Science.gov

Sample records for nuclear program developing

  1. National Nuclear Forensics Expertise Development Program

    NASA Astrophysics Data System (ADS)

    Kentis, Samantha E.; Ulicny, William D.

    2009-08-01

    Over the course of the 2009 Federal Fiscal Year the United States (U.S.) Department of Homeland Security (DHS), in partnership with the Departments of Defense (DoD) and Energy (DOE), is continuing existing programs and introducing new programs designed to maintain a highly qualified, enduring workforce capable of performing the technical nuclear forensics mission. These student and university programs are designed to recruit the best and brightest students, develop university faculty and research capabilities, and engage the national laboratories in fields of study with application in nuclear forensics. This comprehensive effort constitutes the National Nuclear Forensics Expertise Development Program.

  2. Collaborative development of Estonian nuclear master's program

    SciTech Connect

    Tkaczyk, A. H.; Kikas, A.; Realo, E.; Kirm, M.; Kiisk, M.; Isakar, K.; Suursoo, S.; Koch, R.; Feldbach, E.; Lushchik, A.; Reivelt, K.

    2012-07-01

    In 2009 Estonia approved the National Development Plan for the Energy Sector, including the nuclear energy option. This can be realized by construction of a nuclear power plant (NPP) in Estonia or by participation in neighboring nuclear projects (e.g., Lithuania and/or Finland). Either option requires the availability of competent personnel. It is necessary to prepare specialists with expertise in all aspects related to nuclear infrastructure and to meet workforce needs (e.g. energy enterprises, public agencies, municipalities). Estonia's leading institutions of higher education and research with the support of the European Social Fund have announced in this context a new nuclear master's curriculum to be developed. The language of instruction will be English. (authors)

  3. NNSA Program Develops the Next Generation of Nuclear Security Experts

    SciTech Connect

    Brim, Cornelia P.; Disney, Maren V.

    2015-09-02

    NNSA is fostering the next generation of nuclear security experts is through its successful NNSA Graduate Fellowship Program (NGFP). NGFP offers its Fellows an exceptional career development opportunity through hands-on experience supporting NNSA mission areas across policy and technology disciplines. The one-year assignments give tomorrow’s leaders in global nuclear security and nonproliferation unparalleled exposure through assignments to Program Offices across NNSA.

  4. Role of nuclear power in the Philippine power development program

    SciTech Connect

    Aleta, C.R.

    1994-12-31

    The reintroduction of nuclear power in the Philippines is favored by several factors such as: the inclusion of nuclear energy in the energy sector of the science and technology agenda for national development (STAND); the Large gap between electricity demand and available local supply for the medium-term power development plan; the relatively lower health risks in nuclear power fuel cycle systems compared to the already acceptable power systems; the lower environmental impacts of nuclear power systems compared to fossil fuelled systems and the availability of a regulatory framework and trained personnel who could form a core for implementing a nuclear power program. The electricity supply gap of 9600 MW for the period 1993-2005 could be partly supplied by nuclear power. The findings of a recent study are described, as well as the issues that have to be addressed in the reintroduction of nuclear power.

  5. Nuclear power program and technology development in Korea

    SciTech Connect

    Cho, Byung-Oke

    1994-12-31

    KEPCO has successfully implemented the construction and operation of nuclear power plants since the early 1970s, and will continue to build safer and more efficient nuclear plants in the future in accordance with the nuclear power development plan previously established. KEPCO will also make every effort to enhance nuclear safety and obtain the public`s acceptance for nuclear power. We are, however, facing the same difficulties, as United States and other countries have, in strengthened regulatory requirements, public acceptance, radwaste disposal, and acquisition of new plant sites despite an active nuclear power program. Story of Ted Turner, CNN; {open_quotes}It ain`t as easy as it looks.{close_quotes} Yes! It is difficult. But we will cope with these issues so that we can promote the nuclear power development and continue to supply a highly economical and clean energy to the world. In this regard, it is my sincere wish that each organization participating in the nuclear industry, especially Korea and United States strengthen their ties and help each other so that we together can successfully accomplish our goals.

  6. DTRA's Nuclear Explosion Monitoring Research and Development Program

    NASA Astrophysics Data System (ADS)

    Nichols, J.; Dainty, A.; Phillips, J.

    2001-05-01

    The Defense Threat Reduction Agency (DTRA) has a Program in Basic Research and Development for Nuclear Explosion Technology within the Nuclear Treaties Branch of the Arms Control Technology Division. While the funding justification is Arms Control Treaties (i.e., Comprehensive Nuclear-Test-Ban Treaty, CTBT), the results are made available for any user. Funding for the Program has averaged around \\10m per year recently. By Congressional mandate, the program has disbursed money through competitive, peer-reviewed, Program Research and Development Announcements (PRDAs); there is usually (but not always) a PRDA each year. Typical awards have been for about three years at ~\\100,000 per year, currently there are over 60 contracts in place. In addition to the "typical" awards, there was an initiative 2000 to fund seismic location calibration of the International Monitoring System (IMS) of the CTBT; there are three three-year contracts of ~\\$1,000,000 per year to perform such calibration for Eurasia, and North Africa and the Middle East. Scientifically, four technological areas have been funded, corresponding to the four technologies in the IMS: seismic, infrasound, hydroacoustic, and radionuclide, with the lion's share of the funding going to the seismic area. The scientific focus of the Program for all four technologies is detection of signals, locating their origin, and trying to determine of they are unambiguously natural in origin ("event screening"). Location has been a particular and continuing focus within the Program.

  7. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

  8. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

  9. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect

    P. E. MacDonald

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

  10. The Los Alamos nuclear safeguards and nonproliferation technology development program

    SciTech Connect

    Smith, H.A. Jr.; Menlove, H.O.; Reilly, T.D.; Bosler, G.E.; Hakkila, E.A.; Eccleston, G.W.

    1994-04-01

    For nearly three decades, Los Alamos National Laboratory has developed and implemented nuclear measurement technology and training in support of national and international nuclear safeguards. This paper outlines the major elements of those technologies and highlights some of the latest developments.

  11. On the pursuit of a nuclear development capability: The case of the Cuban nuclear program

    NASA Astrophysics Data System (ADS)

    Benjamin-Alvarado, Jonathan Calvert

    1998-09-01

    While there have been many excellent descriptive accounts of modernization schemes in developing states, energy development studies based on prevalent modernization theory have been rare. Moreover, heretofore there have been very few analyses of efforts to develop a nuclear energy capability by developing states. Rarely have these analyses employed social science research methodologies. The purpose of this study was to develop a general analytical framework, based on such a methodology to analyze nuclear energy development and to utilize this framework for the study of the specific case of Cuba's decision to develop nuclear energy. The analytical framework developed focuses on a qualitative tracing of the process of Cuban policy objectives and implementation to develop a nuclear energy capability, and analyzes the policy in response to three models of modernization offered to explain the trajectory of policy development. These different approaches are the politically motivated modernization model, the economic and technological modernization model and the economic and energy security model. Each model provides distinct and functionally differentiated expectations for the path of development toward this objective. Each model provides expected behaviors to external stimuli that would result in specific policy responses. In the study, Cuba's nuclear policy responses to stimuli from domestic constraints and intensities, institutional development, and external influences are analyzed. The analysis revealed that in pursuing the nuclear energy capability, Cuba primarily responded by filtering most of the stimuli through the twin objectives of economic rationality and technological advancement. Based upon the Cuban policy responses to the domestic and international stimuli, the study concluded that the economic and technological modernization model of nuclear energy development offered a more complete explanation of the trajectory of policy development than either the

  12. Vision for the development of an international nuclear fuel recycling program

    SciTech Connect

    Kok, Kenneth D.

    2007-07-01

    The purpose of the development of an international nuclear fuel recycle program is to: - Demonstrate advanced recycling by working to prove the technologies needed to close the fuel cycle, minimize waste, and obtain more energy benefit for each unit of fuel. - Build a global vision by enlisting partners to limit the spread of sensitive nuclear technologies in a way that enables nuclear power to meet global challenges. The program will begin with the establishment of a smaller scale secure fuel cycle facility that would serve as a model for international nuclear fuel reprocessing centers that would eventually be built in several countries world wide. The operating process plants will provide the secure and safe guarded environment for the recycle of spent fuel from nuclear power stations around the world. The demonstration site will provide for developing and testing processes that would lead to the more complete use of the energy available in nuclear fuels and the minimization of long lived nuclear waste. (author)

  13. Development of Nuclear Engineering Educational Program at Ibaraki University with Regional Collaboration

    NASA Astrophysics Data System (ADS)

    Matsumura, Kunihito; Kaminaga, Fumito; Kanto, Yasuhiro; Tanaka, Nobuatsu; Saigusa, Mikio; Kikuchi, Kenji; Kurumada, Akira

    The College of Engineering, Ibaraki University is located at the Hitachi city, in the north part of Ibaraki prefecture. Hitachi and Tokai areas are well known as concentration of advanced technology center of nuclear power research organizations. By considering these regional advantages, we developed a new nuclear engineering educational program for students in the Collage of Engineering and The Graduate School of Science and Engineering of Ibaraki University. The program is consisted of the fundamental lectures of nuclear engineering and nuclear engineering experiments. In addition, several observation learning programs by visiting cooperative organizations are also included in the curriculum. In this paper, we report about the progress of the new educational program for nuclear engineering in Ibaraki University.

  14. Progress in space nuclear reactor power systems technology development - The SP-100 program

    NASA Technical Reports Server (NTRS)

    Davis, H. S.

    1984-01-01

    Activities related to the development of high-temperature compact nuclear reactors for space applications had reached a comparatively high level in the U.S. during the mid-1950s and 1960s, although only one U.S. nuclear reactor-powered spacecraft was actually launched. After 1973, very little effort was devoted to space nuclear reactor and propulsion systems. In February 1983, significant activities toward the development of the technology for space nuclear reactor power systems were resumed with the SP-100 Program. Specific SP-100 Program objectives are partly related to the determination of the potential performance limits for space nuclear power systems in 100-kWe and 1- to 100-MW electrical classes. Attention is given to potential missions and applications, regimes of possible space power applicability, safety considerations, conceptual system designs, the establishment of technical feasibility, nuclear technology, materials technology, and prospects for the future.

  15. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect

    G. O. Hayner; E.L. Shaber

    2004-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  16. Development of a nuclear test strategy for Test Program Element II

    SciTech Connect

    Deis, G.A.; Hsu, P.Y.; Liebenthal, J.L.; Longhurst, G.R.; Miller, L.G.; Schmunk, R.E.; Uldrich, E.D.; Wadkins, R.P.; Watts, K.D.

    1982-03-01

    As part of Phase O in Test Program Element II of the Office of Fusion Energy's First Wall/Blanket/Shield Engineering Test Program, a test strategy has been developed to address the blanket/shield's (B/S's) thermal-hydraulic and thermomechanical data needs, which were identified in an earlier task through the use of nuclear and supporting nonnuclear testing. In Phase I, which extends through 1984, this strategy emphasizes the development of pre-design information and the nonnuclear supporting tests. After Phase I, nuclear testing will be emphasized, and B/S design-verification testing will become more important. The proposed program will investigate a solid-breeder-blanket concept via nuclear testing. This program can begin in Phase I with nonnuclear support tests, and can progress to integrated nuclear testing soon after the completion of Phase I. The program's approximate cost and schedule are presented. In addition, other possible areas of study for Phase I, and strategies for the use of nuclear and nonnuclear facilities after Phase I are outlined.

  17. PUBLIC HEARING TRANSCRIPT: FEDERAL NON-NUCLEAR ENERGY RESEARCH AND DEVELOPMENT PROGRAM

    EPA Science Inventory

    This document presents the proceedings of three days of public hearings on the Federal Non-nuclear Energy Research and Development Program. The document is presented in three sections: (1) Future Energy Patterns and Levels of Coal Use, (2) Solar Energy and Conservation, and (3) O...

  18. Nuclear power programs in developing countries of the world: Southeast Asia

    SciTech Connect

    1995-05-01

    This article reviews the present and future status of the nuclear industry in the developing nations of China, North Korea, Thailand, Indonesia, and the Philippines. Each of the countries has a booming export-driven economy, which is turn requires considerable new generating capacity. The nuclear option is being considered as a provider of much of this additional capacity. China is committed to an extensive nuclear power program, and Indonesia has an ambitious plan to have seven to twelve reactors in service by the year 2015. North Korea will receive two LWRs to replace its current non-power nuclear units. The nuclear option is still under discussion in the Philippines and in Thailand.

  19. Functional process descriptions for the program to develop the Nuclear Waste Management System

    SciTech Connect

    Woods, T.W.

    1991-09-01

    The Office of Civilian Radioactive Waste Management (OCRWM) is executing a plan for improvement of the systems implemented to carry out its responsibilities under the Nuclear Waste Policy Act of 1982 (NWPA). As part of the plan, OCRWM is performing a systems engineering analysis of both the physical system, i.e., the Nuclear Waste Management System (NWMS), and the programmatic functions that must be accomplished to bring the physical system into being. The purpose of the program analysis is to provide a systematic identification and definition of all program functions, functional process flows, and function products necessary and sufficient to provide the physical system. The analysis resulting from this approach provides a basis for development of a comprehensive and integrated set of policies, standard practices, and procedures for the effective and efficient execution of the program. Thus, this analysis will form a basis for revising current OCRWM policies and procedures, or developing new ones is necessary. The primary purposes of this report are as follows: (1) summarizes the major functional processes and process flows that have been developed as a part of the program analysis, and (2) provide an introduction and assistance in understanding the detailed analysis information contained in the three volume report titled The Analysis of the Program to Develop the Nuclear Waste Management System (Woods 1991a).

  20. Developments in the Nuclear Safeguards and Security Engineering Degree Program at Tomsk Polytechnic University

    SciTech Connect

    Boiko, Vladimir I.; Demyanyuk, Dmitry G.; Silaev, Maxim E.; Duncan, Cristen L.; Heinberg, Cynthia L.; Killinger, Mark H.; Goodey, Kent O.; Butler, Gilbert W.

    2009-10-06

    Over the last six years, Tomsk Polytechnic University (TPU) has developed a 5½ year engineering degree program in the field of Material Protection Control and Accounting (MPC&A). In 2009 the first students graduated with this new degree. There were 25 job offers from nuclear fuel cycle enterprises of Russia and Kazakhstan for 17 graduates of the program. Due to the rather wide selection of workplaces, all graduates have obtained positions at nuclear enterprises. The program was developed within the Applied Physics and Engineering Department (APED). The laboratory and methodological base has been created taking into consideration the experience of the similar program at the Moscow Engineering Physics Institute (MEPhI). However, the TPU program has some distinguishing features such as the inclusion of special courses pertaining to fuel enrichment and reprocessing. During the last two years, three MPC&A laboratories have been established at APED. This was made possible due to several factors such as establishment of the State innovative educational program at TPU, assistance of the U.S. Department of Energy through Pacific Northwest National Laboratory and Los Alamos National Laboratory, and the financial support of the Swedish Radiation Safety Authority and some Russian private companies. All three of the MPC&A laboratories are part of the Innovative Educational Center “Nuclear Technologies and Non-Proliferation,” which deals with many topics including research activities, development of new curricula for experts training and retraining, and training of master’s students. In 2008, TPU developed a relationship with the International Atomic Energy Agency (IAEA), which was familiarized with APED’s current resources and activities. The IAEA has shown interest in creation of a master’s degree educational program in the field of nuclear security at TPU. A future objective is to acquaint nuclear fuel cycle enterprises with new APED capabilities and involve the

  1. ORNL Nuclear Safety Research and Development Program Bimonthly Report for July-August 1968

    SciTech Connect

    Cottrell, W.B.

    2001-08-17

    The accomplishments during the months of July and August in the research and development program under way at ORNL as part of the U.S. Atomic Energy Commission's Nuclear Safety Program are summarized, Included in this report are work on various chemical reactions, as well as the release, characterization, and transport of fission products in containment systems under various accident conditions and on problems associated with the removal of these fission products from gas streams. Although most of this work is in general support of water-cooled power reactor technology, including LOFT and CSE programs, the work reflects the current safety problems, such as measurements of the prompt fuel element failure phenomena and the efficacy of containment spray and pool-suppression systems for fission-product removal. Several projects are also conducted in support of the high-temperature gas-cooled reactor (HTGR). Other major projects include fuel-transport safety investigations, a series of discussion papers on various aspects of water-reactor technology, antiseismic design of nuclear facilities, and studies of primary piping and steel, pressure-vessel technology. Experimental work relative to pressure-vessel technology includes investigations of the attachment of nozzles to shells and the implementation of joint AEX-PVFX programs on heavy-section steel technology and nuclear piping, pumps, and valves. Several of the projects are directly related to another major undertaking; namely, the AEC's standards program, which entails development of engineering safeguards and the establishment of codes and standards for government-owned or -sponsored reactor facilities. Another task, CHORD-S, is concerned with the establishment of computer programs for the evaluation of reactor design data, The recent activities of the NSIC and the Nuclear Safety journal in behalf of the nuclear community are also discussed.

  2. Nuclear safeguards research and development. Program status report, October 1980-January 1981

    SciTech Connect

    Henry, C.N.

    1981-11-01

    This report presents the status of the Nuclear Safeguards Research and Development Program pursued by the Energy, Chemistry-Materials Science, and Operational Security/Safeguards Divisions of the Los Alamos National Laboratory. Topics include nondestructive assay technology development and applications, international safeguards systems. Also discussed are training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer Security Technical Center, and operational security.

  3. NIAID/NIH radiation/nuclear medical countermeasures product research and development program.

    PubMed

    Hafer, Nathaniel; Cassatt, David; Dicarlo, Andrea; Ramakrishnan, Narayani; Kaminski, Joseph; Norman, Mai-Kim; Maidment, Bert; Hatchett, Richard

    2010-06-01

    One of the greatest national security threats to the United States is the detonation of an improvised nuclear device or a radiological dispersal device in a heavily populated area. The U.S. Government has addressed these threats with a two-pronged strategy of preventing organizations from obtaining weapons of mass destruction and preparing in case an event occurs. The National Institute of Allergy and Infectious Diseases (NIAID) contributes to these preparedness efforts by supporting basic research and development for chemical, biological, radiological, and nuclear countermeasures for civilian use. The Radiation Countermeasures Program at NIAID has established a broad research agenda focused on the development of new medical products to mitigate and treat acute and long-term radiation injury, promote the clearance of internalized radionuclides, and facilitate accurate individual dose and exposure assessment. This paper reviews the recent work and collaborations supported by the Radiation Countermeasures Program. PMID:20445403

  4. The Defense Threat Reduction Agency's Technical Nuclear Forensics Research and Development Program

    NASA Astrophysics Data System (ADS)

    Franks, J.

    2015-12-01

    The Defense Threat Reduction Agency (DTRA) Technical Nuclear Forensics (TNF) Research and Development (R&D) Program's overarching goal is to design, develop, demonstrate, and transition advanced technologies and methodologies that improve the interagency operational capability to provide forensics conclusions after the detonation of a nuclear device. This goal is attained through the execution of three focus areas covering the span of the TNF process to enable strategic decision-making (attribution): Nuclear Forensic Materials Exploitation - Development of targeted technologies, methodologies and tools enabling the timely collection, analysis and interpretation of detonation materials.Prompt Nuclear Effects Exploitation - Improve ground-based capabilities to collect prompt nuclear device outputs and effects data for rapid, complementary and corroborative information.Nuclear Forensics Device Characterization - Development of a validated and verified capability to reverse model a nuclear device with high confidence from observables (e.g., prompt diagnostics, sample analysis, etc.) seen after an attack. This presentation will outline DTRA's TNF R&D strategy and current investments, with efforts focusing on: (1) introducing new technical data collection capabilities (e.g., ground-based prompt diagnostics sensor systems; innovative debris collection and analysis); (2) developing new TNF process paradigms and concepts of operations to decrease timelines and uncertainties, and increase results confidence; (3) enhanced validation and verification (V&V) of capabilities through technology evaluations and demonstrations; and (4) updated weapon output predictions to account for the modern threat environment. A key challenge to expanding these efforts to a global capability is the need for increased post-detonation TNF international cooperation, collaboration and peer reviews.

  5. Commercial nuclear waste research and development program. Quarterly report, January-March 1982

    SciTech Connect

    Hakl, A.R.

    1982-04-01

    The Westinghouse Advanced Energy Systems Division Nevada Operations, under contract to the US Department of Energy, provides trained personnel and services at the E-MAD Facility required for nuclear materials handling, packaging, data gathering, and other related activities in support of the Commercial Nuclear Waste Research and Development Programs. Support is provided to research programs, including: Waste packaging experiments, spent fuel test - Climax (SFT-C), Hanford Near Surface Test Facility (NSTF), Tests of spent reactor fuel interim handling and storage, tests to assess safety of transport systems for spent reactor fuel and solidified high level nuclear waste, and other special waste package development and handling tests as requested by the DOE. Activities reported have been performed to meet subtask objectives of the Nevada Nuclear Waste Storage Investigations (NNWSI) planning documentation for Fiscal Year 1982: Preliminary facility designs, process flow charts, and recommendations for equipment and services which would be required in a Generic Packaging Facility (GPF) co-located with the proposed Test and Evaluation Facility (TEF); E-MAD facility descriptions, logic diagrams, and process flow charts for E-MAD packaging of nuclear waste for the proposed TEF, if the TEF were not located on the Nevada Test Site; Preliminary cost estimates and schedules for a proposed large scale fuel storage demonstration, as requested by DOE/Headquarters; a remote source integrity check of the Cobalt 60 source; calibration and recertification of the Astro Arc automatic welding system. Installation of illustrated alarm panel for the E-MAD Remote Area Monitor (RAM) system in the E-MAD gatehouse; and installation of the RAM/CAM (Constant Air Monitoring) system computer interface hardware.

  6. Development of a Reliability Program approach to assuring operational nuclear safety

    SciTech Connect

    Mueller, C.J.; Bezella, W.A.

    1985-01-01

    A Reliability Program (RP) model based on proven reliability techniques used in other high technology industries is being formulated for potential application in the nuclear power industry. Research findings are discussed. The reliability methods employed under NASA and military direction, commercial airline and related FAA programs were surveyed with several reliability concepts (e.g., quantitative reliability goals, reliability centered maintenance) appearing to be directly transferable. Other tasks in the RP development effort involved the benchmarking and evaluation of the existing nuclear regulations and practices relevant to safety/reliability integration. A review of current risk-dominant issues was also conducted using results from existing probabilistic risk assessment studies. The ongoing RP development tasks have concentrated on defining a RP for the operating phase of a nuclear plant's lifecycle. The RP approach incorporates safety systems risk/reliability analysis and performance monitoring activities with dedicated tasks that integrate these activities with operating, surveillance, and maintenance of the plant. The detection, root-cause evaluation and before-the-fact correction of incipient or actual systems failures as a mechanism for maintaining plant safety is a major objective of the RP.

