research Forum on the Design of Flat-Plate Photovoltaic Arrays for Central Stations

    NASA Technical Reports Server (NTRS)

    1983-01-01

    The Flat Plate Solar Array Project, focuses on advancing technologies relevant to the design and construction of megawatt level central station systems. Photovoltaic modules and arrays for flat plate central station or other large scale electric power production facilities require the establishment of a technical base that resolves design issues and results in practical and cost effective configurations. Design, qualification and maintenance issues related to central station arrays derived from the engineering and operating experiences of early applications and parallel laboratory reserch activities are investigated. Technical issues are examined from the viewpoint of the utility engineer, architect/engineer and laboratory researcher. Topics on optimum source circuit designs, module insulation design for high system voltages, array safety, structural interface design, measurements, and array operation and maintenance are discussed.

  16. Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project

    SciTech Connect

    Ian McKirdy

    2011-07-01

    The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R&D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R&D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R&D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R&D activities; and proving selected design components in relevant applications.

  17. Integrated data base report--1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    SciTech Connect

    1997-12-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  18. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station: progress report June-August 1981. Quarterly progress report 1 Jun-31 Aug 81

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1982-01-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. In the summer of 1981, Teredo bartschi occurred in large numbers at one station in Oyster Creek, but did not appear in significant numbers in Forked River.

  19. Environmental radionuclide concentrations in the vicinity of the Calvert Cliffs Nuclear Power Plant and the Peach Bottom Atomic Power Station: 1996--1997. Final report

    SciTech Connect

    McLean, R.I.; Jones, T.S.

    1998-11-20

    The Maryland Power Plant Research Program monitors concentrations of natural, weapons, and power plant produced radionuclides in environmental samples collected from the Chesapeake Bay in the vicinity of the Calvert Cliffs Nuclear Power Plant (CCNPP) and from the Susquehanna River-Chesapeake Bay system in the vicinity of Peach Bottom Atomic Power Station (PBAPS). The purpose of this monitoring is to determine the fate, transport, and potential effects of power plant-produced radionuclides. This report contains a description of monitoring activities and data collected during the 1996 and 1997 calendar years. Radionuclide concentrations in shellfish, finfish, aquatic vegetation, and sediment were measured using high-resolution gamma spectrometry. Radionuclides in environmental samples originated from natural sources, historic atmospheric weapons testing, and normal operations of CCNPP and PBAPS.

  20. High Pressure Coolant Injection (HPCI) System Risk-Based Inspection Guide for Browns Ferry Nuclear Power Station

    SciTech Connect

    Wong, S.; DiBiasio, A.; Gunther, W.

    1993-09-01

    The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A System Risk-Based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3. The role of. the HPCI system in mitigating accidents is discussed in this S-RIG, along with insights on identified risk-based failure modes which could prevent proper operation of the system. The S-RIG provides a review of industry-wide operating experience, including plant-specific illustrative examples to augment the PRA and operational considerations in identifying a catalogue of basic PRA failure modes for the HPCI system. It is designed to be used as a reference for routine inspections, self-initiated safety system functional inspections (SSFIs), and the evaluation of risk significance of component failures at the nuclear power plant.

  1. SUPPORT OF GULF OF MEXICO HYDRATE RESEARCH CONSORTIUM: ACTIVITIES TO SUPPORT ESTABLISHMENT OF A SEA FLOOR MONITORING STATION PROJECT

    SciTech Connect

    Paul Higley; J. Robert Woolsey; Ralph Goodman; Vernon Asper; Boris Mizaikoff; Angela Davis

    2005-09-01

    substances has been developed and will be incorporated into an optimized ''deepSniff'' program upon completion of initial systems tests of the ''sphereIR''; Continuation of spectroscopic investigations of the highly permeable polymer, poly(trimethylsilyl)propyne (PTMSP), as a potential sensing membrane for methane have continued and will continue in the following project period.; High-pressure multireflection ATR measurements simulating deep-sea conditions for evaluating environmental impact on the sensor system and multivariate data analysis continue. (6) Progress on the Seismo-acoustic Characterization of Sea Floor Properties and Processes at the Hydrate Monitoring Station: Work has continued on developing the electronic part of the acoustic logging system designed for investigating fine-scale temporal changes in sea floor acoustic reflection responses at the Gas Hydrate Monitoring Station; The hardware has been built and extensively tested.