  7. Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4

    SciTech Connect

    G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

    2007-09-01

    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 electricity and hydrogen production. It will have an outlet gas temperature in the range of 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Some of the general and administrative aspects of the R&D Plan include: • Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R&D Program. • Define and develop inspection needs and the procedures for those inspections. • Support selected university materials related R&D activities that would be of direct benefit to the NGNP Project. • Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M&C) Project Management Board (PMB). • Support document review activities through the Materials Review Committee (MRC) or other suitable forum.

  8. Development and Implementation of a Comprehensive Program to Deal with Canada's Nuclear Legacy Liabilities

    SciTech Connect

    Brown, Peter; Metcalfe, Douglas; Blanchette, Marcia; Dolinar, George; Halpenny, Steven; Purdy, Chris; Smith, David; Kupferschmidt, William

    2008-01-15

    The Government of Canada nuclear legacy liabilities have resulted from 60 years of nuclear research and development (R and D) carried out on behalf of Canada by the National Research Council (1944 to 1952) and Atomic Energy of Canada Limited (AECL, 1952 to present). These liabilities are largely located at AECL research sites, and consist of shutdown research buildings (including several prototype and research reactors), a wide variety of buried and stored wastes, and contaminated lands. The shutdown buildings and contaminated lands need to be safely decommissioned to meet federal regulatory requirements, and long-term solutions need to be developed and implemented for management of the wastes. More than half of the liabilities are the result of Cold War activities during the 1940's, 50's and early 60's. The remaining liabilities stem from R and D for medical isotopes and nuclear reactor technology, as well as national science programs. About 70 percent of the liabilities are located at AECL's Chalk River Laboratories (CRL) in Ontario, and a further 20 percent are located at AECL's shutdown Whiteshell Laboratories in Manitoba. The remaining 10 percent relate largely to three shutdown prototype reactors in Ontario and Quebec, which were key to the developmental stage of Canada's CANDU reactor technology. The inventory of legacy waste includes spent fuel, high-level, intermediate-level and low-level solid and liquid radioactive waste, and wastes (largely contaminated soils) from site clean-up work across Canada. Most of the wastes are in raw, unconditioned form, and limited characterization information is available for the wastes generated in past decades. In many cases unique and potentially costly solutions will be required to recover, handle and process the wastes. In conclusion: the Government of Canada has initiated a program to deal with nuclear legacy liabilities dating back to the Cold War and the birth of nuclear technologies and medicine in Canada. The 5

  9. Next Generation Nuclear Plant Methods Research and Development Technical Program Plan -- PLN-2498

    SciTech Connect

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2008-09-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  10. Nuclear Technology Programs

    SciTech Connect

    Harmon, J.E.

    1990-10-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  11. Iraqi nuclear weapons development program. Final report, October 1, 1992--September 30, 1993

    SciTech Connect

    Not Available

    1993-09-30

    This is an abstract of the final report focusing on the collection, collation, analysis, and recording of information pertaining to Iraqi nuclear weapons development and on the long term monitoring of Iraq.

  12. Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, April 1, 1979-June 30, 1979

    SciTech Connect

    Not Available

    1980-01-25

    The results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented. In addition, the progress in the screening test program is described.

  13. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980

    SciTech Connect

    Not Available

    1980-06-25

    Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.

  14. Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1979-September 30, 1979

    SciTech Connect

    Not Available

    1980-03-07

    The results of work performed from July 1, 1979 through September 30, 1979 on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented. In addition, the progress in the screening test program is described.

  15. Program Development

    SciTech Connect

    Atencio, Julian J.

    2014-05-01

    This presentation covers how to go about developing a human reliability program. In particular, it touches on conceptual thinking, raising awareness in an organization, the actions that go into developing a plan. It emphasizes evaluating all positions, eliminating positions from the pool due to mitigating factors, and keeping the process transparent. It lists components of the process and objectives in process development. It also touches on the role of leadership and the necessity for audit.

  16. Graduate Research Assistant Program for Professional Development at Oak Ridge National Laboratory (ORNL) Global Nuclear Security Technology Division (GNSTD)

    SciTech Connect

    Eipeldauer, Mary D; Shelander Jr, Bruce R

    2012-01-01

    The southeast is a highly suitable environment for establishing a series of nuclear safety, security and safeguards 'professional development' courses. Oak Ridge National Laboratory (ORNL) provides expertise in the research component of these subjects while the Y-12 Nuclear Security Complex handles safeguards/security and safety applications. Several universities (i.e., University of Tennessee, Knoxville (UTK), North Carolina State University, University of Michigan, and Georgia Technology Institute) in the region, which offer nuclear engineering and public policy administration programs, and the Howard Baker Center for Public Policy make this an ideal environment for learning. More recently, the Institute for Nuclear Security (INS) was established between ORNL, Y-12, UTK and Oak Ridge Associate Universities (ORAU), with a focus on five principal areas. These areas include policy, law, and diplomacy; education and training; science and technology; operational and intelligence capability building; and real-world missions and applications. This is a new approach that includes professional development within the graduate research assistant program addressing global needs in nuclear security, safety and safeguards.

  17. Nuclear thermal propulsion program overview

    NASA Technical Reports Server (NTRS)

    Bennett, Gary L.

    1991-01-01

    Nuclear thermal propulsion program is described. The following subject areas are covered: lunar and Mars missions; national space policy; international cooperation in space exploration; propulsion technology; nuclear rocket program; and budgeting.

  18. Technical Review of the Domestic Nuclear Detection Office Transformational and Applied Research Directorate’s Research and Development Program

    SciTech Connect

    Lavietes, Anthony; Trebes, James; Borchers, Robert; Dahlburg, Jill; Donnelly, John; Isles, Adam; Johnson, Neil; Knoll, Glenn; Kouzes, Richard T.; Lanza, Richard; Lieberman, Jodi; Lund, James; Prussin, Stanley G.; Russo, Jeanette; Slakey, Francis

    2013-01-01

    At the request of the Domestic Nuclear Detection Office (DNDO), a Review Committee comprised of representatives from the American Physical Society (APS) Panel on Public Affairs (POPA) and the Institute of Electrical and Electronics Engineers (IEEE) Nuclear and Plasma Sciences Society (NPSS) performed a technical review of the DNDO Transformational and Applied Research Directorate (TARD) research and development program. TARD’s principal objective is to address gaps in the Global Nuclear Detection Architecture (GNDA) through improvements in the performance, cost, and operational burden of detectors and systems. The charge to the Review Committee was to investigate the existing TARD research and development plan and portfolio, recommend changes to the existing plan, and recommend possible new R&D areas and opportunities. The Review Committee has several recommendations.

  19. Results in Developing an Engineering Degree Program in Safeguards and Security of Nuclear Materials at Moscow Engineering Physics Institute

    SciTech Connect

    Kryuchkov, Eduard F.; Geraskin, Nikolay I.; Killinger, Mark H.; Goodey, Kent O.; Butler, Gilbert W.; Duncan, Cristen L.

    2007-07-01

    The world’s first master’s degree program in nuclear safeguards and security, established at Moscow Engineering Physics Institute (MEPhI), has now graduated nine classes of students. Most of the graduates have gone on to work at government agencies, research organizations, or obtain their PhD. In order to meet the demand for safeguards and security specialists at nuclear facilities, MEPhI established a 5½ year engineering degree program that provides more hands-on training desired by facilities. In February 2004, the first students began their studies in the new discipline Nuclear Material Safeguards and Nonproliferation. This class, as well as other subsequent classes, included students who started the program in their third year of studies, as the first 2½ years consists of general engineering curriculum. Fourteen students made up the first graduating class, receiving their engineering degrees in February 2007. The topics addressed in this paper include specific features of the program caused by peculiarities of Russian education legislation and government quality control of academic education. This paper summarizes the main joint actions undertaken by MEPhI and the US National Laboratories in conjunction with the U.S. Department of Energy, to develop the engineering degree program. Also discussed are the program’s specific training requirements, student internships, and job placement. The paper concludes with recommendations from a recent international seminar on nonproliferation education and training.

  20. Commercial nuclear waste research and development program. Quarterly report, October-December 1981

    SciTech Connect

    Hakl, A.R.

    1982-01-01

    This document is a report of activities performed by AESD-Nevada Operations in meeting task objectives of the Nevada Nuclear Waste Storage Investigations (NNWSI) planning documentation for Fiscal Year (FY) 1982. Significant activities were: Completion of a fuel assembly exchange was successfully in support of the Spent Fuel Test-Climax (SFT-C) Program; input was provided, in response to FY 1982 guidance, to DOE/NV and the Office of Nuclear Waste Isolation (ONWI) for a proposed co-located Generic Packaging Facility (GPF); in response to FY 1982 guidance, drafts were prepared of facility layouts, material and process flow charts, equipment requirements, costs, and schedules for packaging (at E-MAD) of 28 alternative configurations of defense high-level waste, disassembled spent fuel, and commercial high-level waste in support of a proposed Test and Evaluation Facility (TEF); and quarterly dry run operations for canister emplacement in a drywell and in the Hot Bay Transfer Pit using the Emplacement/Installation Vehicle (EIV).

  1. Nuclear gas core propulsion research program

    NASA Technical Reports Server (NTRS)

    Diaz, Nils J.; Dugan, Edward T.; Anghaie, Samim

    1993-01-01

    Viewgraphs on the nuclear gas core propulsion research program are presented. The objectives of this research are to develop models and experiments, systems, and fuel elements for advanced nuclear thermal propulsion rockets. The fuel elements under investigation are suitable for gas/vapor and multiphase fuel reactors. Topics covered include advanced nuclear propulsion studies, nuclear vapor thermal rocket (NVTR) studies, and ultrahigh temperature nuclear fuels and materials studies.

  2. Enterprise SRS: Leveraging Ongoing Operations To Advance Nuclear Fuel Cycles Research And Development Programs

    SciTech Connect

    Murray, Alice M.; Marra, John E.; Wilmarth, William R.; Mcguire, Patrick W.; Wheeler, Vickie B.

    2013-07-03

    The Savannah River Site (SRS) is repurposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for ''all things nuclear'' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The Department of Energy, Savannah River Operations Office, Savannah River Nuclear Solutions, the Savannah River National Laboratory (SRNL) have established a center for applied nuclear materials processing and engineering research (hereafter referred to as the Center). The key proposition of this initiative is to bridge the gap between promising transformational nuclear fuel cycle processing discoveries and large commercial-scale-technology deployment by leveraging SRS assets as facilities for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. The Center will coordinate the demonstration of R&D technologies and serve as the interface between the engineering-scale demonstration and the R&D programs, essentially providing cradle-to-grave support to the research team during the demonstration. While the initial focus of the Center will be on the effective use of SRS assets for these demonstrations, the Center also will work with research teams to identify opportunities to perform research demonstrations at other facilities. Unique to this approach is the fact that these SRS

  3. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    SciTech Connect

    1982-07-01

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

  4. Establishing nuclear facility drill programs

    SciTech Connect

    1996-03-01

    The purpose of DOE Handbook, Establishing Nuclear Facility Drill Programs, is to provide DOE contractor organizations with guidance for development or modification of drill programs that both train on and evaluate facility training and procedures dealing with a variety of abnormal and emergency operating situations likely to occur at a facility. The handbook focuses on conducting drills as part of a training and qualification program (typically within a single facility), and is not intended to included responses of personnel beyond the site boundary, e.g. Local or State Emergency Management, Law Enforcement, etc. Each facility is expected to develop its own facility specific scenarios, and should not limit them to equipment failures but should include personnel injuries and other likely events. A well-developed and consistently administered drill program can effectively provide training and evaluation of facility operating personnel in controlling abnormal and emergency operating situations. To ensure the drills are meeting their intended purpose they should have evaluation criteria for evaluating the knowledge and skills of the facility operating personnel. Training and evaluation of staff skills and knowledge such as component and system interrelationship, reasoning and judgment, team interactions, and communications can be accomplished with drills. The appendices to this Handbook contain both models and additional guidance for establishing drill programs at the Department`s nuclear facilities.

  5. Metal matrix integrity and related technology development in the Canadian Nuclear Fuel Waste Management Program

    SciTech Connect

    Mathew, P.M.; Krueger, P.A.

    1984-01-01

    One of the concepts under development as a nuclear fuel waste isolation container is a thin-wall corrosion-resistant shell, supported internally by a cast metal matrix in which intact used fuel bundles are investigated. The integrity of the metal matrix can be influenced by metallurgical factors and by process parameters. Finite element solidification modelling and laboratory experiments with lead as an investment material have shown the influence of heat transfer parameters on matrix integrity. Controlled cooling of the container walls, for example, can be used to reduce the interaction time between the molten matrix, the fuel sheathing and the container wall, and achieve a void-free matrix. The results of the computer simulations have been used to design an improved casting system, based on controlled wall cooling, for investing nuclear fuel waste containers. Ultrasonic testing of bonds between some candidate container and metal matrix materials, in combination with the metallurgical characterization of the interface region, has allowed differentiation between bonded and unbonded regions. Matrix cracking near bonded interfaces was identified as a potential problem, which could limit the use of the ultrasonic scanning technique for matrix inspection. To produce a high quality interface with good chemical bonding, induction skin melting looks promising and is being further evaluated.

  6. Nuclear weapons test detection: Ensuring a verifiable treaty. Comprehensive Test Ban Treaty research and development program 1995 progress report

    SciTech Connect

    1995-12-31

    The US Department of Energy (DOE) has an active program to provide technologies for monitoring and verifying a Comprehensive Test Ban Treaty (CTBT). DOE technologies will significantly increase the nation`s capability to identify potential nuclear explosions with high confidence and with minimal false alarms. This report presents the highlights of the first year of this program. The primary objectives of the CTBT monitoring system are to deter nuclear explosions in all environments (underground, underwater, or in the atmosphere) and, if such an explosion does occur, to detect, locate, and identify its source. The system is designed to provide credible evidence to national authorities to aid in resolving ambiguities and to serve as the basis for appropriate action. To collect this evidence, one must develop technologies that can detect and identify the signals from a nuclear test against a background of hundreds of thousands of benign events. The monitoring system must have high sensitivity to detect the events of interest and, to minimize false alarms, it must identify those events with a high level of confidence.

  7. Enterprise SRS: leveraging ongoing operations to advance nuclear fuel cycles research and development programs

    SciTech Connect

    Murray, A.M.; Marra, J.E.; Wilmarth, W.R.; McGuire, P.W.; Wheeler, V.B.

    2013-07-01

    The Savannah River Site (SRS) is re-purposing its vast array of assets (including H Canyon - a nuclear chemical separation plant) to solve issues regarding advanced nuclear fuel cycle technologies, nuclear materials processing, packaging, storage and disposition. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for 'all things nuclear' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into SRS facilities but also in other facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, a center for applied nuclear materials processing and engineering research has been established in SRS.

  8. Overview of DOE space nuclear propulsion programs

    NASA Technical Reports Server (NTRS)

    Newhouse, Alan R.

    1993-01-01

    An overview of Department of Energy space nuclear propulsion programs is presented in outline and graphic form. DOE's role in the development and safety assurance of space nuclear propulsion is addressed. Testing issues and facilities are discussed along with development needs and recent research activities.

  9. Annual Report Nucelar Energy Research and Development Program Nuclear Energy Research Initiative

    SciTech Connect

    Hively, LM

    2003-02-13

    NERI Project No.2000-0109 began in August 2000 and has three tasks. The first project year addressed Task 1, namely development of nonlinear prognostication for critical equipment in nuclear power facilities. That work is described in the first year's annual report (ORNLTM-2001/195). The current (second) project year (FY02) addresses Task 2, while the third project year will address Tasks 2-3. This report describes the work for the second project year, spanning August 2001 through August 2002, including status of the tasks, issues and concerns, cost performance, and status summary of tasks. The objective of the second project year's work is a compelling demonstration of the nonlinear prognostication algorithm using much more data. The guidance from Dr. Madeline Feltus (DOE/NE-20) is that it would be preferable to show forewarning of failure for different kinds of nuclear-grade equipment, as opposed to many different failure modes from one piece of equipment. Long-term monitoring of operational utility equipment is possible in principle, but is not practically feasible for the following reason. Time and funding constraints for this project do not allow us to monitor the many machines (thousands) that will be necessary to obtain even a few failure sequences, due to low failure rates (<10{sup -3}/year) in the operational environment. Moreover, the ONLY way to guarantee a controlled failure sequence is to seed progressively larger faults in the equipment or to overload the equipment for accelerated tests. Both of these approaches are infeasible for operational utility machinery, but are straight-forward in a test environment. Our subcontractor has provided such test sequences. Thus, we have revised Tasks 2.1-2.4 to analyze archival test data from such tests. The second phase of our work involves validation of the nonlinear prognostication over the second and third years of the proposed work. Recognizing the inherent limitations outlined in the previous paragraph, Dr

  10. Nuclear safeguards research and development

    NASA Astrophysics Data System (ADS)

    Henry, C. N.

    1981-11-01

    The status of a nuclear safeguard research and development program is presented. Topics include nondestructive assay technology development and applications, international safeguards, training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer Security Technical Center, and operational security.

  11. Developments in Neutron Spectrometry and Dosimetry in Support of the U.K. Naval Nuclear Propulsion Program

    SciTech Connect

    P. A. Beeley; N. M. Spyrou; J. M. Brushwood; A. M. Williams

    2000-11-12

    The Defence Radiological Protection Service (DRPS) is tasked with providing the approved dosimetry service to the Naval Nuclear Propulsion Program (NNPP). Within this requirement, DRPS operates a track-etch system for whole-body neutron dosimetry, using the well-known material polyally dyglycol carbonate as the sensitive element. These dosimeters have a number of limitations, including a high limit of detection (typically 200 microsieverts), insensitivity to low-energy neutrons, and a strong angular dependence. Such limitations, along with the incorporation of the recommendations of the International Commission on Radiological Protection (ICRP) 60 into the revised U.K. Ionizing Radiation Regulations 1999, have provided the opportunity to reconsider spectrometric and dosimetric research in support of the NNPP. Area neutron dosimetry is most usually performed using a Leake-type spherical survey meter. In both the case of area and, more significantly, personal dosimetry, the differences in the energy spectra between the calibration and the operational fields require a location correction factor (LCF) to be applied. To determine these LCFs, it is necessary to accurately characterize the operational energy spectra. This characterization is undertaken using the transportable neutron spectrometer (TNS) developed by the U.K. Atomic Energy Establishment at Winfrith in the 1980s. Our research has focused on two areas, the development of an improved TNS system and a complimentary program to design a new area survey meter.

  12. Commercial Nuclear Waste Research and Development Program. Quarterly report, April-June 1985

    SciTech Connect

    1985-07-01

    Support was provided to DOE/NV during preparation of a proposal, requested by the DOE San Francisco office, for performance of SP-100 Ground Engineering Systems tests at the E-MAD facility. The site selection committee visited the Nevada Test Site in May for a tour and briefings on all aspects of the proposal. The fuel assembly used in the two-year metal cask simulation test was removed from the test stand and characterized to document its post-test condition. Fuel assembly integrity monitoring for the second half of FY 1985 was completed of six of the fuel assemblies being stored in unwelded canisters. Post-storage characterization was completed on three fuel assemblies which were stored in welded canisters. All test procedures have been completed and delivered for the Canister Assembly Launch Test Program being conducted at another Area 25 facility. The "Safety Assessment Document for Spent Fuel Handling, Packaging, and Storage Demonstrations at the E-MAD Facility on the Nevada Test Site," DOE/NV10250-20, was revised to be consistent with new and revised DOE Orders and Directives, and delivered to DOE/NV.

  13. JPRS report, nuclear developments

    SciTech Connect

    1991-03-28

    This report contains articles concerning the nuclear developments of the following countries: (1) China; (2) Japan, North Korea, South Korea; (3) Bulgaria; (4) Argentina, Brazil, Honduras; (5) India, Iran, Pakistan, Syria; (6) Soviet Union; and (7) France, Germany, Turkey.

  14. Nuclear programs in India and Pakistan

    NASA Astrophysics Data System (ADS)

    Mian, Zia

    2014-05-01

    India and Pakistan launched their respective nuclear programs in the 1940s and 1950s with considerable foreign technical support, especially from the United States Atoms for Peace Program. The technology and training that was acquired served as the platform for later nuclear weapon development efforts that included nuclear weapon testing in 1974 and in 1998 by India, and also in 1998 by Pakistan - which had illicitly acquired uranium enrichment technology especially from Europe and received assistance from China. As of 2013, both India and Pakistan were continuing to produce fissile material for weapons, in the case of India also for nuclear naval fuel, and were developing a diverse array of ballistic and cruise missiles. International efforts to restrain the South Asian nuclear build-up have been largely set aside over the past decade as Pakistani support became central for the U.S. war in Afghanistan and as U.S. geopolitical and economic interests in supporting the rise of India, in part as a counter to China, led to India being exempted both from U.S non-proliferation laws and international nuclear trade guidelines. In the absence of determined international action and with Pakistan blocking the start of talks on a fissile material cutoff treaty, nuclear weapon programs in South Asia are likely to keep growing for the foreseeable future.

  15. Nuclear programs in India and Pakistan

    SciTech Connect

    Mian, Zia

    2014-05-09

    India and Pakistan launched their respective nuclear programs in the 1940s and 1950s with considerable foreign technical support, especially from the United States Atoms for Peace Program. The technology and training that was acquired served as the platform for later nuclear weapon development efforts that included nuclear weapon testing in 1974 and in 1998 by India, and also in 1998 by Pakistan - which had illicitly acquired uranium enrichment technology especially from Europe and received assistance from China. As of 2013, both India and Pakistan were continuing to produce fissile material for weapons, in the case of India also for nuclear naval fuel, and were developing a diverse array of ballistic and cruise missiles. International efforts to restrain the South Asian nuclear build-up have been largely set aside over the past decade as Pakistani support became central for the U.S. war in Afghanistan and as U.S. geopolitical and economic interests in supporting the rise of India, in part as a counter to China, led to India being exempted both from U.S non-proliferation laws and international nuclear trade guidelines. In the absence of determined international action and with Pakistan blocking the start of talks on a fissile material cutoff treaty, nuclear weapon programs in South Asia are likely to keep growing for the foreseeable future.

  16. THE NEXT GENERATION NUCLEAR PLANT GRAPHITE PROGRAM

    SciTech Connect

    William E. Windes; Timothy D. Burchell; Robert L. Bratton

    2008-09-01

    Developing new nuclear grades of graphite used in the core of a High Temperature Gas-cooled Reactor (HTGR) is one of the critical development activities being pursued within the Next Generation Nuclear Plant (NGNP) program. Graphite’s thermal stability (in an inert gas environment), high compressive strength, fabricability, and cost effective price make it an ideal core structural material for the HTGR reactor design. While the general characteristics necessary for producing nuclear grade graphite are understood, historical “nuclear” grades no longer exist. New grades must be fabricated, characterized, and irradiated to demonstrate that current grades of graphite exhibit acceptable non-irradiated and irradiated properties upon which the thermo-mechanical design of the structural graphite in NGNP is based. The NGNP graphite R&D program has selected a handful of commercially available types for research and development activities necessary to qualify this nuclear grade graphite for use within the NGNP reactor. These activities fall within five primary areas; 1) material property characterization, 2) irradiated material property characterization, 3) modeling, and 4) ASTM test development, and 5) ASME code development efforts. Individual research and development activities within each area are being pursued with the ultimate goal of obtaining a commercial operating license for the nuclear graphite from the US NRC.

  17. JPRS report, nuclear developments

    SciTech Connect

    1991-02-25

    This report contains articles concerning the nuclear developments of the following countries: (1) China; (2) Indonesia, North Korea, South Korea, Thailand; (3) Bulgaria, Czechoslovakia, Hungary; (4) Argentina, Brazil, El Salvador, Nicaragua; (5) India, Iran, Bangladesh, Israel, Egypt, Jordan, Pakistan; (6) Soviet Union; (7) France, Germany, Austria, United Kingdom; and (8) South Africa.

  18. JPRS report, nuclear developments

    SciTech Connect

    1991-03-19

    This report contains articles concerning the nuclear developments of the following countries: (1) China; (2) Japan, North Korea, South Korea, Taiwan; (3) Bulgaria, Czechoslovakia, Yugoslavia; (4) Argentina, Brazil, Panama; (5) India, Iran, Pakistan, Israel, Afghanistan; (6) Soviet Union; (7) France, Germany, Turkey, Belgium, Canada, Netherlands, Switzerland, United Kingdom; and (8) South Africa.

  19. JPRS report, nuclear developments

    SciTech Connect

    1991-02-05

    This report contains articles concerning the nuclear developments of the following countries: (1) China; (2) Japan, North Korea, South Korea; (3) Czechoslovakia; (4) Argentina, Brazil; (5) India, Pakistan; (6) Soviet Union; (7) France, Germany, Canada, Italy, Sweden, Switzerland, United Kingdom; and (8) Ghana, Mauritius.

  20. JPRS report, nuclear developments

    SciTech Connect

    1991-01-04

    This report contains articles concerning the nuclear developments of the following countries: (1) China; (2) Japan, North Korea, South Korea; (3) Bulgaria, Czechoslovakia, Rumania; (4) Argentina, Brazil, Peru; (5) India, Iraq, Syria, Israel, Egypt, Mauritania, Pakistan; (6) Soviet Union; (7) France, Germany, Austria, Canada, Italy, Spain; and (8) South Africa.

  1. A Discrepancy-Based Methodology for Nuclear Training Program Evaluation.

    ERIC Educational Resources Information Center

    Cantor, Jeffrey A.

    1991-01-01

    A three-phase comprehensive process for commercial nuclear power training program evaluation is presented. The discrepancy-based methodology was developed after the Three Mile Island nuclear reactor accident. It facilitates analysis of program components to identify discrepancies among program specifications, actual outcomes, and industry…

  2. ABC Technology Development Program

    SciTech Connect

    1994-10-14

    The Accelerator-Based Conversion (ABC) facility will be designed to accomplish the following mission: `Provide a weapon`s grade plutonium disposition capability in a safe, economical, and environmentally sound manner on a prudent schedule for [50] tons of weapon`s grade plutonium to be disposed on in [20] years.` This mission is supported by four major objectives: provide a reliable plutonium disposition capability within the next [15] years; provide a level of safety and of safety assurance that meets or exceeds that afforded to the public by modern commercial nuclear power plants; meet or exceed all applicable federal, state, and local regulations or standards for environmental compliance; manage the program in a cost effective manner. The ABC Technology Development Program defines the technology development activities that are required to accomplish this mission. The technology development tasks are related to the following topics: blanket system; vessel systems; reactivity control systems; heat transport system components; energy conversion systems; shutdown heat transport systems components; auxiliary systems; technology demonstrations - large scale experiments.

  3. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1980-September 30, 1980

    SciTech Connect

    Not Available

    1980-12-12

    Objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, 950 and 1050/sup 0/C. Initiation of controlled purity helium creep-rupture testing in the intensive screening test program is discussed. In addition, the results of 1000-hour exposures at 750 and 850/sup 0/C on several experimental alloys are discussed.

  4. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, April 1, 1980-June 30, 1980

    SciTech Connect

    Not Available

    1980-11-14

    Objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described; this includes: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850 and 950/sup 0/C. The initiation of air creep-rupture testing in the intensive screening test program is discussed. In addition, the status of the data management system is described.

  5. Iraq's secret nuclear weapons program

    SciTech Connect

    Davis, J.C. ); Kay, D.A. )

    1992-07-01

    UN inspectors discovered an electromagnetic isotope separation factory that put Iraq just 18-30 months away from having enough material for a bomb. They also found European centrifuge technology and plans for an implosion device. The inspections of Iraq mandated by the United Nations as a cease-fire condition at the end of the Gulf War in February 1991 have revealed a clandestine nuclear materials production and weapons design program of unexpected size and sophistication. The total value of that program, in terms of equipment and personnel deployed between 1981 and 1991, may be on the order of $5-10 billion. The program employed an estimated 7000 scientist and 20,000 workers. 6 refs., 4 figs.

  6. Opportunities for Russian Nuclear Weapons Institute developing computer-aided design programs for pharmaceutical drug discovery. Final report

    SciTech Connect

    1996-09-23

    The goal of this study is to determine whether physicists at the Russian Nuclear Weapons Institute can profitably service the need for computer aided drug design (CADD) programs. The Russian physicists` primary competitive advantage is their ability to write particularly efficient code able to work with limited computing power; a history of working with very large, complex modeling systems; an extensive knowledge of physics and mathematics, and price competitiveness. Their primary competitive disadvantage is their lack of biology, and cultural and geographic issues. The first phase of the study focused on defining the competitive landscape, primarily through interviews with and literature searches on the key providers of CADD software. The second phase focused on users of CADD technology to determine deficiencies in the current product offerings, to understand what product they most desired, and to define the potential demand for such a product.

  7. DOE-Nuclear Energy Standards Program annual assessment, FY 1989

    SciTech Connect

    Cooper, W.L. Jr.

    1989-11-01

    To meet the objectives of the programs funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs, the Performance Assurance Project Office (PAPO) administers a nuclear standards program and related activities and fosters the development and application of standards. This standards program is carried out in accordance with the principle in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980. The purposes of this effort, as set forth in three subtasks, are to (1) manage the NE Standards Program, (2) manage the development and maintenance of NE standards, and (3) operate an NE Standards Information Program.

  8. Staff Development Program Evaluation.

    ERIC Educational Resources Information Center

    Ashur, Nina E.; And Others

    An evaluation of the staff development program at College of the Canyons (California) was conducted in 1991 to provide information applicable to program improvement. Questionnaires were distributed to all faculty, classified staff, and flexible calendar program committee and staff development advisory committee members, resulting in response rates…

  9. Guidelines for Program Development.

    ERIC Educational Resources Information Center

    Manitoba Dept. of Education and Training, Winnipeg. Literacy and Continuing Education Branch.

    This guide, which is intended to assist developers of community-based adult literacy programs in Manitoba, explains the following components of good programming and presents suggestions for integrating them into literacy provision: community outreach, program development, learner involvement, provision of appropriate staffing, use of volunteers,…

  10. Nuclear Engineering Academic Programs Survey, 2004

    SciTech Connect

    Oak Ridge Institute for Science and Education

    2005-03-01

    This annual report details the number of nuclear engineering bachelor's, master's, and doctoral degrees awarded at a sampling of academic programs from 1998-2004. It also looks at nuclear engineering degrees by curriculum and the number of students enrolled in nuclear engineering degree programs at 31 U.S. universities in 2004.

  11. Status of Iran's nuclear program and negotiations

    SciTech Connect

    Albright, David

    2014-05-09

    Iran's nuclear program poses immense challenges to international security. Its gas centrifuge program has grown dramatically in the last several years, bringing Iran close to a point where it could produce highly enriched uranium in secret or declared gas centrifuge plants before its breakout would be discovered and stopped. To reduce the risk posed by Iran's nuclear program, the P5+1 have negotiated with Iran short term limits on the most dangerous aspects of its nuclear programs and is negotiating long-term arrangements that can provide assurance that Iran will not build nuclear weapons. These long-term arrangements need to include a far more limited and transparent Iranian nuclear program. In advance of arriving at a long-term arrangement, the IAEA will need to resolve its concerns about the alleged past and possibly on-going military dimensions of Iran's nuclear program.

  12. Status of Iran's nuclear program and negotiations

    NASA Astrophysics Data System (ADS)

    Albright, David

    2014-05-01

    Iran's nuclear program poses immense challenges to international security. Its gas centrifuge program has grown dramatically in the last several years, bringing Iran close to a point where it could produce highly enriched uranium in secret or declared gas centrifuge plants before its breakout would be discovered and stopped. To reduce the risk posed by Iran's nuclear program, the P5+1 have negotiated with Iran short term limits on the most dangerous aspects of its nuclear programs and is negotiating long-term arrangements that can provide assurance that Iran will not build nuclear weapons. These long-term arrangements need to include a far more limited and transparent Iranian nuclear program. In advance of arriving at a long-term arrangement, the IAEA will need to resolve its concerns about the alleged past and possibly on-going military dimensions of Iran's nuclear program.

  13. Environmental Detection of Clandestine Nuclear Weapon Programs

    NASA Astrophysics Data System (ADS)

    Kemp, R. Scott

    2016-06-01

    Environmental sensing of nuclear activities has the potential to detect nuclear weapon programs at early stages, deter nuclear proliferation, and help verify nuclear accords. However, no robust system of detection has been deployed to date. This can be variously attributed to high costs, technical limitations in detector technology, simple countermeasures, and uncertainty about the magnitude or behavior of potential signals. In this article, current capabilities and promising opportunities are reviewed. Systematic research in a variety of areas could improve prospects for detecting covert nuclear programs, although the potential for countermeasures suggests long-term verification of nuclear agreements will need to rely on methods other than environmental sensing.

  14. University Career Development Programming

    ERIC Educational Resources Information Center

    Cochran, Donald J.; Rademacher, Betty Green

    1978-01-01

    Pertinent considerations involved in the delivery of career development services at the college level are reviewed. Specific examples of possible career programming alternatives are discussed and summarized in an organizational grid. A detailed case is included as a concrete example of career program development. (Author)

  15. Leadership in Program Development.

    ERIC Educational Resources Information Center

    Moon, Sidney; Swift, Melanie

    1989-01-01

    Presented are a literature review, model, and case study for effective local program development for gifted and talented students. The model applies the research on educational change and institutional excellence to the task of developing excellent programs for gifted/talented youth in school districts of various types and sizes. (PB)

  16. The Development, Content, Design, and Conduct of the 2011 Piloted US DOE Nuclear Criticality Safety Program Criticality Safety Engineering Training and Education Project

    SciTech Connect

    Hopper, Calvin Mitchell

    2011-01-01

    In May 1973 the University of New Mexico conducted the first nationwide criticality safety training and education week-long short course for nuclear criticality safety engineers. Subsequent to that course, the Los Alamos Critical Experiments Facility (LACEF) developed very successful 'hands-on' subcritical and critical training programs for operators, supervisors, and engineering staff. Since the inception of the US Department of Energy (DOE) Nuclear Criticality Technology and Safety Project (NCT&SP) in 1983, the DOE has stimulated contractor facilities and laboratories to collaborate in the furthering of nuclear criticality as a discipline. That effort included the education and training of nuclear criticality safety engineers (NCSEs). In 1985 a textbook was written that established a path toward formalizing education and training for NCSEs. Though the NCT&SP went through a brief hiatus from 1990 to 1992, other DOE-supported programs were evolving to the benefit of NCSE training and education. In 1993 the DOE established a Nuclear Criticality Safety Program (NCSP) and undertook a comprehensive development effort to expand the extant LACEF 'hands-on' course specifically for the education and training of NCSEs. That successful education and training was interrupted in 2006 for the closing of the LACEF and the accompanying movement of materials and critical experiment machines to the Nevada Test Site. Prior to that closing, the Lawrence Livermore National Laboratory (LLNL) was commissioned by the US DOE NCSP to establish an independent hands-on NCSE subcritical education and training course. The course provided an interim transition for the establishment of a reinvigorated and expanded two-week NCSE education and training program in 2011. The 2011 piloted two-week course was coordinated by the Oak Ridge National Laboratory (ORNL) and jointly conducted by the Los Alamos National Laboratory (LANL) classroom education and facility training, the Sandia National

  17. Space Nuclear Thermal Propulsion (SNTP) program

    NASA Technical Reports Server (NTRS)

    Bleeker, Gary A.

    1993-01-01

    An overview of the Space Nuclear Thermal Propulsion program is presented in graphic form. A program organizational chart is presented that shows the government and industry participants. Enabling technologies and test facilities and approaches are also addressed.

  18. The SCARLET development program

    SciTech Connect

    Allen, D.M.; Piszczor, M.F. Jr.

    1995-12-31

    The paper describes the SCARLET program that has developed an exciting new type of spacecraft solar array. The program includes design, fabrication, testing, and integration to the Comet satellite and has been accomplished in a half year time period. Background of the program, an overview of satellite integration benefits and concerns for concentrator arrays, and a summary of the program development process and rationale arc included. The history making first SCARLET array will be flown on the Comet spacecraft which will be launched on a Conestoga launch vehicle from Wallops Island in July 1995.

  19. Developing an Intergenerational Program.

    ERIC Educational Resources Information Center

    Brummel, Steven W.

    1989-01-01

    Steps in the development of intergenerational programs include the following: (1) needs assessment; (2) planning; (3) implementation; (4) assuring program longevity; and (5) establishing a national focus. Detailed description of such stages as facility and site procurement, recruitment, orientation, training, maintenance, and support is provided.…

  20. The nuclear data program at rensselaer

    NASA Astrophysics Data System (ADS)

    Danon, Y.; Blain, Z.; Bahran, R.; Rapp, M.; Thompson, J.; Williams, D.; Leinweber, G.; Barry, D.; Block, R.; Hoole, J.

    2010-10-01

    The nuclear data program at the Rensselaer Polytechnic Institute (RPI) is centered around a 60 MeV pulsed electron Linear Accelerator (LINAC) configured to deliver pulsed neutron beams. The LINAC electron pulse width can vary between 5 ns and 5 us, a repetition rate of 1-500 pulses per second and neutron yield of up to 1013 n/s. Over the years several experimental setups and techniques were developed to enable a variety of measurement capabilities. The experiments cover the energy range from 0.001 eV to 20 MeV and included neutron transmission, capture, scattering and fission measurements. The facility is also equipped with a Lead Slowing-Down Spectrometer (LSDS) producing a high neutron flux that is used for simultaneous measurements of the fission cross section and fission fragment mass and energy distributions. Detectors for (n, alpha) and (n, p) cross section measurements using the LSDS were also developed and measurements of (n, alpha) cross section were completed. The high neutron flux inside the LSDS enables measurements on small samples (sub micrograms) or samples with small cross section (sub millibarns). In order to fully utilize the capabilities of the facility, several measurement techniques were developed; high accuracy (<1%) total cross sections were measured using iron and uranium filtered neutron beams. A system for fast neutron scattering measurements using an array of liquid scintillators and a digital data acquisition system was recently developed and used for several measurements and is now being adapted for fission neutron studies. Methods for simultaneous measurements of fission and capture cross sections using the RPI multiplicity detector are under development and new modular detectors for both fast and resonance region neutron detection were developed and deployed. These developments result in numerous measurements on different materials and provide input to improved evaluated nuclear data libraries and thus help improve the accuracy of

  1. The MSFC Program Control Development Program

    NASA Technical Reports Server (NTRS)

    1994-01-01

    It is the policy of the Marshall Space Flight Center (MSFC) that employees be given the opportunity to develop their individual skills and realize their full potential consistent with their selected career path and with the overall Center's needs and objectives. The MSFC Program Control Development Program has been designed to assist individuals who have selected Program Control or Program Analyst Program Control as a career path to achieve their ultimate career goals. Individuals selected to participate in the MSFC Program Control Development Program will be provided with development training in the various Program Control functional areas identified in the NASA Program Control Model. The purpose of the MSFC Program Control Development Program is to develop individual skills in the various Program Control functions by on-the-job and classroom instructional training on the various systems, tools, techniques, and processes utilized in these areas.

  2. Trauma program development.

    PubMed

    Althausen, Peter L

    2014-07-01

    The development of a strong trauma program is clearly one of the most important facets of successful business development. Several recent publications have demonstrated that well run trauma services can generate significant profits for both the hospital and the surgeons involved. There are many aspects to this task that require constant attention and insight. Top notch patient care, efficiency, and cost-effective resource utilization are all important components that must be addressed while providing adequate physician compensation within the bounds of hospital financial constraints and the encompassing legal issues. Each situation is different but many of the components are universal. This chapter addresses all aspects of trauma program development to provide the graduating fellow with the tools to create a new trauma program or improve an existing program in order to provide the best patient care while optimizing financial reward and improving care efficiency. PMID:24918830

  3. Nuclear Migration During Retinal Development

    PubMed Central

    Baye, Lisa M.; Link, Brian A.

    2009-01-01

    In this review we focus on the mechanisms, regulation, and cellular consequences of nuclear migration in the developing retina. In the nervous system, nuclear migration is prominent during both proliferative and post-mitotic phases of development. Interkinetic nuclear migration is the process where the nucleus oscillates from the apical to basal surfaces in proliferative neuroepithelia. Proliferative nuclear movement occurs in step with the cell cycle, with M-phase being confined to the apical surface and G1-, S-, and G2-phases occurring at more basal locations. Later, following cell cycle exit, some neuron precursors migrate by nuclear translocation. In this mode of cellular migration, nuclear movement is the driving force for motility. Following discussion of the key components and important regulators for each of these processes, we present an emerging model where interkinetic nuclear migration functions to distinguish cell fates among retinal neuroepithelia. PMID:17560964

  4. FY 2007 LDRD Director's R&D Progress SummaryProposal Title: Developing a Science Base for Fuel Reprocessing Separations in the Global Nuclear Energy Program

    SciTech Connect

    de Almeida, Valmor F; Tsouris, Costas; Birdwell Jr, Joseph F; D'Azevedo, Ed F; Jubin, Robert Thomas; DePaoli, David W; Moyer, Bruce A

    2011-01-01

    This work is aimed at developing an experimentally validated computational capability for understanding the complex processes governing the performance of solvent extraction devices used for separations in nuclear fuel reprocessing. These applications pose a grand challenge due to the combination of complicating factors in a three-dimensional, turbulent, reactive, multicomponent, multiphase/interface fluid flow system. The currently limited process simulation and scale-up capabilities provides uncertainty in the ability to select and design the separations technology for the demonstration plan of the Global Nuclear Energy Partnership (GNEP) program. We anticipate the development of science-based models for technology development and design. This project will position ORNL to address the emerging opportunity by creating an expandable process model validated experimentally. This project has three major thrusts, namely, a prototype experimental station, a continuum modeling and simulation effort, and molecular modeling and kinetics support. Excellent progress has been made in corresponding activities in this first year in: (1) defining, assembling, and operating a relevant prototype system for model validation; (2) establishing a mathematical model for fluid flow and transport; (3) deploying sub-scale molecular modeling.

  5. EPRI guide to managing nuclear utility protective clothing programs

    SciTech Connect

    Kelly, J.J. )

    1991-05-01

    The Electric Power Research Institute (EPRI) commissioned a radioactive waste related project (RP2414-34) during the last quarter of 1989 to produce a guide for developing and managing nuclear protective clothing programs. Every nuclear facility must coordinate some type of protective clothing program for its radiation workers to insure proper and safe protection for the wearer and to maintain control over the spread of contamination. Yet, every nuclear facility has developed its own unique program for managing such clothing. Accordingly, a need existed for a reference guide to assist with the standardization of protective clothing programs and to assist in controlling the potentially runaway economics of such programs. This document is the first known effort to formalize the planning and economic factors surrounding a nuclear utility protective clothing program. It is intended to be informative by addressing the various pieces of information necessary to establish and maintain an effective, professionally managed protective clothing program. It also attempts to provide guidance toward tailoring the information and providing examples within the report to fit each utility's specific needs. This report is further intended to address new issues and trends occurring throughout the nuclear industry in late 1989 which can have either a significant positive or negative impact on the operations or economics of nuclear protective clothing programs. 1 ref., 11 tabs.

  6. Nuclear proliferation: The diplomatic role of non-weaponized programs

    SciTech Connect

    Reynolds, R.R.

    1996-01-01

    The end of the Cold War has not seen the end of reliance on nuclear weapons for deterrence or diplomacy purposes. The use of nuclear weapons for such purposes is as evident in the threshold states as in the nuclear powers. The nuclear weapon states used their nuclear weapons for deterrence, bargaining, and blackmail, even during the early years of the Cold War when the US was essentially non-Weaponized. In the nuclear non-Weaponized states in Asia a non-Weaponized deterrent relationship is developing between India and Pakistan and North Korea has used its nuclear program to restore diplomatic relations with the international community. The role of nuclear weapons in the post Cold War world is determined by the role of non-Weaponized programs in proliferating states. This paper describes examples in South Asia and the Korean peninsula and show that while an increased reliance on nuclear weapons programs may be a threat to the current non-proliferation regime, the focus on non-Weaponized programs rather than on weapons themselves actually improves international security by reducing the threat of nuclear war.

  7. Update on DOE's Nuclear Energy University Program

    NASA Astrophysics Data System (ADS)

    Lambregts, Marsha J.

    2009-08-01

    The Nuclear Energy University Program (NEUP) Office assists the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) by administering its University Program. To promote accountable relationships between universities and the Technical Integration Offices (TIOs)/Technology Development Offices (TDOs), a process was designed and administered which includes two competitive Requests for Proposals (RFPs) and two Funding Opportunity Announcements (FOAs) in the following areas: (1) Research and Development (R&D) Grants, (2) Infrastructure improvement, and (3) Scholarships and Fellowships. NEUP will also host periodic reviews of university mission-specific R&D that document progress, reinforce accountability, and assess return on investment; sponsor workshops that inform universities of the Department's research needs to facilitate continued alignment of university R&D with NE missions; and conduct communications activities that foster stakeholder trust, serve as a catalyst for accomplishing NEUP objectives, and provide national visibility of NEUP activities and accomplishments. Year to date efforts to achieve these goals will be discussed.