  2. Robust Neighborhood Preserving Projection by Nuclear/L2,1-Norm Regularization for Image Feature Extraction.

    PubMed

    Zhang, Zhao; Li, Fanzhang; Zhao, Mingbo; Zhang, Li; Yan, Shuicheng

    2017-04-01

    We propose two nuclear- and L2,1-norm regularized 2D neighborhood preserving projection (2DNPP) methods for extracting representative 2D image features. 2DNPP extracts neighborhood preserving features by minimizing a Frobenius norm-based reconstruction error that is very sensitive noise and outliers in given data. To make the distance metric more reliable and robust, and encode the neighborhood reconstruction error more accurately, we minimize the nuclear- and L2,1-norm-based reconstruction error, respectively and measure it over each image. Technically, we propose two enhanced variants of 2DNPP, nuclear-norm-based 2DNPP and sparse reconstruction-based 2DNPP. Besides, to optimize the projection for more promising feature extraction, we also add the nuclear- and sparse L2,1-norm constraints on it accordingly, where L2,1-norm ensures the projection to be sparse in rows so that discriminative features are learnt in the latent subspace and the nuclear-norm ensures the low-rank property of features by projecting data into their respective subspaces. By fully considering the neighborhood preserving power, using more reliable and robust distance metric, and imposing the low-rank or sparse constraints on projections at the same time, our methods can outperform related state-of-the-arts in a variety of simulation settings.

  3. Ecological studies of wood-boring bivalves and fouling organisms in the vicinity of the Oyster Creek Nuclear Generating Station. Final report, September 1976-December 1982

    SciTech Connect

    Hoagland, K.E.

    1983-10-01

    The species composition, distribution, and population dynamics of wood-boring bivalves were studied using wood test panels at 20 stations in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Physiological tolerances of three teredinid species were investigated in the laboratory and correlated with field values of temperature, salinity, siltation, precipitation, and plant operations. The interaction of boring and fouling organisms was examined. There is a definite correlation between the operation of the power plant and teredinid outbreaks. Increased salinity and water flow as well as temperature are responsible. After 1976, most of the damage in Oyster Creek was done by the introduced subtropical species Teredo bartschi. It can respond faster than native species to environmental change. Although Oyster Creek contributed larvae to neighboring parts of Barnegat Bay, its role as a breeding ground was limited. Some elements of the fouling community may be antagonistic to shipworm growth. Fouling was increased in both biomass and species richness in Oyster Creek when compared with creek controls, but the fouling community in Oyster Creek was less stable than that in other areas. Lower salinity limits for the teredinids were within the salinity range found in Oyster Creek but not within the range found in the control creeks. 71 references, 9 figures, 39 tables.

  4. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, June-August 1982

    SciTech Connect

    Hoagland, K.E.

    1982-12-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. Adult populations of Teredo bartschi existed in both Oyster Creek and Forked River in the summer of 1982, but the species was rare. There was no large settlement of this or any other teredinid species in Barnegat Bay. Teredo navalis was the most common species in the monthly panels. The fouling community reached its maximum yearly diversity in June-July. There was a thermal effluent causing a ..delta..T of 3 to 4/sup 0/C during most of the summer, and salinity in Oyster Creek and Forked River was similar to that of Barnegat Bay. The lack of a shipworm outbreak in 1982 may be related to the low ..delta..T in summer, plus the lack of a thermal effluent in the preceding winter-spring period.

  5. Analysis of populations of boring and fouling organisms in the vicinity of the Oyster Creek Nuclear Generating Station. Quarterly progress report No. 12, Jun-Aug 79

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1980-07-01

    The growth, distribution, and species composition of marine borers (primarily shipworms) and fouling organisms are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 18 localities. Our most recent findings covering June-August, 1979, are that at least one subtropical species of the borer family Teredinidae, Teredo bartschi, continues to live in Oyster Creek and can breed in Forked River, although many die off in winter in Forked River and the species may have to recolonize. A few of the subtropical T. furcifera also survive in Oyster Creek but cause negligible damage at present, compared with T. bartschi. The summer, 1979, outbreak of T. bartschi in Oyster Creek was severe, causing nearly total destruction to wood panels. The breeding season for T. bartschi was the same as in 1978. Some fouling organisms were present in Oyster Creek that are absent in control creek stations due to low salinity.