  8. Update on DOE's Nuclear Energy University Program

    SciTech Connect

    Lambregts, Marsha J.

    2009-08-19

    The Nuclear Energy University Program (NEUP) Office assists the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) by administering its University Program. To promote accountable relationships between universities and the Technical Integration Offices (TIOs)/Technology Development Offices (TDOs), a process was designed and administered which includes two competitive Requests for Proposals (RFPs) and two Funding Opportunity Announcements (FOAs) in the following areas: (1) Research and Development (R and D) Grants, (2) Infrastructure improvement, and (3) Scholarships and Fellowships. NEUP will also host periodic reviews of university mission-specific R and D that document progress, reinforce accountability, and assess return on investment; sponsor workshops that inform universities of the Department's research needs to facilitate continued alignment of university R and D with NE missions; and conduct communications activities that foster stakeholder trust, serve as a catalyst for accomplishing NEUP objectives, and provide national visibility of NEUP activities and accomplishments. Year to date efforts to achieve these goals will be discussed.

  9. Nuclear Cryogenic Propulsion Stage Affordable Development Strategy

    NASA Technical Reports Server (NTRS)

    Doughty, Glen E.; Gerrish, H. P.; Kenny, R. J.

    2014-01-01

    The development of nuclear power for space use in nuclear thermal propulsion (NTP) systems will involve significant expenditures of funds and require major technology development efforts. The development effort must be economically viable yet sufficient to validate the systems designed. Efforts are underway within the National Aeronautics and Space Administration's (NASA) Nuclear Cryogenic Propulsion Stage Project (NCPS) to study what a viable program would entail. The study will produce an integrated schedule, cost estimate and technology development plan. This will include the evaluation of various options for test facilities, types of testing and use of the engine, components, and technology developed. A "Human Rating" approach will also be developed and factored into the schedule, budget and technology development approach.

  10. The development of nuclear energy in the Philippines

    SciTech Connect

    Aleta, C. )

    1992-01-01

    The paper traces the development of nuclear energy in the Philippines and outlines the program on the peaceful uses of nuclear energy in the country as well as the problems and prospects of nuclear energy development. Nuclear power is at a standstill but the other areas of nuclear energy development are underway. The projects on the application of nuclear energy in agriculture, industry, public health and safety, are being pursued. Technology transfer to end users is sometimes hampered by public acceptance issues, such as irradiated food being believed to become radioactive, dislike with anything associated with radiation, and plain inherent fear of nuclear energy.

  11. Nuclear Waste Management Program summary document, FY 1981

    SciTech Connect

    Meyers, Sheldon

    1980-03-01

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel.

  12. Review of EPRI Nuclear Human Factors Program

    SciTech Connect

    Hanes, L.F.; O`Brien, J.F.

    1996-03-01

    The Electric Power Research Institute (EPRI) Human Factors Program, which is part of the EPRI Nuclear Power Group, was established in 1975. Over the years, the Program has changed emphasis based on the shifting priorities and needs of the commercial nuclear power industry. The Program has produced many important products that provide significant safety and economic benefits for EPRI member utilities. This presentation will provide a brief history of the Program and products. Current projects and products that have been released recently will be mentioned.

  13. Iran's nuclear-power program revisited

    SciTech Connect

    Mossavar-Rahmani, B.

    1980-09-01

    Iran's new government has not yet decided the fate of the country's once-ambitious nuclear power program. If the program is kept alive, it will be limited to the completion of at most one or two of the reactors that were already well underway then the revolution broke out. The author traces the origins and growth of the Iranian nuclear-power program between 1974 and 1978, summarizes the principal economic, infrasturctural, and political criticisms of the program as originally planned, discusses the potential for greater use of natural gas as an alternative and, finally, recommends a long, detailed reassessment of Iran's energy options. 13 references, 3 tables.

  14. Nuclear Engineering Academic Programs Survey, 2003

    SciTech Connect

    Science and Engineering Education, Oak Ridge Institute for Science and Education

    2004-03-01

    The survey includes degrees granted between September 1, 2002 and August 31, 2003. Thirty-three academic programs reported having nuclear engineering programs during the survey time period and all responded (100% response rate). Three of the programs included in last year's report were discontinued or out-of-scope in 2003. One new program has been added to the list. This year the survey data include U.S. citizenship, gender, and race/ethnicity by degree level.

  15. Developing hazardous waste programs

    NASA Astrophysics Data System (ADS)

    Showstack, Randy

    Developing a fully operational hazardous waste regulatory system requires at least 10 to 15 years—even in countries with strong legal and bureaucratic institutions, according to a report on "The Evolution of Hazardous Waste Programs," which was funded by Resources for the Future (RFF) and the World Bank's South Asia Environment Group, and issued on June 4.The report, which compares the experiences of how four developed and four developing countries have created hazardous waste programs, indicates that hazardous waste issues usually do not become a pressing environmental issue until after countries have dealt with more direct threats to public health, such as contaminated drinking water and air pollution. The countries examined include Indonesia, Thailand, Germany, and the United States.

  16. Nuclear Concrete Materials Database Phase I Development

    SciTech Connect

    Ren, Weiju; Naus, Dan J

    2012-05-01

    The FY 2011 accomplishments in Phase I development of the Nuclear Concrete Materials Database to support the Light Water Reactor Sustainability Program are summarized. The database has been developed using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In this Phase I development, the database has been successfully designed and constructed to manage documents in the Portable Document Format generated from the Structural Materials Handbook that contains nuclear concrete materials data and related information. The completion of the Phase I database has established a solid foundation for Phase II development, in which a digital database will be designed and constructed to manage nuclear concrete materials data in various digitized formats to facilitate electronic and mathematical processing for analysis, modeling, and design applications.

  17. Nuclear Materials Management Program at the NNSS

    SciTech Connect

    ,

    2012-06-08

    The Nevada National Security Site (NNSS), formerly the Nevada Test Site, was established in 1951 mainly for weapons testing; because special nuclear materials (SNM) were expended during the tests, a nuclear material management program was not required. That changed in December 2004 with the receipt of Category I SNM for purposes other than weapons testing. At that time, Material Control and Accountability and Nuclear Material Management were a joint laboratory (Los Alamos and Lawrence Livermore) effort with nuclear material management being performed at the laboratories. That changed in March 2006 when the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office appointed sole responsibility to the Management and Operations (M&O) contractor, National Security Technologies, LLC (NSTec). Since 2006 the basic nuclear material management work was completed by a combination of M&O employees and subcontractors, but a true Nuclear Material Management (NMM) Program was not determined to be necessary until recently. With expanding missions and more nuclear material (NM) coming to the NNSS, it became imperative to have an organization to manage these materials; therefore, an NMM Manager was officially appointed by NSTec in 2012. In June 2011 a Gap Analysis and white paper was completed by a subcontractor; this presentation will include highlights from those documents along with our plans to resolve the “gaps” and stand up a functional and compliant NMM Program at the NNSS.

  18. Criteria for Global Nuclear Energy Development

    SciTech Connect

    Lawrence, Michael J.

    2002-07-01

    Global energy consumption will at least double over the next fifty years due to population growth, increased consumption, and an urgent need to improve the standard of living in under-developed countries. Thirty percent of this growth will be for electricity. At the same time, carbon emissions must be significantly reduced to respond to concerns regarding global warming. The use of nuclear energy to meet this growing electricity demand without carbon emissions is an obvious solution to many observers, however real concerns over economics, safety, waste and proliferation must be adequately addressed. The issue is further complicated by the fact that developing countries, which have the most pressing need for additional electricity generation, have the least capability and infrastructure to deploy nuclear energy. Nevertheless, if the specific needs of developing countries are appropriately considered now as new generation reactors are being developed, and institutional arrangements based upon the fundamental principles of President Eisenhower's 1953 Atoms For Peace speech are followed, nuclear energy could be deployed in any country. From a technical perspective, reactor safety and accessibility of special nuclear material are primary concerns. Institutionally, plant and fuel ownership and waste management issues must be addressed. International safety and safeguards authority are prerequisites. While the IAEA's IMPRO program and the United States' Generation IV programs are focusing on technical solutions, institutional issues, particularly with regard to deployment in developing countries, are not receiving corresponding attention. Full-service, cradle-to-grave, nuclear electricity companies that retain custody and responsibility for the plant and materials, including waste, are one possible solution. Small modular reactors such as the Pebble Bed Modular Reactor could be ideal for such an arrangement. While waste disposal remains a major obstacle, this is already

  19. Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, October 1, 1979-December 31, 1979

    SciTech Connect

    Not Available

    1980-04-18

    This report presents the results of work performed from October 1, 1979 through December 31, 1979. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described. This includes: screening creep results, weight gain and post-exposure mechanical properties for materials thermally exposed at 750/sup 0/ and 850/sup 0/C (1382/sup 0/ and 1562/sup 0/F). In addition, the status of the data management system is described.

  20. Developing disease management programs.

    PubMed

    Herman, K

    1999-11-01

    Several market forces are driving interest in disease management and its growth, including the need to control costs; improve quality; attract, satisfy, and retain members; and meet accreditation requirements. People with chronic diseases and disabilities represent the most expensive and fastest-growing group of patients in health care, and agencies that develop successful disease management programs for these populations will reap a variety of benefits. PMID:10661985

  1. Robot development for nuclear material processing

    SciTech Connect

    Pedrotti, L.R.; Armantrout, G.A.; Allen, D.C.; Sievers, R.H. Sr.

    1991-07-01

    The Department of Energy is seeking to modernize its special nuclear material (SNM) production facilities and concurrently reduce radiation exposures and process and incidental radioactive waste generated. As part of this program, Lawrence Livermore National Laboratory (LLNL) lead team is developing and adapting generic and specific applications of commercial robotic technologies to SNM pyrochemical processing and other operations. A working gantry robot within a sealed processing glove box and a telerobot control test bed are manifestations of this effort. This paper describes the development challenges and progress in adapting processing, robotic, and nuclear safety technologies to the application. 3 figs.

  2. NASA safety program activities in support of the Space Exploration Initiatives Nuclear Propulsion program

    NASA Technical Reports Server (NTRS)

    Sawyer, J. C., Jr.

    1993-01-01

    The activities of the joint NASA/DOE/DOD Nuclear Propulsion Program Technical Panels have been used as the basis for the current development of safety policies and requirements for the Space Exploration Initiatives (SEI) Nuclear Propulsion Technology development program. The Safety Division of the NASA Office of Safety and Mission Quality has initiated efforts to develop policies for the safe use of nuclear propulsion in space through involvement in the joint agency Nuclear Safety Policy Working Group (NSPWG), encouraged expansion of the initial policy development into proposed programmatic requirements, and suggested further expansion into the overall risk assessment and risk management process for the NASA Exploration Program. Similar efforts are underway within the Department of Energy to ensure the safe development and testing of nuclear propulsion systems on Earth. This paper describes the NASA safety policy related to requirements for the design of systems that may operate where Earth re-entry is a possibility. The expected plan of action is to support and oversee activities related to the technology development of nuclear propulsion in space, and support the overall safety and risk management program being developed for the NASA Exploration Program.

  3. Nuclear Thermal Propulsion Development Risks

    NASA Technical Reports Server (NTRS)

    Kim, Tony

    2015-01-01

    There are clear advantages of development of a Nuclear Thermal Propulsion (NTP) for a crewed mission to Mars. NTP for in-space propulsion enables more ambitious space missions by providing high thrust at high specific impulse ((is) approximately 900 sec) that is 2 times the best theoretical performance possible for chemical rockets. Missions can be optimized for maximum payload capability to take more payload with reduced total mass to orbit; saving cost on reduction of the number of launch vehicles needed. Or missions can be optimized to minimize trip time significantly to reduce the deep space radiation exposure to the crew. NTR propulsion technology is a game changer for space exploration to Mars and beyond. However, 'NUCLEAR' is a word that is feared and vilified by some groups and the hostility towards development of any nuclear systems can meet great opposition by the public as well as from national leaders and people in authority. The public often associates the 'nuclear' word with weapons of mass destruction. The development NTP is at risk due to unwarranted public fears and clear honest communication of nuclear safety will be critical to the success of the development of the NTP technology. Reducing cost to NTP development is critical to its acceptance and funding. In the past, highly inflated cost estimates of a full-scale development nuclear engine due to Category I nuclear security requirements and costly regulatory requirements have put the NTP technology as a low priority. Innovative approaches utilizing low enriched uranium (LEU). Even though NTP can be a small source of radiation to the crew, NTP can facilitate significant reduction of crew exposure to solar and cosmic radiation by reducing trip times by 3-4 months. Current Human Mars Mission (HMM) trajectories with conventional propulsion systems and fuel-efficient transfer orbits exceed astronaut radiation exposure limits. Utilizing extra propellant from one additional SLS launch and available

  4. St. Lucie nuclear plant's instrument setpoint control program

    SciTech Connect

    Woodruff, B.A. )

    1991-01-01

    In the past several years, instrument setpoint control has become an issue of significant utility focus and concern. Various nuclear industry initiatives have contributed to shaping the current environment. Florida Power and Light Company's St. Lucie nuclear plant maintains a proactive approach to implementing an instrument setpoint control program. St. Lucie's timely response to prevailing setpoint issues ensures that an effective setpoint program is the end result. Florida Power and Light (FP and L) initiated a setpoint control program at St. Lucie, a two-unit Combustion Engineering plant, in 1985. The plan's development was the result of obsolete equipment modifications, setpoint changes, and regulatory inquiries.

  5. Rover nuclear rocket engine program: Overview of rover engine tests

    NASA Technical Reports Server (NTRS)

    Finseth, J. L.

    1991-01-01

    The results of nuclear rocket development activities from the inception of the ROVER program in 1955 through the termination of activities on January 5, 1973 are summarized. This report discusses the nuclear reactor test configurations (non cold flow) along with the nuclear furnace demonstrated during this time frame. Included in the report are brief descriptions of the propulsion systems, test objectives, accomplishments, technical issues, and relevant test results for the various reactor tests. Additionally, this document is specifically aimed at reporting performance data and their relationship to fuel element development with little or no emphasis on other (important) items.

  6. Nuclear target development

    SciTech Connect

    Greene, J.P.; Thomas, G.E.

    1995-08-01

    The Physics Division operates a target development laboratory that produces thin foil targets needed for experiments performed at the ATLAS and Dynamitron accelerators. Targets are not only produced for the Physics Division but also for other divisions and occasionally for other laboratories and universities. In the past year, numerous targets were fabricated by vacuum evaporation either as self-supporting foils or on various substrates. Targets produced included Ag, Au, {sup 10,11}B, {sup 138}Ba, Be, {sup 12}C, {sup 40}Ca, {sup 116}Cd, {sup 155,160}Gd, {sup 76}Ge, In, LID, {sup 6}LiH, Melamine, Mg, {sup 142,150}Nd, {sup 58}Ni, {sup 206,208}Pb, {sup 194}Pt, {sup 28}Si, {sup 144,148}Sm, {sup 120,122,124}Sn, Ta, {sup 130}Te, ThF{sub 4}, {sup 46,50}Ti, TiH, U, UF{sub 4}, {sup 182}W and {sup 170}Yb. Polypropylene and aluminized polypropylene, along with metallized Mylar were produced for experiments at ATLAS. A number of targets of {sup 11}B of various thickness were made for the DEP 2-MeV Van de Graff accelerator. An increased output of foils fabricated using our small rolling mill included targets of Au, C, {sup 50}Cr, Cu, {sup 155,160}Gd, Mg, {sup 58}Ni, {sup 208}Pb, {sup 105,110}Pd. Sc, Ti, and {sup 64,66}Zn.

  7. Nuclear Materials Stewardship Within the DOE Environmental Management Program

    SciTech Connect

    Bilyeu, J. D.; Kiess, T. E.; Gates, M. L.

    2002-02-26

    The Department of Energy (DOE) Environmental Management (EM) Program has made significant progress in planning disposition of its excess nuclear materials and has recently completed several noteworthy studies. Since establishment in 1997, the EM Nuclear Material Stewardship Program has developed disposition plans for excess nuclear materials to support facility deactivation. All nuclear materials have been removed from the Miamisburg Environmental Management Project (Mound), and disposition planning is nearing completion for the Fernald Environmental Management Project and the Rocky Flats Environmental Technology Site. Only a few issues remain for materials at the Hanford and Idaho sites. Recent trade studies include the Savannah River Site Canyons Nuclear Materials Identification Study, a Cesium/Strontium Management Alternatives Trade Study, a Liquid Technical Standards Trade Study, an Irradiated Beryllium Reflectors with Tritium study, a Special Performance Assessment Required Trade Study, a Neutron Source Trade Study, and development of discard criteria for uranium. A Small Sites Workshop was also held. Potential and planned future activities include updating the Plutonium-239 storage study, developing additional packaging standards, developing a Nuclear Material Disposition Handbook, determining how to recover or dispose of Pu-244 and U-233, and working with additional sites to define disposition plans for their nuclear materials.

  8. The Maryland nuclear science baccalaureate degree program: The utility perspective

    SciTech Connect

    Mueller, J.R.

    1989-01-01

    In the early 1980s, Wisconsin Public Service Corporation (WPSC) made a firm commitment to pursue development and subsequent delivery of an appropriate, academically accredited program leading to a baccalaureate degree in nuclear science for its nuclear operations personnel. Recognizing the formidable tasks to be accomplished, WPSC worked closely with the University of Maryland University College (UMUC) in curriculum definition, specific courseware development for delivery by computer-aided instruction, individual student evaluation, and overall program implementation. Instruction began on our nuclear plant site in the fall of 1984. The university anticipates conferring the first degrees from this program at WPSC in the fall of 1989. There are several notable results that WPSC achieved from this degree program. First and most importantly, an increase in the level of education of our employees. It should be stated that this program has been well received by WPSC operator personnel. These employees, now armed with plant experience, a formal degree in nuclear science, and professional education in management are real candidates for advancement in our nuclear organization.

  9. Nuclear Safeguards Infrastructure Development and Integration with Safety and Security

    SciTech Connect

    Kovacic, Donald N; Raffo-Caiado, Ana Claudia; McClelland-Kerr, John; Van sickle, Matthew; Bissani, Mo

    2009-01-01

    Faced with increasing global energy demands, many developing countries are considering building their first nuclear power plant. As a country embarks upon or expands its nuclear power program, it should consider how it will address the 19 issues laid out in the International Atomic Energy Agency (IAEA) document Milestones in Development of a National Infrastructure for Nuclear Power. One of those issues specifically addresses the international nonproliferation treaties and commitments and the implementation of safeguards to prevent diversion of nuclear material from peaceful purposes to nuclear weapons. Given the many legislative, economic, financial, environmental, operational, and other considerations preoccupying their planners, it is often difficult for countries to focus on developing the core strengths needed for effective safeguards implementation. Typically, these countries either have no nuclear experience or it is limited to the operation of research reactors used for radioisotope development and scientific research. As a result, their capacity to apply safeguards and manage fuel operations for a nuclear power program is limited. This paper argues that to address the safeguards issue effectively, a holistic approach must be taken to integrate safeguards with the other IAEA issues including safety and security - sometimes referred to as the '3S' concept. Taking a holistic approach means that a country must consider safeguards within the context of its entire nuclear power program, including operations best practices, safety, and security as well as integration with its larger nonproliferation commitments. The Department of Energy/National Nuclear Security Administration's International Nuclear Safeguards and Engagement Program (INSEP) has been involved in bilateral technical cooperation programs for over 20 years to promote nonproliferation and the peaceful uses of nuclear energy. INSEP is currently spearheading efforts to promote the development of

  10. The MPD thruster development program

    NASA Technical Reports Server (NTRS)

    Rudolph, L. K.; Pawlik, E. V.

    1979-01-01

    Recent research results have inferred that the self-field magnetoplasmadynamic (MPD) thruster can attain efficiency and specific impulse levels which are competitive with ion thrusters. Based on these results, a program was initiated at JPL to develop this thruster for application on future spacecraft. Preliminary mission analyses have shown that the high thrust density MPD arcjet is advantageous for high power missions, such as a short trip time earth orbit transfer vehicle or a nuclear powered outer planet explorer. Direct thrust stand verification of the inferred performance levels used in these analyses is planned for a facility being assembled at Princeton University. A parallel effort at JPL is considering various thruster system configurations, energy storage concepts and propellant control techniques. In addition, a one pulse per second thruster test facility is planned at JPL to be used for thruster optimization studies including erosion and lifetime measurements.

  11. Program For Optimization Of Nuclear Rocket Engines

    NASA Technical Reports Server (NTRS)

    Plebuch, R. K.; Mcdougall, J. K.; Ridolphi, F.; Walton, James T.

    1994-01-01

    NOP is versatile digital-computer program devoloped for parametric analysis of beryllium-reflected, graphite-moderated nuclear rocket engines. Facilitates analysis of performance of engine with respect to such considerations as specific impulse, engine power, type of engine cycle, and engine-design constraints arising from complications of fuel loading and internal gradients of temperature. Predicts minimum weight for specified performance.

  12. Sister Lab Program Prospective Partner Nuclear Profile: Malaysia

    SciTech Connect

    Bissani, M; Tyson, S

    2006-12-14

    The Malaysian Deputy Prime Minister Tun Dr Ismail Abdul Rahman suggested in the early 1970s that Malaysia should have a role in the development of nuclear science and technology for peaceful purposes. Accordingly, the Center for the Application of Nuclear Energy (CRANE) was established, with a focus on the development of a scientific and technical pool critical to a national nuclear power program. The Malaysian Cabinet next established the Tun Ismail Atomic Research Center (TIARC) under the Ministry of Science, Technology and the Environment on 19 September 1972, at a site in Bangi, about 35 km south of Kuala Lampur. On 28 June 1982, the PUSPATI reactor, a 1-MW TRIGA MK-II research reactor, first reached criticality. On 10 August 1994, TIARC was officially renamed as the Malaysian Institute for Nuclear Technology Research (MINT). In addition to radioisotope production and neutron radiography conducted at the PUSPATI research reactor, MINT also supports numerous programs employing nuclear technology for medicine, agriculture and industry, and has been involved in both bilateral and multilateral technical cooperation to extend its capabilities. As an energy exporting country, Malaysia has felt little incentive to develop a nuclear energy program, and high level opposition within the government discouraged it further. A recent statement by Malaysia's Science, Technology and Innovation Minister supported this view, indicating that only a near-catastrophic jump in world oil prices might change the government's view. However, the rate at which Malaysia is using its natural gas and oil reserves is expected to force it to reassess the role of nuclear energy in the near future. In addition, the government does intend to construct a radioactive waste repository to dispose of naturally occurring radioactive materials (extracted during tin mining, in particular). Also, Malaysia's growing economy could encourage expansion in Malaysia's existing nuclear-applications programs

  13. Nonflammable Clothing Development Program

    NASA Technical Reports Server (NTRS)

    Johnston, Richard; Radnofsky, Matthew I.

    1968-01-01

    Protective clothing is of major importance in our space program. The authors discuss the requirements, selection, and testing of materials considered for use in the program. The various types of garments worn by astronauts and support personnel are briefly described.

  14. Nuclear migration events throughout development.

    PubMed

    Bone, Courtney R; Starr, Daniel A

    2016-05-15

    Moving the nucleus to a specific position within the cell is an important event during many cell and developmental processes. Several different molecular mechanisms exist to position nuclei in various cell types. In this Commentary, we review the recent progress made in elucidating mechanisms of nuclear migration in a variety of important developmental models. Genetic approaches to identify mutations that disrupt nuclear migration in yeast, filamentous fungi, Caenorhabditis elegans, Drosophila melanogaster and plants led to the identification of microtubule motors, as well as Sad1p, UNC-84 (SUN) domain and Klarsicht, ANC-1, Syne homology (KASH) domain proteins (LINC complex) that function to connect nuclei to the cytoskeleton. We focus on how these proteins and various mechanisms move nuclei during vertebrate development, including processes related to wound healing of fibroblasts, fertilization, developing myotubes and the developing central nervous system. We also describe how nuclear migration is involved in cells that migrate through constricted spaces. On the basis of these findings, it is becoming increasingly clear that defects in nuclear positioning are associated with human diseases, syndromes and disorders. PMID:27182060

  15. Stanford Hardware Development Program

    NASA Technical Reports Server (NTRS)

    Peterson, A.; Linscott, I.; Burr, J.

    1986-01-01

    Architectures for high performance, digital signal processing, particularly for high resolution, wide band spectrum analysis were developed. These developments are intended to provide instrumentation for NASA's Search for Extraterrestrial Intelligence (SETI) program. The real time signal processing is both formal and experimental. The efficient organization and optimal scheduling of signal processing algorithms were investigated. The work is complemented by efforts in processor architecture design and implementation. A high resolution, multichannel spectrometer that incorporates special purpose microcoded signal processors is being tested. A general purpose signal processor for the data from the multichannel spectrometer was designed to function as the processing element in a highly concurrent machine. The processor performance required for the spectrometer is in the range of 1000 to 10,000 million instructions per second (MIPS). Multiple node processor configurations, where each node performs at 100 MIPS, are sought. The nodes are microprogrammable and are interconnected through a network with high bandwidth for neighboring nodes, and medium bandwidth for nodes at larger distance. The implementation of both the current mutlichannel spectrometer and the signal processor as Very Large Scale Integration CMOS chip sets was commenced.

  16. The Bioscience Nuclear Microscopy Program at LLNL

    SciTech Connect

    Bench, G.; Freeman, S.; Roberts, M.; Sideras-Haddad, E.

    1996-12-31

    Since initiation in mid 1994, a bioscience nuclear microscopy program at Livermore has enabled collaboration with bio-scientists on a variety of projects requiring quantitative elemental microanalysis. For microprobe analysis a combination of PIXE and STIM are typically used; respectively generating element distribution maps with micron scale spatial resolution, and projected densities and histological information with sub-micron spatial resolution. Current studies demonstrate the applicability of nuclear microscopy (particularly when combined with other analysis techniques) in environmental tracing, toxicology, carcinogenesis, and structural biology. The program currently uses {approximately}10 percent of the available time on a 10 MV tandem accelerator that is also applied to a variety of Accelerator Mass Spectrometry and other microprobe programs. The completion of a dedicated nuclear microprobe system, using a 5 SDH NEC 1.7 MV tandem accelerator and employing several energy dispersive x-ray detectors to improve x-ray counting rates, promises increased accelerator access, greater sample throughput and continued expansion of the program.

  17. Developing an orientation program.

    PubMed

    Edwards, K

    1999-01-01

    When the local area experienced tremendous growth and change, the radiology department at Maury Hospital in Columbia, Tennessee looked seriously at its orientation process in preparation for hiring additional personnel. It was an appropriate time for the department to review its orientation process and to develop a manual to serve as both a tool for supervisors and an ongoing reference for new employees. To gather information for the manual, supervisors were asked to identify information they considered vital for new employees to know concerning the daily operations of the department, its policies and procedures, the organizational structure of the hospital, and hospital and departmental computer systems. That information became the basis of the orientation manual, and provided an introduction to the hospital and radiology department; the structure of the organization; an overview of the radiology department; personnel information; operating procedures and computer systems; and various policies and procedures. With the manual complete, the radiology department concentrated on an orientation process that would meet the needs of supervisors who said they had trouble remembering the many details necessary to teach new employees. A pre-orientation checklist was developed, which contained the many details supervisors must handle between the time an employee is hired and arrives for work. The next step was the creation of a checklist for use by the supervisor during a new employee's first week on the job. A final step in the hospital's orientation program is to have each new employee evaluate the entire orientation process. That information is then used to update and revise the manual. PMID:10346648

  18. Advanced Launch Development Program status

    NASA Technical Reports Server (NTRS)

    Colgrove, Roger

    1990-01-01

    The Advanced Launch System is a joint NASA - Air Force program originally directed to define the concept for a modular family of launch vehicles, to continue development programs and preliminary design activities focused primarily on low cost to orbit, and to offer maturing technologies to existing systems. The program was restructed in the spring of 1990 as a result of funding reductions and renamed the Advanced Launch Development Program. This paper addresses the program's status following that restructuring and as NASA and the Air Force commence a period of deliberation over future space launch needs and the budgetary resources available to meet those needs. The program is currently poised to protect a full-scale development decision in the mid-1990's through the appropriate application of program resources. These resources are concentrated upon maintaining the phase II system contractor teams, continuing the Space Transportation Engine development activity, and refocusing the Advanced Development Program demonstrated activities.

  19. Revitalizing Undergraduate Programs: Curriculum Development.

    ERIC Educational Resources Information Center

    Ernst, Edward W.

    1989-01-01

    Discusses the Undergraduate Curriculum Development in Engineering program. Provides a short history of the program. Describes 10 curriculum projects ranging from engineering design to industry participation. Each program is encouraged to develop: analytical ability, ability to innovate and synthesize, integrating ability, and contextual…

  20. Game Changing Development Program Office

    NASA Video Gallery

    The Game Changing Development Program is a part of NASA's Space Technology Mission Directorate. The Program advances space technologies that may lead to entirely new approaches for the Agency's fut...

  1. MSFC nuclear thermal propulsion technology program

    NASA Technical Reports Server (NTRS)

    Swint, Shane

    1993-01-01

    Viewgraphs on non-nuclear materials assessment, nuclear thermal propulsion (NTP) turbomachinery technologies, and high temperature superconducting magnetic bearing technology are presented. The objective of the materials task is to identify and evaluate candidate materials for use in NTP turbomachinery and propellant feed system applications. The objective of the turbomachinery technology task is to develop and validate advanced turbomachinery technologies at the component and turbopump assembly levels. The objective of the high temperature superconductors (HTS) task is to develop and validate advanced technology for HTS passive magnetic/hydrostatic bearing.

  2. Computer program for afterheat temperature distribution for mobile nuclear power plant

    NASA Technical Reports Server (NTRS)

    Parker, W. G.; Vanbibber, L. E.

    1972-01-01

    ESATA computer program was developed to analyze thermal safety aspects of post-impacted mobile nuclear power plants. Program is written in FORTRAN 4 and designed for IBM 7094/7044 direct coupled system.

  3. RECENT ACTIVITIES AT THE CENTER FOR SPACE NUCLEAR RESEARCH FOR DEVELOPING NUCLEAR THERMAL ROCKETS

    SciTech Connect

    Robert C. O'Brien

    2001-09-01

    Nuclear power has been considered for space applications since the 1960s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors/ rocket-engines in the Rover/NERVA programs. However, changes in environmental laws may make the redevelopment of the nuclear rocket more difficult. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel form significantly different from NERVA may be needed to ensure public support. The Center for Space Nuclear Research (CSNR) is pursuing development of tungsten based fuels for use in a NTR, for a surface power reactor, and to encapsulate radioisotope power sources. The CSNR Summer Fellows program has investigated the feasibility of several missions enabled by the NTR. The potential mission benefits of a nuclear rocket, historical achievements of the previous programs, and recent investigations into alternatives in design and materials for future systems will be discussed.

  4. Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development

    SciTech Connect

    Jon Carmack

    2014-01-01

    The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Advanced nuclear fuels and materials development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Advanced Fuel Campaign (AFC).

  5. Followup audit of the cask development program

    SciTech Connect

    Not Available

    1994-03-15

    The Department of Energy is responsible for developing a system for the transportation and storage of spent nuclear fuel generated by utility companies. To carry out this responsibility, the Department of Energy established the Office of Civilian Radioactive Waste Management (Waste Management Office). The Waste Management office began development of a series of new shipping casks to transport the spent fuel. The purpose of this audit was to review the current development status of the cask designs; compare the original milestone dates to current milestone dates; and review the program funds that have been used to date on the development of these casks. The Office of Inspector General audited the cask development program in 1987. The audit report (DOE/IG-0244), recommended that program management establish minimum criteria that each cask must meet to qualify for further development funding. Our followup audit found that this recommendation had not been adequately implemented. As a result, the Waste Management office will spend an estimated $143 million on the cask development program and receive only two cask designs that were originally scheduled to cost $26 million. Moreover, it is not certain, at this time, whether those two cask designs will eventually receive the Nuclear Regulatory Commission certification. Historically, the program has experienced slippage in milestone dates and steady increases in total cost. Management generally agreed with our current recommendations to establish formal contingency plans to counter further delays, develop current baselines and schedules in sufficient detail to adequately control cask development schedules and costs, and reevaluate the current status of the casks under development for the purpose of justifying further development. Management has proposed actions to correct the milestone date slippages and continued growth in the total cost of the program.

  6. Developing a Collegiate Aquatics Program.

    ERIC Educational Resources Information Center

    Fawcett, Paul A.

    2001-01-01

    Presents suggestions for departments of health, physical education, and recreation that are planning to develop their own aquatics programs, focusing on: the prevalence of collegiate aquatics programs; course offerings in an aquatics minor; practicums and internships; graduate programs in aquatics; cross-disciplinary appeal; marketing the aquatics…

  7. The Future of the U.S. Nuclear Weapons Program

    NASA Astrophysics Data System (ADS)

    Brooks, Linton F.

    2007-03-01

    This paper will examine our plans for the future of the U.S. nuclear weapons program including efforts to ``transform'' the stockpile and supporting infrastructure. We proceed from the premise that the United States will need a safe, secure, and reliable nuclear deterrent for the foreseeable future. Moreover, the Stockpile Stewardship Program is working. Today's stockpile---comprised of legacy warheads left over from the Cold War---is safe and reliable. That said, we see increased risk, absent nuclear testing, in assuring the long-term safety and reliability of our current stockpile. Nor is today's nuclear weapons complex sufficiently ``responsive'' to fixing technical problems in the stockpile, or to potential adverse geopolitical change. Our task is to work to ensure that the U.S. nuclear weapons enterprise, including the stockpile and supporting infrastructure, meets long-term national security needs. Our approach is to develop and field replacement warheads for the legacy stockpile---so-called Reliable Replacement Warheads (RRW)---as a means to transform both the nuclear stockpile and supporting infrastructure.

  8. Final report to DOE: Matching Grant Program for the Penn State University Nuclear Engineering Program

    SciTech Connect

    Jack S. Brenizer, Jr.

    2003-01-17

    The DOE/Industry Matching Grant Program is designed to encourage collaborative support for nuclear engineering education as well as research between the nation's nuclear industry and the U.S. Department of Energy (DOE). Despite a serious decline in student enrollments in the 1980s and 1990s, the discipline of nuclear engineering remained important to the advancement of the mission goals of DOE. The program is designed to ensure that academic programs in nuclear engineering are maintained and enhanced in universities throughout the U.S. At Penn State, the Matching Grant Program played a critical role in the survival of the Nuclear Engineering degree programs. Funds were used in a variety of ways to support both undergraduate and graduate students directly. Some of these included providing seed funding for new graduate research initiatives, funding the development of new course materials, supporting new teaching facilities, maintenance and purchase of teaching laboratory equipment, and providing undergraduate scholarships, graduate fellowships, and wage payroll positions for students.

  9. Nuclear Data Activities in Support of the DOE Nuclear Criticality Safety Program

    SciTech Connect

    Westfall, R.M.; McKnight, R.D.

    2005-05-24

    The DOE Nuclear Criticality Safety Program (NCSP) provides the technical infrastructure maintenance for those technologies applied in the evaluation and performance of safe fissionable-material operations in the DOE complex. These technologies include an Analytical Methods element for neutron transport as well as the development of sensitivity/uncertainty methods, the performance of Critical Experiments, evaluation and qualification of experiments as Benchmarks, and a comprehensive Nuclear Data program coordinated by the NCSP Nuclear Data Advisory Group (NDAG).The NDAG gathers and evaluates differential and integral nuclear data, identifies deficiencies, and recommends priorities on meeting DOE criticality safety needs to the NCSP Criticality Safety Support Group (CSSG). Then the NDAG identifies the required resources and unique capabilities for meeting these needs, not only for performing measurements but also for data evaluation with nuclear model codes as well as for data processing for criticality safety applications. The NDAG coordinates effort with the leadership of the National Nuclear Data Center, the Cross Section Evaluation Working Group (CSEWG), and the Working Party on International Evaluation Cooperation (WPEC) of the OECD/NEA Nuclear Science Committee. The overall objective is to expedite the issuance of new data and methods to the DOE criticality safety user. This paper describes these activities in detail, with examples based upon special studies being performed in support of criticality safety for a variety of DOE operations.

  10. Solid amine development program

    NASA Technical Reports Server (NTRS)

    Lovell, J. S.

    1973-01-01

    A regenerable solid amine material to perform the functions of humidity control and CO2 removal for space shuttle type vehicle is reported. Both small scale and large scale testing have shown this material to be competitive, especially for the longer shuttle missions. However, it had been observed that the material off-gasses ammonia under certain conditions. This presents two concerns. The first, that the ammonia would contaminate the cabin atmosphere, and second, that the material is degrading with time. An extensive test program has shown HS-C to produce only trace quantities of atmospheric contaminants, and under normal extremes, to have no practical life limitation.

  11. Nuclear Energy Readiness Indicator Index (NERI): A benchmarking tool for assessing nuclear capacity in developing countries

    SciTech Connect

    Saum-Manning,L.

    2008-07-13

    Declining natural resources, rising oil prices, looming climate change and the introduction of nuclear energy partnerships, such as GNEP, have reinvigorated global interest in nuclear energy. The convergence of such issues has prompted countries to move ahead quickly to deal with the challenges that lie ahead. However, developing countries, in particular, often lack the domestic infrastructure and public support needed to implement a nuclear energy program in a safe, secure, and nonproliferation-conscious environment. How might countries become ready for nuclear energy? What is needed is a framework for assessing a country's readiness for nuclear energy. This paper suggests that a Nuclear Energy Readiness Indicator (NERI) Index might serve as a meaningful basis for assessing a country's status in terms of progress toward nuclear energy utilization under appropriate conditions. The NERI Index is a benchmarking tool that measures a country's level of 'readiness' for nonproliferation-conscious nuclear energy development. NERI first identifies 8 key indicators that have been recognized by the International Atomic Energy Agency as key nonproliferation and security milestones to achieve prior to establishing a nuclear energy program. It then measures a country's progress in each of these areas on a 1-5 point scale. In doing so NERI illuminates gaps or underdeveloped areas in a country's nuclear infrastructure with a view to enable stakeholders to prioritize the allocation of resources toward programs and policies supporting international nonproliferation goals through responsible nuclear energy development. On a preliminary basis, the indicators selected include: (1) demonstrated need; (2) expressed political support; (3) participation in nonproliferation and nuclear security treaties, international terrorism conventions, and export and border control arrangements; (4) national nuclear-related legal and regulatory mechanisms; (5) nuclear infrastructure; (6) the

  12. History of nuclear technology development in Japan

    NASA Astrophysics Data System (ADS)

    Yamashita, Kiyonobu

    2015-04-01

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

  13. History of nuclear technology development in Japan

    SciTech Connect

    Yamashita, Kiyonobu

    2015-04-29

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

  14. System model development for nuclear thermal propulsion

    SciTech Connect

    Walton, J.T.; Hannan, N.A.; Perkins, K.R.; Buksa, J.J.; Worley, B.A.; Dobranich, D.

    1992-10-01

    A critical enabling technology in the evolutionary development of nuclear thermal propulsion (NTP) is the ability to predict the system performance under a variety of operating conditions. Since October 1991, US (DOE), (DOD) and NASA have initiated critical technology development efforts for NTP systems to be used on Space Exploration Initiative (SEI) missions to the Moon and Mars. This paper presents the strategy and progress of an interagency NASA/DOE/DOD team for NTP system modeling. It is the intent of the interagency team to develop several levels of computer programs to simulate various NTP systems. An interagency team was formed for this task to use the best capabilities available and to assure appropriate peer review. The vision and strategy of the interagency team for developing NTP system models will be discussed in this paper. A review of the progress on the Level 1 interagency model is also presented.

  15. The TRIUMF nuclear structure program and TIGRESS

    SciTech Connect

    Garrett, P E; Andreyev, A; E.Austin, R A; Ball, G C; Bandyopadhyay, D; Becker, J A; Boston, A; Boston, H; Charkrawarthy, R S; Churchman, R; Cline, D; Cooper, R J; Cross, D; Dashdorj, D; Demand, G A; Dimmock, M R; Drake, T; Finlay, P; Gagnon, K; Gallant, A T; Green, K L; Grint, A N; Grinyer, G F; Hackman, G; Harkness, L J; Hayes, A B; Kanungo, R; Kulp, W D; Leach, K G; Lee, G; Leslie, J R; Maharaj, R; Martin, J P; Mattoon, C; Mills, W J; Morton, A C; Nelson, L; Newman, O; Nolan, P J; Padilla-Rodal, E; Pearson, C J; Phillips, A A; Porter-Peden, M; Ressler, J J; Ruiz, C; Sarazin, F; Schumaker, M A; Scraggs, D P; Strange, M T; Subramanian, M; Svensson, C E; Waddington, J C; Wan, J; Whitebeck, A; Williams, S J; Wood, J L; Wong, J C; Wu, C Y; Zganjar, E F

    2006-08-30

    The Isotope Separator and Accelerator (ISAC) facility located at the TRIUMF laboratory in Vancouver, Canada, is one of the world's most advanced ISOL-type radioactive ion beam facilities. An extensive {gamma}-ray spectroscopy program at ISAC is centered around two major research facilities: (1) the 8{pi} {gamma}-ray spectrometer for {beta}-delayed {gamma}-ray spectroscopy experiments with the low-energy beams from ISAC-I, and (2) the next-generation TRIUMF-ISAC Gamma-Ray Escape Suppressed Spectrometer (TIGRESS) for in-beam experiments with the accelerated radioactive ion beams. An overview of these facilities and recent results from the diverse program of nuclear structure and fundamental interaction studies they support is presented.

  16. Survey of Dynamic Simulation Programs for Nuclear Fuel Reprocessing

    SciTech Connect

    Troy J. Tranter; Daryl R. Haefner

    2008-06-01

    The absence of any industrial scale nuclear fuel reprocessing in the U.S. has precluded the necessary driver for developing the advanced simulation capability now prevalent in so many other industries. Modeling programs to simulate the dynamic behavior of nuclear fuel separations and processing were originally developed to support the US government’s mission of weapons production and defense fuel recovery. Consequently there has been little effort is the US devoted towards improving this specific process simulation capability during the last two or three decades. More recent work has been focused on elucidating chemical thermodynamics and developing better models of predicting equilibrium in actinide solvent extraction systems. These equilibrium models have been used to augment flowsheet development and testing primarily at laboratory scales. The development of more robust and complete process models has not kept pace with the vast improvements in computational power and user interface and is significantly behind simulation capability in other chemical processing and separation fields.

  17. System model development for nuclear thermal propulsion

    NASA Astrophysics Data System (ADS)

    Walton, James T.; Hannan, Nelson A.; Perkins, Ken R.; Buksa, John H.; Worley, Brian A.; Dobranich, Dean

    1992-08-01

    A critical enabling technology in the evolutionary development of nuclear thermal propulsion (NTP) is the ability to predict the system performance under a variety of operating conditions. This is crucial for mission analysis and for control subsystem testing as well as for the modeling of various failure modes. Performance must be accurately predicted during steady-state and transient operation, including startup, shutdown, and post operation cooling. The development and application of verified and validated system models has the potential to reduce the design, testing, and cost and time required for the technology to reach flight-ready status. Since Oct. 1991, the U.S. Department of Energy (DOE), Department of Defense (DOD), and NASA have initiated critical technology development efforts for NTP systems to be used on Space Exploration Initiative (SEI) missions to the Moon and Mars. This paper presents the strategy and progress of an interagency NASA/DOE/DOD team for NTP system modeling. It is the intent of the interagency team to develop several levels of computer programs to simulate various NTP systems. The first level will provide rapid, parameterized calculations of overall system performance. Succeeding computer programs will provide analysis of each component in sufficient detail to guide the design teams and experimental efforts. The computer programs will allow simulation of the entire system to allow prediction of the integrated performance. An interagency team was formed for this task to use the best capabilities available and to assure appropriate peer review.

  18. System model development for nuclear thermal propulsion

    NASA Technical Reports Server (NTRS)

    Walton, James T.; Hannan, Nelson A.; Perkins, Ken R.; Buksa, John H.; Worley, Brian A.; Dobranich, Dean

    1992-01-01

    A critical enabling technology in the evolutionary development of nuclear thermal propulsion (NTP) is the ability to predict the system performance under a variety of operating conditions. This is crucial for mission analysis and for control subsystem testing as well as for the modeling of various failure modes. Performance must be accurately predicted during steady-state and transient operation, including startup, shutdown, and post operation cooling. The development and application of verified and validated system models has the potential to reduce the design, testing, and cost and time required for the technology to reach flight-ready status. Since Oct. 1991, the U.S. Department of Energy (DOE), Department of Defense (DOD), and NASA have initiated critical technology development efforts for NTP systems to be used on Space Exploration Initiative (SEI) missions to the Moon and Mars. This paper presents the strategy and progress of an interagency NASA/DOE/DOD team for NTP system modeling. It is the intent of the interagency team to develop several levels of computer programs to simulate various NTP systems. The first level will provide rapid, parameterized calculations of overall system performance. Succeeding computer programs will provide analysis of each component in sufficient detail to guide the design teams and experimental efforts. The computer programs will allow simulation of the entire system to allow prediction of the integrated performance. An interagency team was formed for this task to use the best capabilities available and to assure appropriate peer review.