  6. Colorado School of Mines Low Energy Nuclear Physics Project technical progress report

    SciTech Connect

    Cecil, F.E.

    1990-01-05

    This report summarizes the activity and accomplishments of the Colorado School of Mines Low Energy Nuclear Physics project during the calendar year 1989. Many of the projects which were anticipated in the original grant proposal have been completed. Among these completed projects we include of study of the radiative capture of low energy protons on {sup 6}Li, {sup 7}Li, {sup 9}Be, and {sup 11}B. Preliminary measurements of the branching ratios and yields of these reactions were reported in last year's Technical Progress Report. These measurements are now complete and have been used to extract the respective astrophysical S-factors and the corresponding thermonuclear reactivities. While not complete, progress has been made in some of the other originally proposed studies. Among these include a fairly extensive study of the interaction of low energy deuterons with {sup 6}Li and {sup 7}Li. In the course of this study we have made a solid observation of the Oppenheimer-Phillips effect in the D-{sup 6}Li system. Progress has been made in our study of the radiative capture of alpha particles by deuterons, {sup 6}Li, and {sup 7}Li but considerable work remains in these studies. In our earlier reports we noted the observation of d-d reactions during the bombardment of deuterated targets with energetic beams of protons, alpha particles, and other light-to-medium ions. We believe we now understand this phenomenon and feel it has some fairly significant consequences both for our studies and for those of other researchers. Our susceptibility to mob hysteria led us to invest a significant effort in cold nuclear fusion, both employing a fairly unique accelerator based approach at CSM and as one of the gamma ray diagnosticians on the Princeton Plasma Physics Laboratory's Cold Fusion Task Force.

  7. Stratospheric Aerosol and Gas Experiment, SAGE III on ISS, An Earth Science Mission on the International Space Station, Schedule Risk Analysis, A Project Perspective

    NASA Technical Reports Server (NTRS)

    Bonine, Lauren

    2015-01-01

    The presentation provides insight into the schedule risk analysis process used by the Stratospheric Aerosol and Gas Experiment III on the International Space Station Project. The presentation focuses on the schedule risk analysis process highlighting the methods for identification of risk inputs, the inclusion of generic risks identified outside the traditional continuous risk management process, and the development of tailored analysis products used to improve risk informed decision making.

  8. Colorado School of Mines low energy nuclear physics project. Final technical progress report

    SciTech Connect

    Cecil, F.E.

    1993-11-23

    This report summarizes the accomplishments of the project ``Studies of nuclear reactions at very low energies``. This project was undertaken in 1987 and completed in 1993. All but one of the major objectives of this study have been accomplished. Specifically the authors have completed their investigation of the (p,{gamma}) on light nuclei, a study of the Oppenheimer-Phillips effect, a measurements of the astrophysically interesting reaction D({alpha},{gamma}){sup 6}Li at low energies and an extension of the reaction D(d,{gamma}){sup 4}He to lower energies than previously observed. Preliminary investigation of te reaction {sup 7}Li({sup 3}He,p){sup 9}Be was begun and is continuing under a separate DOE grant. In addition to these tasks, they have completed some very interesting projects which were not included in the original proposal. These include a study of the (d,{gamma}) reactions on {sup 6}Li, {sup 7}Li and {sup 10}B and an investigation of the possibility of observing terrestrial antineutrinos from the beta decay chains of U and Th as a diagnostic of terrestrial heat flow.

  9. Uranium Oxide Rate Summary for the Spent Nuclear Fuel (SNF) Project (OCRWM)

    SciTech Connect

    PAJUNEN, A.L.