  19. Current Development of Nuclear Thermal Propulsion technologies at the Center for Space Nuclear Research

    SciTech Connect

    Robert C. O'Brien; Steven K. Cook; Nathan D. Jerred; Steven D. Howe; Ronald Samborsky; Daniel Brasuell

    2012-09-01

    Nuclear power and propulsion has been considered for space applications since the 1950s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors / rocket engines in the Rover/NERVA programs1. The Aerojet Corporation was the prime contractor for the NERVA program. Modern changes in environmental laws present challenges for the redevelopment of the nuclear rocket. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel composition that is significantly different from those of the NERVA project can be engineered; this may be needed to ensure public support and compliance with safety requirements. The Center for Space Nuclear Research (CSNR) is pursuing a number of technologies, modeling and testing processes to further the development of safe, practical and affordable nuclear thermal propulsion systems.

  20. Sister Lab Program Prospective Partner Nuclear Profile: Indonesia

    SciTech Connect

    Bissani, M; Tyson, S

    2006-12-14

    Indonesia has participated in cooperative technical programs with the IAEA since 1957, and has cooperated with regional partners in all of the traditional areas where nuclear science is employed: in medicine, public health (such as insect control and eradication programs), agriculture (e.g. development of improved varieties of rice), and the gas and oil industries. Recently, Indonesia has contributed significantly to the Reduced Enrichment Research and Training Reactor (RERTR) Program by conducting experiments to confirm the feasibility of Mo-99 production using high-density low enriched uranium (LEU) fuel, a primary goal of the RERTR Program. Indonesia's first research reactor, the TRIGA Mark II at Bandung, began operation in 1964 at 250 kW and was subsequently upgraded in 1971 to 1 MW and further upgraded in 2000 to 2 MW. This reactor was joined by another TRIGA Mark II, the 100-kW Kartini-PPNY at Yogyakarta, in 1979, and by the 30-MW G.A. Siwabessy multipurpose reactor in Serpong, which achieved criticality in July 1983. A 10-MW radioisotope production reactor, to be called the RPI-10, also was proposed for construction at Serpong in the late 1990s, but the project apparently was not carried out. In the five decades since its nuclear research program began, Indonesia has trained a cadre of scientific and technical staff who not only operate and conduct research with the current facilities, but also represent the nucleus of a skilled labor pool to support development of a nuclear power program. Although Indonesia's previous on-again, off-again consideration of nuclear power has not gotten very far in the past, it now appears that Indonesia again is giving serious consideration to beginning a national nuclear energy program. In June 2006, Research and Technology Minister Kusmayanto Kadiman said that his ministry was currently putting the necessary procedures in place to speed up the project to acquire a nuclear power plant, indicating that, ''We will need around

  1. Development costs for a nuclear electric propulsion stage.

    NASA Technical Reports Server (NTRS)

    Mondt, J. F.; Prickett, W. Z.

    1973-01-01

    Development costs are presented for an unmanned nuclear electric propulsion (NEP) stage based upon a liquid metal cooled, in-core thermionic reactor. A total of 120 kWe are delivered to the thrust subsystem which employs mercury ion engines for electric propulsion. This study represents the most recent cost evaluation of the development of a reactor power system for a wide range of nuclear space power applications. These include geocentric, and outer planet and other deep space missions. The development program is described for the total NEP stage, based upon specific development programs for key NEP stage components and subsystems.

  2. Historically Black Colleges and Universities Nuclear Energy Training Program: Summary of program activities, fiscal year 1986

    SciTech Connect

    Not Available

    1987-04-27

    The Historically Black Colleges and Universities Nuclear Energy Training (HBCU NET) Program, funded by DOE, Office of Nuclear Energy and administered by ORAU, began in February 1984. The program provides support for training, study, research participation, and academic enrichment of students and faculty at designated HBCUs in nuclear science, nuclear engineering, and other nuclear-related technologes and disciplines. The program is composed of undergraduate scholarships, graduate fellowships, student and faculty research participation, and an annual student training institute.

  3. Robotics development programs overview

    SciTech Connect

    Heckendorn, F.M.

    1990-11-01

    This paper discusses the applications of robotics at the Westinghouse Savannah River Site. The Savannah River Laboratory (SRL) continues to provide support to the Savannah River Site (SRS) in many areas of Robotics and Remote Vision. An overview of the current and near term future developments are presented. The driving forces for Robotics and Vision developments at SRS include the classic reasons for industrial robotics installation (i.e. repetitive and undesirable jobs) and those reasons related to radioactive environments. Protection of personnel from both radiation and radioactive contamination benefit greatly from both Robotics and Telerobotics. Additionally, the quality of information available from remote locations benefits greatly from the ability to visually monitor and remotely sense. The systems discussed include a glovebox waste handling and bagout robot, a shielded cells robot for radioactive waste sample transfer, waste handling gantry robots, a two armed master/slave manipulator as an attachment to a gantry robot, navigation robot research/testing, demonstration of the mobile underwater remote cleaning and inspection device, a camera deployment robot to support remote crane operations and for deployment of radiation sensors directly over a hazardous site, and demonstration of a large mobile robot for high radiation environments. Development of specialized and limited life vision/viewing systems for hazardous environments is also discussed.

  4. Recommendations for quality assurance programs in nuclear medicine facilities. Radiation recommendations series

    SciTech Connect

    Segal, P.; Hamilton, D.R.

    1984-10-01

    The publication provides the elements that should be considered by nuclear medicine facilities to improve their existing programs or develop new quality assurance programs. The important administrative aspects of quality assurance programs are stressed. Each facility is encouraged to adopt those elements of the recommended program that are appropriate to its individual needs and resources.

  5. NCG turbocompressor development program

    SciTech Connect

    Nichols, K.E.

    1997-12-31

    Barber-Nichols, Pacific Gas and Electric and UNOCAL as an industry group applied for a DOE grant under the GTO to develop a new type of compressor that could be used to extract non-condensable gas (NCG) from the condensers of geothermal power plants. This grant (DE-FG07-951A13391) was awarded on September 20, 1995. The installation and startup of the turbocompressor at the PG&E Geysers Unit 11 is covered by this paper. The turbocompressor has operated several days at 17000rpm while the plant was producing 50 to 70 MW.

  6. Environmental awareness program development

    NASA Technical Reports Server (NTRS)

    Steinhauer, David A.

    1995-01-01

    Work this summer in the Office of Safety, Environment, and Mission Assurance began with a review of current initiatives and environmental projects at the Langley Research Center (LaRC). This involved researching many of the documents on file which detail problems which have occurred as well as various approaches which have been used to address these problems. A large portion of the time was spent interviewing and working with each of the engineers, industrial hygienists and other professionals connected with the Office of Environmental Engineering. A few of the projects I worked on include: Researching environmental compliance, and pollution prevention efforts; touring many of the facilities at LaRC to observe the environmental efforts in the work place; researching equipment needs for the recycling/reclamation center; writing scripts for in-house training videos; working with the video production department to produce a training video; developing e-mail distribution list; developing environmental coordinator's database; and working with others to research logistics of recycling and waste minimization efforts.

  7. Nanosatellite Propulsion Development Program

    NASA Technical Reports Server (NTRS)

    Gagosian, J. S.; Rhee, M. S.; Zakrzwski, C. M.

    1999-01-01

    Earth-orbiting nanosatellite constellations are a unique and exciting means toward fulfilling part of the mission of the Goddard Space Flight Center (GSFC). These constellations, which may consist of several hundred 10-kg spacecraft, present unique challenges in the area of propulsion. Many mission concepts require significant delta-v and attitude control capability to reside in the nanosatellites. In response to requirements from mission feasibility studies, such as the Magnetospheric Constellation study, the GSFC has initiated industry and government partnerships to develop enabling propulsion technologies. The largest challenge has been to meet the power constraints of nanosatellites. These power issues, combined with the high thrust required by many of the missions studied, have led the GSFC to concentrate its efforts on chemical propulsion technology. Electric propulsion technologies capable of performing efficiently at very low power are also of interest to the GSFC as potential candidates for nanosatellite formation flying missions. This paper provides the status of specific industrial or government partnerships undertaken by the GSFC to develop nano/micro propulsion components. Three specific technologies are described in detail: 1) Nanosatellite Solid Rocket Motor Prototype 2) Ultra-Low-Power Cold Gas Thruster for Spin-Axis Precession 3) Micro-Machined Solid-Propellant Gas Generators.

  8. Reliability program requirements for Space and Terrestrial Nuclear Power Systems

    SciTech Connect

    Not Available

    1982-10-01

    The objectives of the reliability program requirements described in this report are (1) to provide contractors with an outline of the reliability requirements established by the Department of Energy (DOE) in the areas of design, development, production, testing, and acceptance of space and terrestrial nuclear systems hardware, and (2) to guide the contractor in meeting these requirements. This publication or particular portions of it is applicable as specified in the contract. Whether the contractors/subcontractors are subject to all the requirements or only to part of them will be specified by contract, program letter, or by the contract statement-of-work.

  9. Automotive Stirling Engine Development Program

    NASA Technical Reports Server (NTRS)

    Allen, M. (Editor)

    1980-01-01

    Progress is reported in the following: the Stirling reference engine system design; components and subsystems; F-40 baseline Stirling engine installation and test; the first automotive engine to be built on the program; computer development activities; and technical assistance to the Government. The overall program philosophy is outlined, and data and results are given.

  10. Nuclear Education and Training Programs of Potential Interest to Utilities.

    ERIC Educational Resources Information Center

    Atomic Energy Commission, Washington, DC.

    This compilation of education and training programs related to nuclear applications in electric power generation covers programs conducted by nuclear reactor vendors, public utilities, universities, technical institutes, and community colleges, which were available in December 1968. Several training-program consultant services are also included.…

  11. Developing an Undergraduate Program in Energy Systems

    NASA Astrophysics Data System (ADS)

    Fanchi, John

    2010-10-01

    Texas Christian University (TCU) is developing an undergraduate program in engineering that prepares students to become engineers with an emphasis in energy systems. Courses in the program include an overview of energy in society that is suitable for the general student population; a technical overview of traditional energy (coal, oil and gas), nuclear energy, and renewable energy; and courses that cover more specialized energy topics. Students participating in this program will improve their understanding of energy systems; be introduced to outstanding scientific and engineering problems; learn about the role of energy in a global and societal context; and evaluate contemporary issues associated with energy. The energy systems curriculum will improve student understanding of activities that are a major component of the economy. As engineering students graduate with an energy systems emphasis, they will take their places in society with a much more sophisticated understanding of energy-related issues affecting their community. This talk will present the status of the new program.

  12. Study of a spherical torus based volumetric neutron source for nuclear technology testing and development. Final report of a scientific research supported by the USDOE/SBIR program

    SciTech Connect

    E.T. Cheng, et al.

    1999-06-01

    A plasma based, deuterium and tritium (DT) fueled, volumetric 14 MeV neutron source (VNS) has been considered as a possible facility to support the development of the demonstration fusion power reactor (DEMO). It can be used to test and develop necessary fusion blanket and divertor components and provide sufficient database, particularly on the reliability of nuclear components necessary for DEMO. The VNS device complement to ITER by reducing the cost and risk in the development of DEMO. A low cost, scientifically attractive, and technologically feasible volumetric neutron source based on the spherical torus (ST) concept has been conceived. The ST-VNS, which has a major radius of 1.07 m, aspect ratio 1.4, and plasma elongation 3, can produce a neutron wall loading from 0.5 to 5 MW/m{sup 2} at the outboard test section with a modest fusion power level from 38 to 380 MW. It can be used to test necessary nuclear technologies for fusion power reactor and develop fusion core components include divertor, first wall, and power blanket. Using staged operation leading to high neutron wall loading and optimistic availability, a neutron fluence of more than 30 MW-y/m{sup 2} is obtainable within 20 years of operation. This will permit the assessments of lifetime and reliability of promising fusion core components in a reactor relevant environment. A full scale demonstration of power reactor fusion core components is also made possible because of the high neutron wall loading capability. Tritium breeding in such a full scale demonstration can be very useful to ensure the self-sufficiency of fuel cycle for a candidate power blanket concept.

  13. Lunar exploration rover program developments

    SciTech Connect

    Klarer, P.R.

    1993-09-01

    The Robotic All Terrain Lunar Exploration Rover (RATLER) design concept began at Sandia National Laboratories in late 1991 with a series of small, proof-of-principle, working scale models. The models proved the viability of the concept for high mobility through mechanical simplicity, and eventually received internal funding at Sandia National Laboratories for full scale, proof-of-concept prototype development. Whereas the proof-of-principle models demonstrated the mechanical design`s capabilities for mobility, the full scale proof-of-concept design currently under development is intended to support field operations for experiments in telerobotics, autonomous robotic operations, telerobotic field geology, and advanced man-machine interface concepts. The development program`s current status is described, including an outline of the program`s work over the past year, recent accomplishments, and plans for follow-on development work.

  14. Developing an Operator Training Program.

    ERIC Educational Resources Information Center

    Wubbena, Robert L.

    1978-01-01

    The study reported is a nationwide comprehensive analysis of the availability of training and the problems associated with the development of effective state programs for operators of water supply and wastewater facilities. (CS)

  15. The nuclear frontier; Cornell's program of basic and applied research

    SciTech Connect

    Clark, D.D. . Dept. of Nuclear Science and Engineering)

    1992-01-01

    This paper discusses the Program in Nuclear Science and Engineering at Cornell, an interdisciplinary field that encompasses a wide range of research. Some faculty members and graduate students are working on the basic physics of nuclei, plasmas, and atoms, while other are investigating the interaction of radiation with matter and the basic mechanisms of radiation-induced failure in microelectronic devices. Some are developing new research techniques based on nuclear and atomic interactions, and others are adapting nuclear methods such as activation analysis to research in geology, biology, and archaeology. Some are investigating advanced types of ion and electron beams, while yet others are improving the generation of power from fission and seeking to generate it from fusion.

  16. Update on DOE’s Nuclear Energy University Program

    SciTech Connect

    M. J. Lambregts

    2009-04-01

    The Center for Advanced Energy Studies (CAES) Nuclear Energy University Program Office assists the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) by administering its University Program. To promote accountable relationships between universities and the TIOs/TDOs, a process was designed and administered which includes two competitive Requests for Proposals (RFP’s) and two FOAs in the following areas: (1)Research and Development Grants, (2)Infrastructure improvement, and (3)Scholarships and Fellowships. NEUP will also host periodic reviews of university mission-specific R&D that document progress, reinforce accountability, and assess return on investment; sponsor workshops that inform universities of the Department’s research needs to facilitate continued alignment of university R&D with NE missions; and conduct communications activities that foster stakeholder trust, serve as a catalyst for accomplishing NEUP objectives, and provide national visibility of NEUP activities and accomplishments. Year to date efforts to achieve these goals will be discussed.

  17. Kodak AMSD Mirror Development Program

    NASA Technical Reports Server (NTRS)

    Matthews, Gary; Dahl, Roger; Barrett, David; Bottom, John; Russell, Kevin (Technical Monitor)

    2002-01-01

    The Advanced Mirror System Demonstration Program is developing minor technology for the next generation optical systems. Many of these systems will require extremely lightweight and stable optics due to the overall size of the primary mirror. These segmented, deployable systems require new technology that AMSD is developing. The on-going AMSD program is a critical enabler for Next Generation Space Telescope (NGST) which will start in 2002. The status of Kodak's AMSD mirror and future plans will be discussed with respect to the NGST program.

  18. Infrastructure development assistance modeling for nuclear power plant

    SciTech Connect

    Park, J. H.; Hwang, K.; Park, K. M.; Kim, S. W.; Lee, S. M.

    2012-07-01

    The purpose of this paper is to develop a model, a general frame to be utilized in assisting newcomer countries to start a nuclear power program. A nuclear power plant project involves technical complexity and high level of investment with long duration. Considering newcomers are mostly developing countries that lack the national infrastructure, key infrastructure issues may constitute the principal constraints to the development of a nuclear power program. In this regard, it is important to provide guidance and support to set up an appropriate infrastructure when we help them with the first launch of nuclear power plant project. To date, as a sole nuclear power generation company, KHNP has been invited many times to mentor or assist newcomer countries for their successful start of a nuclear power program since Republic of Korea is an exemplary case of a developing country which began nuclear power program from scratch and became a major world nuclear energy country in a short period of time. Through hosting events organized to aid newcomer countries' initiation of nuclear power projects, difficulties have been recognized. Each event had different contents according to circumstances because they were held as an unstructured and one-off thing. By developing a general model, we can give more adequate and effective aid in an efficient way. In this paper, we created a model to identify necessary infrastructures at the right stage, which was mainly based on a case of Korea. Taking into account the assistance we received from foreign companies and our own efforts for technological self-reliance, we have developed a general time table and specified activities required to do at each stage. From a donor's perspective, we explored various ways to help nuclear infrastructure development including technical support programs, training courses, and participating in IAEA technical cooperation programs on a regular basis. If we further develop the model, the next task would be to

  19. Potential criminal adversaries of nuclear programs: a portrait

    SciTech Connect

    Jenkins, B.M.

    1980-07-01

    This paper examines the possibility that terrorists or other kinds of criminals might attempt to seize or sabotage a nuclear facility, steal nuclear material, or carry out other criminal activities in the nuclear domain which has created special problems for the security of nuclear programs. This paper analyzes the potential threat. Our tasks was to describe the potential criminal adversary, or rather the spectrum of potential adversaries who conceivably might carry out malevolent criminal actions against nuclear programs and facilities. We were concerned with both the motivations as well as the material and operational capabilities likely to be displayed by various categories of potential nuclear adversaries.

  20. Perspectives of Nuclear Energy for Human Development

    SciTech Connect

    Rouyer, Jean-Loup

    2002-07-01

    In this period of expectation and short term viewing, everyone has difficulties to draw long term perspectives. A positive global world vision of sustainable development gives confidence in the preparation of energy future in a moving international context. This presentation proposes to share such a long term vision inside which energy scenarios for nuclear development take their right place. It is founded on a specific analysis of an index of countries global development which is representative of a country efficiency. Human Development Index (HDI) is a composite international index recommended and calculated every year since 1990 by the United Nations Development Program (UNDP). This index is still very dependent of GNP, which ignores the disparities of revenues inside the country. That is why a Country Efficiency Index (CEI) has been defined to better represent the capacity of a country to utilize its resources for welfare of its inhabitants. CEI is a ratio of health and education levels to the capacity of the country to satisfy this welfare. CEI has been calculated for the 70 more populated countries of the world for the year 1997. CEI calculation has been also performed for European Countries, the United States, China and India on the period from 1965 to 1997. It is observed a growth of CEI. for France from 0.6 to 0.78, and from 0.7 to 0.85 for USA. In 1997, CEI of China was 0.46, and 0.38 for India. This index is a good tool to measure the progression of development of the countries and the related energy needs. Comparison of the evolutions of CEI of these different countries shows a similar positive trend with some delay between OECD countries and China or India. A positive scenario for the future is based on a similar curve for these developing countries with learning effect which produces development with less energy consumption. This simulation results however in energy needs that exceed fossil fuel today available resources in 2070. Ultimate fossil

  1. A review of the Los Alamos effort in the development of nuclear rocket propulsion

    SciTech Connect

    Durham, F.P.; Kirk, W.L.; Bohl, R.J.

    1991-01-01

    This paper reviews the achievements of the Los Alamos nuclear rocket propulsion program and describes some specific reactor design and testing problems encountered during the development program along with the progress made in solving these problems. The relevance of these problems to a renewed nuclear thermal rocket development program for the Space Exploration Initiative (SEI) is discussed. 11 figs.

  2. Nuclear Technology Series. Nuclear Reactor (Plant) Operator Trainee. A Suggested Program Planning Guide. Revised June 80.

    ERIC Educational Resources Information Center

    Center for Occupational Research and Development, Inc., Waco, TX.

    This program planning guide for a two-year postsecondary nuclear reactor (plant) operator trainee program is designed for use with courses 1-16 of thirty-five in the Nuclear Technology Series. The purpose of the guide is to describe the nuclear power field and its job categories for specialists, technicians and operators; and to assist planners,…

  3. Developing a Leadership Program Trajectory.

    PubMed

    Bleich, Michael R

    2016-06-01

    From a program development perspective, leadership goals and content are best developed over time, with an aim to help nurses mature into their capacity to lead. Leadership often is encouraged in new nurses or in those who seek management positions. Professional development educators are encouraged to enact leadership development across a career continuum. J Contin Educ Nurs. 2016;47(6):250-252. PMID:27232221

  4. Nuclear electric propulsion for planetary science missions: NASA technology program planning

    NASA Technical Reports Server (NTRS)

    Doherty, Michael P.

    1993-01-01

    This paper presents the status of technology program planning to develop those Nuclear Electric Propulsion technologies needed to meet the advanced propulsion system requirements for planetary science missions in the next century. The technology program planning is based upon technologies with significant development heritage: ion electric propulsion and the SP-100 space nuclear power technologies. Detailed plans are presented for the required ion electric propulsion technology development and demonstration. Closer coordination between space nuclear power and space electric propulsion technology programs is a necessity as technology plans are being further refined in light of NEP concept definition and possible early NEP flight activities.

  5. China's Nuclear Power Program: Options for the US

    SciTech Connect

    Suttmeier, R.P.

    1985-01-01

    The issue of American nuclear cooperation with the People's Republic of China is examined with regards to political relations, commercial benefits to the United States, and nonproliferation. China's interest in nuclear power is examined, and its nuclear program is briefly reviewed from the 1950's to present. China's international nuclear relations with other countries are discussed, and implications for the United States examined, particularly with regards to China's intentions toward nuclear proliferation, danger of diversion of material for nuclear weapons, use of pressurized water reactor technology for Chinese naval reactors, and the terms of the nuclear cooperation agreement. (LEW)

  6. NASA Procurement Career Development Program

    NASA Technical Reports Server (NTRS)

    1987-01-01

    The NASA Procurement Career Development Program establishes an agency-wide framework for the management of career development activity in the procurement field. Within this framework, installations are encouraged to modify the various components to meet installation-specific mission and organization requirements. This program provides a systematic process for the assessment of and planning for the development, training, and education required to increase the employees' competence in the procurement work functions. It includes the agency-wide basic knowledge and skills by career field and level upon which individual and organizational development plans are developed. Also, it provides a system that is compatible with other human resource management and development systems, processes, and activities. The compatibility and linkage are important in fostering the dual responsibility of the individual and the organization in the career development process.

  7. Business Development Executive (BDE) Program

    SciTech Connect

    Rice, E.J. "Woody"; Frederick, W. James

    2005-12-05

    The IPST BDE (Institute of Paper Science and Technology Business Development Executive) program was initiated in 1997 to make the paper industry better aware of the new manufacturing technologies being developed at IPST for the U.S. pulp and paper industry's use. In April 2000, the BDE program management and the 20 BDEs, all retired senior level industry manufacturing and research executives, were asked by Ms. Denise Swink of OIT at DOE to take the added responsibility of bringing DOE developed energy conservation technology to the paper industry. This project was funded by a DOE grant of $950,000.

  8. Commercial Crew Development Program Overview

    NASA Technical Reports Server (NTRS)

    Russell, Richard W.

    2011-01-01

    NASA's Commercial Crew Development Program is designed to stimulate efforts within the private sector that will aid in the development and demonstration of safe, reliable, and cost-effective space transportation capabilities. With the goal of delivery cargo and eventually crew to Low Earth Orbit (LEO) and the International Space Station (ISS) the program is designed to foster the development of new spacecraft and launch vehicles in the commercial sector. Through Space Act Agreements (SAAs) in 2011 NASA provided $50M of funding to four partners; Blue Origin, The Boeing Company, Sierra Nevada Corporation, and SpaceX. Additional, NASA has signed two unfunded SAAs with ATK and United Space Alliance. This paper will give a brief summary of these SAAs. Additionally, a brief overview will be provided of the released version of the Commercial Crew Development Program plans and requirements documents.

  9. Automotive Stirling engine development program

    NASA Technical Reports Server (NTRS)

    Ernst, W.; Richey, A.; Farrell, R.; Riecke, G.; Smith, G.; Howarth, R.; Cronin, M.; Simetkosky, M.; Meacher, J.

    1986-01-01

    This is the ninth Semiannual Technical Progress Report prepared under the Automotive Stirling Engine Development Program. It covers the twenty-eighth and twenty-ninth quarters of activity after award of the contract. Quarterly Technical Progress Reports related program activities from the first through the thirteenth quarters; thereafter, reporting was changed to a Semiannual format. This report summarizes the study of higher-power kinematic Stirling engines for transportation use, development testing of Mod I Stirling engines, and component development activities. Component development testing included successful conical fuel nozzle testing and functional checkout of Mod II controls and auxiliaries on Mod I engine test beds. Overall program philosophy is outlined and data and test results are presented.

  10. DOE (Department of Energy)-Nuclear Energy Standards Program annual assessment, FY 1990

    SciTech Connect

    Williams, D.L. Jr.

    1990-11-01

    To meet the objectives of the programs funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs, the Performance Assurance Project Office (PAPO) administers a nuclear standards program and related activities and fosters the development and application of standards. This standards program is carried out in accordance with the principles in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980. The purposes of this effort, as set forth in three subtasks, are to (1) manage the NE Standards Program, (2) manage the development and maintenance of NE standards, and (3) operate an NE Standards Information Program. This report assesses the Performance Assurance Project Office (PAPO) activities in terms of the objectives of the Department of Energy-Nuclear Energy (DOE-NE) funded programs. To meet these objectives, PAPO administers a nuclear standards program and related activities and fosters the development and application of standards. This task is carried out in accordance with the principles set forth in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980, and DOE memorandum, Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs, March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. 1 tab. (JF)

  11. Environmental Education and Development Program

    SciTech Connect

    Not Available

    1994-03-01

    The Environmental Education and Development Program is a component on the effort to accomplish the Office of Environmental Restoration and Waste Management`s (EM) goal of environmental compliance and cleanup of the 1989 inventory of inactive DOE sites and facilities by the year 2019. Education and Development programs were designed specifically to stimulate the knowledge and workforce capability necessary to achieve EM goals while contributing to DOE`s overall goal of increasing scientific and technical literacy and competency. The primary implementation criterion for E&D activities involved a focus on programs and projects that had both immediate and long-range leveraging effects on infrastructure. This focus included programs that yielded short term results (one to five years), as well as long-term results, to ensure a steady supply of appropriately trained and educated human resources, including women and minorities, to meet EM`s demands.

  12. The solid-core heat-exchanger nuclear rocket program

    SciTech Connect

    Malenfant, R.E.

    1994-12-31

    As measured by the results of its accomplishments, the nuclear rocket program was a success. Why, then, was it cancelled? In my opinion, the cancellation resulted from the success of the Apollo program. President Kennedy declared that putting a man on the moon by 1969 would be a national objective. Upon the Apollo program`s completion, space spectaculars lost their attraction, and the manned exploration of Mars, which could have been accomplished with nuclear rockets, was shelved. Perhaps another generation of physicists and engineers will experience the thrill and satisfaction of participating in a nuclear-propulsion-based program for space exploration in decades to come.

  13. Development of Secure and Sustainable Nuclear Infrastructure in Emerging Nuclear Nations Such as Vietnam

    SciTech Connect

    Shipwash, Jacqueline L; Kovacic, Donald N

    2008-01-01

    Infrastructure Preparedness and Vietnam Jacqueline L. Shipwash and Donald N. Kovacic (shipwashjl@ornl.gov, 865-241-9129, and kovacicdn@ornl.gov, 865-576-1459) Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 The global expansion of nuclear energy will require international cooperation to ensure that nuclear materials, facilities, and sensitive technologies are not diverted to non-peaceful uses. Developing countries will require assistance to ensure the effective regulation, management, and operation of their nuclear programs to achieve best practices in nuclear nonproliferation. A developing nation has many hurdles to pass before it can give assurances to the international community that it is capable of implementing a sustainable nuclear energy program. In August of this year, the U.S. Department of Energy and the Ministry of Science and Technology of the Socialist Republic of Vietnam signed an arrangement for Information Exchange and Cooperation on the Peaceful Uses of Nuclear Energy. This event signals an era of cooperation between the U.S. and Vietnam in the area of nuclear nonproliferation. This paper will address how DOE is supporting the development of secure and sustainable infrastructures in emerging nuclear nations such as Vietnam.

  14. Nuclear waste treatment program: Annual report for FY 1987

    SciTech Connect

    Brouns, R.A.; Powell, J.A.

    1988-09-01

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs.

  15. Report of the President's Blue Ribbon Task Group on Nuclear Weapons Program Management

    SciTech Connect

    Not Available

    1985-07-01

    The President established the Blue Ribbon Task Group on Nuclear Weapons Program Management at the direction of the Congress to address fiscal accountability and discipline in the nation's nuclear weapons program. The Task Group was asked to ''examine the procedures used by DOD and DOE in establishing requirements for, and providing resources for, the research, development, testing, production, surveillance, and retirement of nuclear weapons,'' and to recommend any needed change in coordination, budgeting, or management procedures. The Task Group was also asked to address ''whether DOD should assume the responsibility for funding current DOE weapon activities and material production programs.'' The Task Group found that the present relationship between DOD and DOE for managing the nuclear weapons program is sound. Accordingly, the Task Group sought a process for improving the integrated determination of nuclear weapon requirements and the management of nuclear weapon production.

  16. Leadership Development for Program Directors

    PubMed Central

    Bing-You, Robert; Wiltshire, Whitney; Skolfield, Jenny

    2010-01-01

    Background Residency program directors have increasingly challenging roles, but they may not be receiving adequate leadership development. Objective To assess and facilitate program directors' leadership self-awareness and development at a workshop retreat. Methods At our annual program director retreat, program directors and associate program directors from a variety of specialties completed the Thomas-Kilmann Conflict Mode Instrument (TKI), which evaluates an individual's behavior in conflict situations, and the Hersey-Blanchard Situational Leadership (HBSL) model, which measures individuals' preferred leadership style in working with followers. Participants received their results during the retreat and discussed their leadership style results in the context of conflict situations experienced in the past. An online survey was distributed 3 weeks after the retreat to assess participant satisfaction and to determine whether participants would make changes to their leadership styles. Results Seventeen program directors attended the retreat and completed the tools. On the TKI, 47% preferred the Compromising mode for handling conflict, while 18% preferred either the Avoiding or Accommodating modes. On the HBSL, 71% of program directors preferred a Coaching leadership style. Ninety-one percent of postretreat-survey respondents found the leadership tools helpful and also thought they had a better awareness of their conflict mode and leadership style preferences. Eighty-two percent committed to a change in their leadership behaviors in the 6 months following the retreat. Conclusions Leadership tools may be beneficial for promoting the professional development of program directors. The TKI and HBSL can be used within a local retreat or workshop as we describe to facilitate positive leadership-behavior changes. PMID:22132267

  17. Nuclear data needs for application in nuclear criticality safety programs

    SciTech Connect

    Leal, L.C.; Westfall, R.M.; Jordan, W.C.; Wright, R.Q.

    1995-09-01

    In nuclear criticality safety applications, a number of important uncertainties have to be addressed to establish the required criticality safety margin of a nuclear system. One source of these uncertainties is the basic nuclear data used to calculate the effective multiplication factor of the system. Before criticality safety calculations are performed, the bias and uncertainties of the codes and cross sections that are used must be determined. Cross-section data are measured, evaluated, and tested prior to their inclusion in nuclear data libraries. Traditionally, nuclear data evaluations are performed to support the analysis and design of thermal and fast reactors. The neutron spectra characteristic of the thermal and fast systems used for data testing are predominantly in the low- and high-energy ranges, with a relatively minor influence from the intermediate-energy range. In the area of nuclear criticality safety, nuclear systems involving spent fuel elements from reactors can lead to situations very different from those most commonly found in reactor analysis and design. These systems are not limited to thermal or fast neutron spectra and may have their most significant influence from the intermediate energy range. This requires extending the range of applicability of the nuclear data evaluation beyond thermal and fast systems. The aim here is to focus on the evaluated nuclear data pertaining to applications in nuclear criticality safety.

  18. Nuclear Waste Programs semiannual progress report, April--September 1992

    SciTech Connect

    Bates, J.K.; Bradley, C.R.; Buck, E.C.

    1994-05-01

    This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period April--September 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  19. Nuclear waste programs; Semiannual progress report, October 1991--March 1992

    SciTech Connect

    Bates, J.K.; Bradley, C.R.; Buck, E.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Finn, P.A.; Gerding, T.J.; Hoh, J.C.

    1993-11-01

    This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1991-March 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories

  20. Attracting students to nuclear careers: INPO educational assistance program

    SciTech Connect

    Dunkle, M.

    1981-10-01

    The utility industry is responding to a manpower shortage of 2000 at nuclear plants with a concerted analysis of regional training centers and educational assistance programs through the Institute of Nuclear Power Operations (INPO). University support and cooperation are generally strong. The INPO program includes undergraduate- and graduate-level scholarships and fellowships. (DCK)

  1. Nuclear Engine System Simulation (NESS). Volume 1: Program user's guide

    NASA Astrophysics Data System (ADS)

    Pelaccio, Dennis G.; Scheil, Christine M.; Petrosky, Lyman J.

    1993-03-01

    A Nuclear Thermal Propulsion (NTP) engine system design analysis tool is required to support current and future Space Exploration Initiative (SEI) propulsion and vehicle design studies. Currently available NTP engine design models are those developed during the NERVA program in the 1960's and early 1970's and are highly unique to that design or are modifications of current liquid propulsion system design models. To date, NTP engine-based liquid design models lack integrated design of key NTP engine design features in the areas of reactor, shielding, multi-propellant capability, and multi-redundant pump feed fuel systems. Additionally, since the SEI effort is in the initial development stage, a robust, verified NTP analysis design tool could be of great use to the community. This effort developed an NTP engine system design analysis program (tool), known as the Nuclear Engine System Simulation (NESS) program, to support ongoing and future engine system and stage design study efforts. In this effort, Science Applications International Corporation's (SAIC) NTP version of the Expanded Liquid Engine Simulation (ELES) program was modified extensively to include Westinghouse Electric Corporation's near-term solid-core reactor design model. The ELES program has extensive capability to conduct preliminary system design analysis of liquid rocket systems and vehicles. The program is modular in nature and is versatile in terms of modeling state-of-the-art component and system options as discussed. The Westinghouse reactor design model, which was integrated in the NESS program, is based on the near-term solid-core ENABLER NTP reactor design concept. This program is now capable of accurately modeling (characterizing) a complete near-term solid-core NTP engine system in great detail, for a number of design options, in an efficient manner. The following discussion summarizes the overall analysis methodology, key assumptions, and capabilities associated with the NESS presents an

  2. Nuclear Engine System Simulation (NESS). Volume 1: Program user's guide

    NASA Technical Reports Server (NTRS)

    Pelaccio, Dennis G.; Scheil, Christine M.; Petrosky, Lyman J.

    1993-01-01

    A Nuclear Thermal Propulsion (NTP) engine system design analysis tool is required to support current and future Space Exploration Initiative (SEI) propulsion and vehicle design studies. Currently available NTP engine design models are those developed during the NERVA program in the 1960's and early 1970's and are highly unique to that design or are modifications of current liquid propulsion system design models. To date, NTP engine-based liquid design models lack integrated design of key NTP engine design features in the areas of reactor, shielding, multi-propellant capability, and multi-redundant pump feed fuel systems. Additionally, since the SEI effort is in the initial development stage, a robust, verified NTP analysis design tool could be of great use to the community. This effort developed an NTP engine system design analysis program (tool), known as the Nuclear Engine System Simulation (NESS) program, to support ongoing and future engine system and stage design study efforts. In this effort, Science Applications International Corporation's (SAIC) NTP version of the Expanded Liquid Engine Simulation (ELES) program was modified extensively to include Westinghouse Electric Corporation's near-term solid-core reactor design model. The ELES program has extensive capability to conduct preliminary system design analysis of liquid rocket systems and vehicles. The program is modular in nature and is versatile in terms of modeling state-of-the-art component and system options as discussed. The Westinghouse reactor design model, which was integrated in the NESS program, is based on the near-term solid-core ENABLER NTP reactor design concept. This program is now capable of accurately modeling (characterizing) a complete near-term solid-core NTP engine system in great detail, for a number of design options, in an efficient manner. The following discussion summarizes the overall analysis methodology, key assumptions, and capabilities associated with the NESS presents an

  3. Ongoing Space Nuclear Systems Development in the United States

    SciTech Connect

    S. Bragg-Sitton; J. Werner; S. Johnson; Michael G. Houts; Donald T. Palac; Lee S. Mason; David I. Poston; A. Lou Qualls

    2011-10-01

    Reliable, long-life power systems are required for ambitious space exploration missions. Nuclear power and propulsion options can enable a bold, new set of missions and introduce propulsion capabilities to achieve access to science destinations that are not possible with more conventional systems. Space nuclear power options can be divided into three main categories: radioisotope power for heating or low power applications; fission power systems for non-terrestrial surface application or for spacecraft power; and fission power systems for electric propulsion or direct thermal propulsion. Each of these areas has been investigated in the United States since the 1950s, achieving various stages of development. While some nuclear systems have achieved flight deployment, others continue to be researched today. This paper will provide a brief overview of historical space nuclear programs in the U.S. and will provide a summary of the ongoing space nuclear systems research, development, and deployment in the United States.

  4. STS pilot user development program

    NASA Technical Reports Server (NTRS)

    Mcdowell, J. R.

    1977-01-01

    Full exploitation of the STS capabilities will be not only dependent on the extensive use of the STS for known space applications and research, but also on new, innovative ideas of use originating with both current and new users. In recognition of this, NASA has been engaged in a User Development Program for the STS. The program began with four small studies. Each study addressed a separate sector of potential new users to identify techniques and methodologies for user development. The collective results established that a user development function was not only feasible, but necessary for NASA to realize the full potential of the STS. This final report begins with a description of the overall pilot program plan, which involved five specific tasks defined in the contract Statement of Work. Each task is then discussed separately; but two subjects, the development of principal investigators and space processing users, are discussed separately for improved continuity of thought. These discussions are followed by a summary of the primary results and conclusions of the Pilot User Development Program. Specific recommendations of the study are given.

  5. MSFC Nuclear Propulsion Materials Development

    NASA Technical Reports Server (NTRS)

    Rogers, J. R.; Cook, B.

    2004-01-01

    Nuclear propulsion systems for spacecraft applications present numerous technical challenges for propulsion systems. They have been the focus of a recent NRA. Challenges inclue: a nuclear reactor subsystem to produce thermal energy; a power conversion subsystem to convert the thermal energy into electrical energy; a propulsion subsystem that utilizes Hall effect thrusters; thruster technologies and high temperature materials to support subsystems. The MSFC Electrostatic Levitation (ESL) Facility provides an ideal platform for the study of high temperature and reactive materials. An overview of the facility and its capabilities will be presented.

  6. Nuclear Explosion Monitoring Research and Engineering Program - Strategic Plan

    SciTech Connect

    Casey, Leslie A.

    2004-09-01

    The Department of Energy (DOE)/National Nuclear Security Administration (NNSA) Nuclear Explosion Monitoring Research and Engineering (NEM R&E) Program is dedicated to providing knowledge, technical expertise, and products to US agencies responsible for monitoring nuclear explosions in all environments and is successful in turning scientific breakthroughs into tools for use by operational monitoring agencies. To effectively address the rapidly evolving state of affairs, the NNSA NEM R&E program is structured around three program elements described within this strategic plan: Integration of New Monitoring Assets, Advanced Event Characterization, and Next-Generation Monitoring Systems. How the Program fits into the National effort and historical accomplishments are also addressed.

  7. Lunar exploration rover program developments

    NASA Technical Reports Server (NTRS)

    Klarer, P. R.

    1994-01-01

    The Robotic All Terrain Lunar Exploration Rover (RATLER) design concept began at Sandia National Laboratories in late 1991 with a series of small, proof-of-principle, working scale models. The models proved the viability of the concept for high mobility through mechanical simplicity, and eventually received internal funding at Sandia National Laboratories for full scale, proof-of-concept prototype development. Whereas the proof-of-principle models demonstrated the mechanical design's capabilities for mobility, the full scale proof-of-concept design currently under development is intended to support field operations for experiments in telerobotics, autonomous robotic operations, telerobotic field geology, and advanced man-machine interface concepts. The development program's current status is described, including an outline of the program's work over the past year, recent accomplishments, and plans for follow-on development work.

  8. Data Base Development: Federal Programs.

    ERIC Educational Resources Information Center

    Fisk, Dorothy A.; Weiss, Todd D.

    1980-01-01

    Describes the development of a prototype database of federal food, agriculture, and nutrition programs: preliminary work; database design, including the identification of data elements; and data collection and processing. The uses of the database and suggestions for enhancing its future usefulness are discussed. (Author/JD)

  9. Motor Education: Educational Development Programs.

    ERIC Educational Resources Information Center

    Tansley, A. E.

    This booklet presents educational programs and activities focusing on motor skills for 5- to 9-year-old children and older children with learning problems. The premise of the activities is that the acquisition of motor skills is essential to basic learning. The role of language as a mediator and controller of motor development is emphasized. The…

  10. Social Development Program. 1967 Report.

    ERIC Educational Resources Information Center

    Ptaschnik, Jeffrey

    The Social Development Program was originated under Title I to aid socially maladjusted students, particularly disadvantaged Negro students, to adjust socially and academically. Group dynamics were used to influence the self-concepts of sixth and seventh graders from five participating schools. This report states the formal definition of the…

  11. Automotive Stirling Engine Development Program

    NASA Technical Reports Server (NTRS)

    Nightingale, N.; Ernst, W.; Richey, A.; Simetkosky, M.; Smith, G.; Rohdenburg, C.; Antonelli, M. (Editor)

    1983-01-01

    Program status and plans are discussed for component and technology development; reference engine system design, the upgraded Mod 1 engine; industry test and evaluation; and product assurance. Four current Mod 1 engines reached a total of 2523 operational hours, while two upgraded engines accumulated 166 hours.

  12. Child Development and Intergenerational Programming.

    ERIC Educational Resources Information Center

    Crites, Marsha S.

    1989-01-01

    Child development can be fostered through relationships between older adults and children. Children's social isolation resulting from demographic, economic, and social changes can be addressed by means of intergenerational programs. During four developmental stages from infancy to adolescence, older adults can play a significant role in…

  13. Professorship: A Faculty Development Program.

    ERIC Educational Resources Information Center

    Davis, Todd M.; Davis, Jane F.

    1987-01-01

    A faculty development program at a traditionally black college was designed to enhance the ability of graduate faculty to supervise research activities of graduate students. Focus was on interpersonal problem solving in advisement and professional issues; classroom techniques of discussion teaching, case methods, and psychodrama encouraged the…

  14. Early Site Permit Demonstration Program: Nuclear Power Plant Siting Database

    Energy Science and Technology Software Center (ESTSC)

    1994-01-28

    This database is a repository of comprehensive licensing and technical reviews of siting regulatory processes and acceptance criteria for advanced light water reactor (ALWR) nuclear power plants. The program is designed to be used by applicants for an early site permit or combined construction permit/operating license (10CFRR522, Subparts A and C) as input for the development of the application. The database is a complete, menu-driven, self-contained package that can search and sort the supplied datamore » by topic, keyword, or other input. The software is designed for operation on IBM compatible computers with DOS.« less

  15. Auditing nuclear weapons quality programs at Los Alamos

    SciTech Connect

    Davis, A.H.

    1988-01-01

    Some of the problems involved in introducing quality assurance on a broad scale in a national laboratory are discussed. A philosophy of how QA can be utilized beneficially in research and development activities is described briefly, and our experiences at Los Alamos in applying QA to nuclear weapons activities are outlines. The important role of audits is emphasized; audits are used not merely to determine the effectiveness of QA programs but also to explain and demonstrate the usefulness of QA to a generally sceptical body of engineers and scientists. Finally, some ways of easing the application of QA in the future are proposed. 1 ref.

  16. Opening Doors of Opportunity to Develop the Future Nuclear Workforce - 13325

    SciTech Connect

    Mets, Mindy

    2013-07-01

    The United States' long-term demand for highly skilled nuclear industry workers is well-documented by the Nuclear Energy Institute. In addition, a study commissioned by the SRS Community Reuse Organization concludes that 10,000 new nuclear workers are needed in the two-state region of Georgia and South Carolina alone. Young adults interested in preparing for these nuclear careers must develop specialized skills and knowledge, including a clear understanding of the nuclear workforce culture. Successful students are able to enter well-paying career fields. However, the national focus on nuclear career opportunities and associated training and education programs has been minimal in recent decades. Developing the future nuclear workforce is a challenge, particularly in the midst of competition for similar workers from various industries. In response to regional nuclear workforce development needs, the SRS Community Reuse Organization established the Nuclear Workforce Initiative (NWI{sup R}) to promote and expand nuclear workforce development capabilities by facilitating integrated partnerships. NWI{sup R} achievements include a unique program concept called NWI{sup R} Academies developed to link students with nuclear career options through firsthand experiences. The academies are developed and conducted at Aiken Technical College and Augusta Technical College with support from workforce development organizations and nuclear employers. Programs successfully engage citizens in nuclear workforce development and can be adapted to other communities focused on building the future nuclear workforce. (authors)

  17. Nuclear Technology Programs semiannual progress report, April-- September 1990

    SciTech Connect

    Harmon, J.E.