    2000-09-20

    The purpose of this document is to summarize the uranium oxidation reaction rate information developed by the Hanford Spent Nuclear Fuel (SNF) Project and describe the basis for selecting reaction rate correlations used in system design. The selection basis considers the conditions of practical interest to the fuel removal processes and the reaction rate application during design studies. Since the reaction rate correlations are potentially used over a range of conditions, depending of the type of evaluation being performed, a method for transitioning between oxidation reactions is also documented. The document scope is limited to uranium oxidation reactions of primary interest to the SNF Project processes. The reactions influencing fuel removal processes, and supporting accident analyses, are: uranium-water vapor, uranium-liquid water, uranium-moist air, and uranium-dry air. The correlation selection basis will consider input from all available sources that indicate the oxidation rate of uranium fuel, including the literature data, confirmatory experimental studies, and fuel element observations. Trimble (2000) summarizes literature data and the results of laboratory scale experimental studies. This document combines the information in Trimble (2000) with larger scale reaction observations to describe uranium oxidation rate correlations applicable to conditions of interest to the SNF Project.

  10. The uptake of iron-55 by marine sediment, macroalgae, and biota following discharge from a nuclear power station.

    PubMed

    Warwick, P E; Cundy, A B; Croudace, I W; Bains, M E; Dale, A A

    2001-06-01

    Significant quantities of 55Fe, an activation product of stable iron, have been released into the environment following the atmospheric testing of nuclear weapons (mainly in the 1950s and 1960s) as well as through authorized discharges of radioactivity from nuclear power and reprocessing sites. Although some studies have been performed on the behavior of weapons' fallout-derived 55Fe in the environment and subsequent impact on humans, little has been published on the behavior of 55Fe released as a point source discharge from nuclear sites. This study presents data on the concentration and temporal variation of 55Fe in fucoid seaweeds, shellfish, crab, and lobster collected from Weymouth Bay and adjacent coastal areas, southern England. These areas have received authorized discharges of radionuclides originating from the operation of a now-decommissioned steam-generating, heavy water-type reactor at AEE Winfrith. The highest activities of 55Fe are found associated with marine sediments collected near the discharge pipeline and a rapid decline occurs away from the pipeline. This is consistent with rapid sorption of 55Fe by the sediment, and the data show there is only limited reworking and remobilization. Activities of 55Fe in biota generally decreased over time, due to a reduction in the amount of 55Fe discharged. The variation of 55Fe activity, revealed from the monthly sampling of seaweed, does not reflect the short-term fluctuations seen in the patterns of discharged 55Fe activity. Although discharges of 55Fe from AEE Winfrith exceeded other radionuclides, the radiological impact on local seafood consumers is considerably less than for other key radionuclides such as 60Co and 65Zn but of comparable magnitude to the global average population dose arising from fallout-derived 55Fe.

  11. Effect of pH on the release of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resins collected from operating nuclear power stations

    SciTech Connect

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W. )

    1991-06-01

    Data are presented on the physical stability and leachability of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small-scale waste--form specimens collected during solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station were leach-tested and subjected to compressive strength testing in accordance with the Nuclear Regulatory Commission's Technical Position on Waste Form'' (Revision 1). Samples of untreated resin waste collected from each solidification vessel before the solidification process were analyzed for concentrations of radionuclides, selected transition metals, and chelating agents to determine the quantities of these chemicals in the waste-form specimens. The chelating agents included oxalic, citric, and picolinic acids. In order to determine the effect of leachant chemical composition and pH on the stability and leachability of the waste forms, waste-form specimens were leached in various leachants. Results of this study indicate that differences in pH do not affect releases from cement-solidified decontamination ion-exchange resin waste forms, but that differences in leachant chemistry and the presence of chelating agents may affect the releases of radionuclides and chelating agents. Also, this study indicates that the cumulative releases of radionuclides and chelating agents are similar for waste- form specimens that decomposed and those that retained their general physical form. 36 refs., 60 figs., 28 tabs.

  12. Preliminary Thermal Modeling of Hi-Storm 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI

    SciTech Connect

    Cuta, Judith M.; Adkins, Harold E.

    2013-08-30

    This report fulfills the M3 milestone M3FT-13PN0810022, “Report on Inspection 1”, under Work Package FT-13PN081002. Thermal analysis is being undertaken at Pacific Northwest National Laboratory (PNNL) in support of inspections of selected storage modules at various locations around the United States, as part of the Used Fuel Disposition Campaign of the U.S. Department of Energy, Office of Nuclear Energy (DOE-NE) Fuel Cycle Research and Development. This report documents pre-inspection predictions of temperatures for four modules at the Hope Creek Nuclear Generating Station ISFSI that have been identified as candidates for inspection in late summer or early fall/winter of 2013. These are HI-STORM 100S-218 Version B modules storing BWR 8x8 fuel in MPC-68 canisters. The temperature predictions reported in this document were obtained with detailed COBRA-SFS models of these four storage systems, with the following boundary conditions and assumptions.

  13. 75 FR 8756 - South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station, Unit 1; Environmental...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-25

    ... Management System (ADAMS) Accession No. ML093490316) and RC-09-0148 (NRC ADAMS ML093480496 and ML093480497... project closeout activities for the required upgrades to the SCE&G security system, while simultaneously... National Pollution Discharge Elimination System permit are needed. No effects on the aquatic or...

  14. Spent Nuclear Fuel Project FY 1996 Multi-Year Program Plan WBS No. 1.4.1, Revision 1

    SciTech Connect

    1995-09-01

    This document describes the Spent Nuclear Fuel (SNF) Project portion of the Hanford Strategic Plan for the Hanford Reservation in Richland, Washington. The SNF Project was established to evaluate and integrate the urgent risks associated with N-reactor fuel currently stored at the Hanford site in the K Basins, and to manage the transfer and disposition of other spent nuclear fuels currently stored on the Hanford site. An evaluation of alternatives for the expedited removal of spent fuels from the K Basin area was performed. Based on this study, a Recommended Path Forward for the K Basins was developed and proposed to the U.S. DOE.

  15. Computer software design description for the Treated Effluent Disposal Facility (TEDF), Project L-045H, Operator Training Station (OTS)

    SciTech Connect

    Carter, R.L. Jr.

    1994-11-07

    The Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) is a computer-based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS).

  16. Spent Nuclear Fuel (SNF) Project Cask and MCO Helium Purge System Design Review Completion Report Project A.5 and A.6

    SciTech Connect

    ARD, K.E.

    2000-04-19

    This report documents the results of the design verification performed on the Cask and Multiple Canister Over-pack (MCO) Helium Purge System. The helium purge system is part of the Spent Nuclear Fuel (SNF) Project Cask Loadout System (CLS) at 100K area. The design verification employed the ''Independent Review Method'' in accordance with Administrative Procedure (AP) EN-6-027-01.

  17. Project: Modeling Relativistic Electrons from Nuclear Explosions in the Magnetosphere

    SciTech Connect

    Cowee, Misa; Gary, S. Peter; Winske, Dan; Liu, Kaijun

    2012-07-17

    We present a summary of the FY12 activities for DTRA-funded project 'Modeling Relativistic Electrons from Nuclear Explosions in the Magnetosphere'. We briefly review the outstanding scientific questions and discuss the work done in the last year to try to answer these questions. We then discuss the agenda for this Technical Meeting with the DTRA sponsors. In the last year, we have continued our efforts to understand artificial radiation belts from several different perspectives: (1) Continued development of Electron Source Model (ESM) and comparison to HANE test data; (2) Continued studies of relativistic electron scattering by waves in the natural radiation belts; (3) Began study of self-generated waves from the HANE electrons; and (4) Began modeling for the UCLA laser experiment.

  18. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    SciTech Connect

    IRWIN, J.J.

    2000-02-03

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  19. DoD’s Compressed Natural Gas Filling Station in Afghanistan: An Ill-conceived $43 Million Project

    DTIC Science & Technology

    2015-10-01

    the Task Force spent nearly $43 million to construct a compressed natural gas (CNG) automobile filling station in the city of Sheberghan...construction and operation of a CNG automobile filling station in the city of Sheberghan, near Afghanistan’s natural gas fields.4 Figure 1 – The pumps...Mazar-e Sharif, the second-largest city in Afghanistan (sic), with a market of 100,000 cars;5  Provide subject matter expert support to the CNG

  20. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron Activated Shield Wall

    SciTech Connect

    Michael R. Kruzic

    2007-09-16

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D&D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D&D strategy is now being employed on the larger ''sister'' facility, Test Cell C.