    1992-06-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  18. Nuclear technology programs. Semiannual progress report, April--September 1991

    SciTech Connect

    Not Available

    1993-07-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April through September 1991. These programs involve R & D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  19. Nuclear Technology Programs semiannual progress report, October 1990--March 1991

    SciTech Connect

    1992-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1990--March 1991. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transpose of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  20. Nuclear Technology Programs semiannual progress report, April-- September 1990

    SciTech Connect

    Harmon, J.E.

    1992-06-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  1. Nuclear Technology Programs semiannual progress report, October 1988--March 1989

    SciTech Connect

    Harmon, J.E.

    1990-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1988--March 1989. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories. 127 refs., 76 figs., 103 tabs.

  2. Nuclear technology programs; Semiannual progress report, October 1989--March 1990

    SciTech Connect

    Harmon, J.E.

    1992-01-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  3. Program to justify life extension of older nuclear piping systems

    SciTech Connect

    Burr, T.K.; Dwight, J.E. Jr.; Morton, D.K.

    1991-01-01

    The Idaho National Engineering Laboratory (INEL) has a history of more than 40 years devoted to the operation of nuclear reactors designed for research and experiments. The Advanced Test Reactor (ATR) is one such operating reactor whose mission requires continued operation for an additional 25 years or more. Since the ATR is approaching its design life of twenty years, life extension evaluations have been initiated. Of particular importance are the associated high temperature, high pressure loop piping system supporting in--reactor experiments. Failure of this piping could challenge core safety margins. Since regulatory rules for nuclear power plant life extension are only in the formulation stage, the current technical guidance on this subject provided by the Department of Energy (DOE) or the commercial nuclear industry is incomplete. In the interim, order to assure continued safe operation of this piping beyond its initial design life, a program has been developed to provide the necessary technical justification for life extension. This paper describes a program that establishes Section 11 of the ASME Boiler and Pressure Vessel Code as the governing criteria document, retains B31.1 as the Code of record for Section 11 activities, specifies additional inservice inspection requirements more strict than Section 11, and relies heavily on flaw detection and fracture mechanics evaluations. 18 refs., 2 figs.

  4. DEVELOPMENT OF NUCLEAR POWER PLANT SIMULATORS FOR SOVIET-DESIGNED NUCLEAR REACTORS.

    SciTech Connect

    Kohut, P.; Tutu, N.K.; Cleary, E.J.; Erickson, K.G.; Yoder, J.; Kroshilin, A.

    2001-01-07

    The US Department of Energy (US DOE), under the US government's International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators, are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper.

  5. ADVANCED EMISSIONS CONTROL DEVELOPMENT PROGRAM

    SciTech Connect

    G.A. Farthing

    2001-02-06

    The primary objective of the Advanced Emissions Control Development Program (AECDP) is to develop practical, cost-effective strategies for reducing the emissions of hazardous air pollutants (HAPs, or air toxics) from coal-fired boilers. The project goal is to effectively control air toxic emissions through the use of conventional flue gas cleanup equipment such as electrostatic precipitators (ESPs), fabric filters (baghouses), and wet flue gas desulfurization (WFGD) systems. Development work initially concentrated on the capture of trace metals, fine particulate, hydrogen chloride, and hydrogen fluoride. Recent work has focused almost exclusively on the control of mercury emissions.

  6. Advanced Emissions Control Development Program

    SciTech Connect

    G. A. Farthing; G. T. Amrhein; G. A. Kudlac; D. A. Yurchison; D. K. McDonald; M. G. Milobowski

    2001-03-31

    The primary objective of the Advanced Emissions Control Development Program (AECDP) is to develop practical, cost-effective strategies for reducing the emissions of hazardous air pollutants (HAPs, or air toxics) from coal-fired boilers. This objective is being met by identifying ways to effectively control air toxic emissions through the use of conventional flue gas cleanup equipment such as electrostatic precipitators (ESPs), fabric filters (fabric filters), and wet flue gas desulfurization (wet FGD) systems. Development work initially concentrated on the capture of trace metals, hydrogen chloride, and hydrogen fluoride. Recent work has focused almost exclusively on the control of mercury emissions.

  7. Accelerated leach test development program

    SciTech Connect

    Fuhrmann, M.; Pietrzak, R.F.; Heiser, J.; Franz, E.M.; Colombo, P.

    1990-11-01

    In FY 1989, a draft accelerated leach test for solidified waste was written. Combined test conditions that accelerate leaching were validated through experimental and modeling efforts. A computer program was developed that calculates test results and models leaching mechanisms. This program allows the user to determine if diffusion controls leaching and, if this is the case, to make projections of releases. Leaching mechanisms other than diffusion (diffusion plus source term partitioning and solubility limited leaching) are included in the program is indicators of other processes that may control leaching. Leach test data are presented and modeling results are discussed for laboratory scale waste forms composed of portland cement containing sodium sulfate salt, portland cement containing incinerator ash, and vinyl ester-styrene containing sodium sulfate. 16 refs., 38 figs., 5 tabs.

  8. Sister Lab Program Prospective Partner Nuclear Profile: Vietnam

    SciTech Connect

    Bissani, M; Tyson, S

    2006-12-14

    Vietnam's nuclear program began in the 1960s with the installation at Dalat of a 250 kW TRIGA Mk-II research reactor under the U.S. Atoms for Peace Program. The reactor was shut down and its core removed only a few years later, and the nuclear research program was suspended until after the end of the civil war in the late 1970s. The Soviet Union assisted Vietnam in restoring the Dalat reactor to an operational status in 1984, trained a cadre of scientific and technical staff in its operation, and contributed to the development of nuclear science for the medical and agricultural sectors. In the agricultural area in particular, Vietnamese experts have been very successful in developing mutant strains of rice, and continue to work with the IAEA to yield strains that have a shorter growing period, increased resistance to disease, and other desirable characteristics. Rice has always been the main crop in Vietnam, but technical cooperation with the IAEA and other states has enabled the country to become one of the top rice producers in the world, exporting much of its annual crop to over two dozen countries annually. More recently, Vietnam's government has shown increasing interest in developing a civil nuclear program to supplement its fossil fuel and other energy resources. Projections from a variety of open sources, ranging from the IAEA, the U.S. Department of Energy's Energy Information Administration (EIA), the Vietnamese government, energy corporations, and think tanks all predict a massive increase in energy consumption--especially electricity--within Vietnam and the region as a whole. This growth in consumption will require a corresponding increase in energy production, which in Vietnam is currently satisfied mainly by fossil fuels (coal) and renewable energy (hydropower and biomass); Vietnam has a refining capacity of about 800 barrels/day. Most of its crude oil is exported to generate export income, and is not used to generate electricity. Although Vietnam is

  9. Development of an Integrity Evaluation System for Nuclear Power Plants

    NASA Astrophysics Data System (ADS)

    Kim, Young-Jin; Choi, Jae-Boong; Lee, Joon-Seong; Jun, Hyun-Kyu; Park, Youn-Won

    This paper describes the structure and development strategy for integrity evaluation system for nuclear power plants called NPP-KINS/SAFE. NPP-KINS/SAFE consists of three different programs covering the integrity assessment of reactor pressure vessel, pipings, and pressure tubes, respectively. The system has been developed based on currently available codes and standards, and includes a number of databases, expert systems, and numerical analysis schemes. NPP-KINS/SAFE is applicable for various types of nuclear power plants constructed in Korea with the aid of attached database systems including plant specific data. Case studies for the developed system are also provided.

  10. Glucocorticoid programming of intrauterine development.

    PubMed

    Fowden, A L; Valenzuela, O A; Vaughan, O R; Jellyman, J K; Forhead, A J

    2016-07-01

    Glucocorticoids (GCs) are important environmental and maturational signals during intrauterine development. Toward term, the maturational rise in fetal glucocorticoid receptor concentrations decreases fetal growth and induces differentiation of key tissues essential for neonatal survival. When cortisol levels rise earlier in gestation as a result of suboptimal conditions for fetal growth, the switch from tissue accretion to differentiation is initiated prematurely, which alters the phenotype that develops from the genotype inherited at conception. Although this improves the chances of survival should delivery occur, it also has functional consequences for the offspring long after birth. Glucocorticoids are, therefore, also programming signals that permanently alter tissue structure and function during intrauterine development to optimize offspring fitness. However, if the postnatal environmental conditions differ from those signaled in utero, the phenotypical outcome of early-life glucocorticoid receptor overexposure may become maladaptive and lead to physiological dysfunction in the adult. This review focuses on the role of GCs in developmental programming, primarily in farm species. It examines the factors influencing GC bioavailability in utero and the effects that GCs have on the development of fetal tissues and organ systems, both at term and earlier in gestation. It also discusses the windows of susceptibility to GC overexposure in early life together with the molecular mechanisms and long-term consequences of GC programming with particular emphasis on the cardiovascular, metabolic, and endocrine phenotype of the offspring. PMID:27345310

  11. A look at the Soviet space nuclear power program

    NASA Technical Reports Server (NTRS)

    Bennett, Gary L.

    1989-01-01

    For the most part Soviet nuclear power sources have been low-power nuclear reactors using a thermoelectric conversion principle. Recently the Soviet Union has flown two satellites using a higher power reactor that employs a thermionic conversion system. Despite reentry of two of the earlier reactors on board Cosmos 954 and Cosmos 1402 and the recent potential accident involving Cosmos 1900, the evidence points toward a continued Soviet use of nuclear power sources in space. Information in the open literature on the Soviet space nuclear power program, including the Romashka Topaz, the new reactor based on the Topaz program, and the RORSAT reactor experience, is summarized.

  12. Programmed Cell Death During Caenorhabditis elegans Development.

    PubMed

    Conradt, Barbara; Wu, Yi-Chun; Xue, Ding

    2016-08-01

    Programmed cell death is an integral component of Caenorhabditis elegans development. Genetic and reverse genetic studies in C. elegans have led to the identification of many genes and conserved cell death pathways that are important for the specification of which cells should live or die, the activation of the suicide program, and the dismantling and removal of dying cells. Molecular, cell biological, and biochemical studies have revealed the underlying mechanisms that control these three phases of programmed cell death. In particular, the interplay of transcriptional regulatory cascades and networks involving multiple transcriptional regulators is crucial in activating the expression of the key death-inducing gene egl-1 and, in some cases, the ced-3 gene in cells destined to die. A protein interaction cascade involving EGL-1, CED-9, CED-4, and CED-3 results in the activation of the key cell death protease CED-3, which is tightly controlled by multiple positive and negative regulators. The activation of the CED-3 caspase then initiates the cell disassembly process by cleaving and activating or inactivating crucial CED-3 substrates; leading to activation of multiple cell death execution events, including nuclear DNA fragmentation, mitochondrial elimination, phosphatidylserine externalization, inactivation of survival signals, and clearance of apoptotic cells. Further studies of programmed cell death in C. elegans will continue to advance our understanding of how programmed cell death is regulated, activated, and executed in general. PMID:27516615

  13. Development of Curricula for Nuclear Radiation Protection, Nuclear Instrumentation, and Nuclear Materials Processing Technologies. Final Report.

    ERIC Educational Resources Information Center

    Hull, Daniel M.

    A study was conducted to assist two-year postsecondary educational institutions in providing technical specialty courses for preparing nuclear technicians. As a result of project activities, curricula have been developed for five categories of nuclear technicians and operators: (1) radiation protection technician, (2) nuclear instrumentation and…

  14. Robotic control architecture development for automated nuclear material handling systems

    SciTech Connect

    Merrill, R.D.; Hurd, R.; Couture, S.; Wilhelmsen, K.

    1995-02-01

    Lawrence Livermore National Laboratory (LLNL) is engaged in developing automated systems for handling materials for mixed waste treatment, nuclear pyrochemical processing, and weapon components disassembly. In support of these application areas there is an extensive robotic development program. This paper will describe the portion of this effort at LLNL devoted to control system architecture development, and review two applications currently being implemented which incorporate these technologies.

  15. Development of a survivorship program.

    PubMed

    Downs-Holmes, Catherine; Dracon, Andrea; Svarovsky, Therese; Sustin, Marla

    2014-01-01

    The number of cancer survivors has steadily climbed to more than 10 million since the 1980s secondary to advances in detection and treatment modalities. This reality, combined with an aging population, has drawn the attention of the medical community to meet the needs of this population. Therefore, cancer care providers are being called to develop survivorship programs for patients with curable disease. Some of the prominent organizations supporting this movement for focused survivorship care include the Institute of Medicine, the National Comprehensive Cancer Network, the American Society of Clinical Oncology, LiveStrong™, and the Oncology Nursing Society. This article provides the necessary steps for the development and implementation of an institution-specific survivorship program to fulfill the new standards for survivorship care. PMID:25252995

  16. Advanced Emissions Control Development Program

    SciTech Connect

    A.P.Evans; K.E. Redinger; M.J. Holmes

    1998-04-01

    The objective of the Advanced Emissions Control Development Program (AECDP) is to develop practical, cost-effective strategies for reducing the emissions of air toxics from coal-fired boilers. Ideally, the project aim is to effectively control air toxic emissions through the use of conventional flue gas cleanup equipment such as electrostatic precipitators (ESPS), fabric filters (baghouse), and wet flue gas desulfurization. Development work to date has concentrated on the capture of mercury, other trace metals, fine particulate and hydrogen chloride. Following the construction and evaluation of a representative air toxics test facility in Phase I, Phase II focused on the evaluation of mercury and several other air toxics emissions. The AECDP is jointly funded by the United States Department of Energy's Federal Energy Technology Center (DOE), the Ohio Coal Development Office within the Ohio Department of Development (oCDO), and Babcock& Wilcox-a McDermott company (B&W).

  17. The Need for a Strong Science and Technology Program in the Nuclear Weapons Complex for the 21st Century

    SciTech Connect

    Garaizar, Xabier

    2009-07-02

    In this paper I argue for the need for a strong Science and Technology program in the Nuclear Weapons Complex as the basis for maintaining a credible deterrence capability. The current Nuclear Posture Review establishes a New Triad as the basis for the United States deterrence strategy in a changing security environment. A predictive science capability is at the core of a credible National Nuclear Weapons program in the 21st Century. In absence of nuclear testing, the certification of our current Nuclear Weapons relies on predictive simulations and quantification of the associated simulation uncertainties. In addition, a robust nuclear infrastructure needs an active research and development program that considers all the required nuclear scenarios, including new configurations for which there is no nuclear test data. This paper also considers alternative positions to the need for a Science and Technology program in the Nuclear Weapons complex.

  18. The Meteorological Monitoring program at a former nuclear weapons plant

    SciTech Connect

    Maxwell, D.R.; Bowen, B.M.

    1994-02-01

    The purpose of the Meteorological Monitoring program at Rocky Flats Plant (RFP) is to provide meteorological information for use in assessing the transport, and diffusion, and deposition of effluent actually or potentially released into the atmosphere by plant operations. Achievement of this objective aids in protecting health and safety of the public, employees, and environment, and directly supports Emergency Response programs at RFP. Meteorological information supports the design of environmental monitoring networks for impact assessments, environmental surveillance activities, remediation activities, and emergency responses. As the mission of the plant changes from production of nuclear weapons parts to environmental cleanup and economic development, smaller releases resulting from remediation activities become more likely. These possible releases could result from airborne fugitive dust, evaporation from collection ponds, or grass fires.

  19. JPRS report: Nuclear developments, [February 25, 1988

    SciTech Connect

    1988-02-25

    This report contains information concerning the nuclear developments of the following countries: Canada, Nigeria, China, Japan, Argentina, Brazil, Jamaica, Bangladesh, India, Pakistan, Egypt, Sudan, Ireland, France, Turkey, United Kingdom, and Federal Republic of Germany.

  20. Office of Nuclear Energy Knowledge Management Program Situational Analysis Report

    SciTech Connect

    Kimberlyn C. Mousseau

    2011-12-01

    Knowledge management (KM) has been a high priority for the Department of Energy (DOE) Office of Nuclear Energy (NE) for the past several years. NE Programs are moving toward well-established knowledge management practices and a formal knowledge management program has been established. Knowledge management is being practiced to some level within each of the NE programs. Although it continues to evolve as NE programs evolve, a formal strategic plan that guides the implementation of KM has been developed. Despite the acceptance of KM within DOE NE, more work is necessary before the NE KM program can be considered fully successful. Per Dr. David J. Skyrme[1], an organization typically moves through the following evolutionary phases: (1) Ad-hoc - KM is being practiced to some level in some parts of the organization; (2) Formal - KM is established as a formal project or program; (3) Expanding - the use of KM as a discipline grows in practice across different parts of the organization; (4) Cohesive - there is a degree of coordination of KM; (5) Integrated - there are formal standards and approaches that give every individual access to most organizational knowledge through common interfaces; and (6) Embedded - KM is part-and-parcel of everyday tasks; it blends seamlessly into the background. According to the evolutionary phases, the NE KM program is operating at the two lower levels, Ad-hoc and Formal. Although KM is being practiced to some level, it is not being practiced in a consistent manner across the NE programs. To be fully successful, more emphasis must be placed on establishing KM standards and processes for collecting, organizing, sharing and accessing NE knowledge. Existing knowledge needs to be prioritized and gathered on a routine basis, its existence formally recorded in a knowledge inventory. Governance to ensure the quality of the knowledge being used must also be considered. For easy retrieval, knowledge must be organized according to a taxonomy that

  1. Wind Energy Career Development Program

    SciTech Connect

    Gwen Andersen

    2012-03-29

    Saint Francis University has developed curriculum in engineering and in business that is meeting the needs of students and employers (Task 1) as well as integrating wind energy throughout the curriculum. Through a variety of approaches, the University engaged in public outreach and education that reached over 2,000 people annually (Task 2). We have demonstrated, through the success of these programs, that students are eager to prepare for emerging jobs in alternative energy, that employers are willing to assist in developing employees who understand the broader business and policy context of the industry, and that people want to learn about wind energy.

  2. NASA's mobile satellite development program

    NASA Technical Reports Server (NTRS)

    Rafferty, William; Dessouky, Khaled; Sue, Miles

    1988-01-01

    A Mobile Satellite System (MSS) will provide data and voice communications over a vast geographical area to a large population of mobile users. A technical overview is given of the extensive research and development studies and development performed under NASA's mobile satellite program (MSAT-X) in support of the introduction of a U.S. MSS. The critical technologies necessary to enable such a system are emphasized: vehicle antennas, modulation and coding, speech coders, networking and propagation characterization. Also proposed is a first, and future generation MSS architecture based upon realized ground segment equipment and advanced space segment studies.

  3. Nuclear structure, gene expression and development.

    PubMed

    Brown, K

    1999-01-01

    This article considers the extent to which features of nuclear structure are involved in the regulation of genome function. The recent renaissance in imaging technology has inspired a new determination to assign specific functions to nuclear domains or structures, many of which have been described as "factories" to express the idea that they coordinate nuclear processes in an efficient way. Visual data have been combined with genetic and biochemical information to support the idea that nuclear organization has functional significance. Particular DNA sequences or chromatin structures may nucleate domains that are permissive or restrictive of transcription, to which active or inactive loci could be recruited. Associations within the nucleus, as well as many nuclear structures, are transient and change dynamically during cell cycle progression and development. Despite this complexity, elucidation of the possible structural basis of epigenetic phenomena, such as the inheritance of a "cellular memory" of gene expression status, is an important goal for cell biology. Topics for discussion include the regulatory effect of chromatin structure on gene expression, putative "nuclear addresses" for genes and proteins, the functional significance of nuclear bodies, and the role of the nuclear matrix in nuclear compartmentalization. PMID:10651237

  4. Interim Report: Program Development Specialist's Role.

    ERIC Educational Resources Information Center

    Coon, George E.

    In a memorandum to the Chief of Planning and Program Development, Teacher Corps, the Program Development Specialist for the Pontiac Urban Corps in Oakland examines the role of the program development specialist. Although the program was successful in that 31 beginning teachers were placed and modules were developed in three discipline areas, the…

  5. Sustainability of a Nuclear Security Educational Program at Tomsk Polytechnic University

    SciTech Connect

    Boiko, Vladimir I.; Silaev, Maxim E.; Duncan, Cristen L.; Hazel, Michael J.; Heinberg, Cynthia L.; Goodey, Kent O.; Butler, Gilbert W.

    2012-06-07

    Educational programs for training of specialists in the area of material protection, control and accounting (MPC&A) for Russian nuclear facilities have been implemented at the National Research Tomsk Polytechnic University over the last eight years. The initial stage of creating the program, which can be deemed as successfully functioning, has been completed. The next stage entails further improvement of the program in order to create conditions for its sustainability and steady improvement. The educational program sustainability plan contains a number of steps, including the following: - Analysis of the status, standards and prospects for development of nuclear security educational programs in the world; - Analysis of the current educational program, level of its functionality and the demand for the program as well as its capability to react adequately to external influences; - Analysis of the factors influencing program development at its current stage and in the future; - Assessment of needs and development of proposals for the program’s sustainability; - Assessment of needs and development of proposals for improving quality and increasing the demand for the program by potential employers; - Assessment of needs and development of proposals for expansion of the program’s content and the scope of its application; - Development of short-term and long-term plans for functioning and development. Strategic prospects for development are associated with the transition from MPC&A to a broader range of tasks covered by the specialization in the area of nuclear security.

  6. Status report of the US Department of Energy`s International Nuclear Safety Program

    SciTech Connect

    1994-12-01

    The US Department of Energy (DOE) implements the US Government`s International Nuclear Safety Program to improve the level of safety at Soviet-designed nuclear power plants in Central and Eastern Europe, Russia, and Unkraine. The program is conducted consistent with guidance and policies established by the US Department of State (DOS) and the Agency for International Development and in close collaboration with the Nuclear Regulatory Commission. Some of the program elements were initiated in 1990 under a bilateral agreement with the former Soviet Union; however, most activities began after the Lisbon Nuclear Safety Initiative was announced by the DOS in 1992. Within DOE, the program is managed by the International Division of the Office of Nuclear Energy. The overall objective of the International Nuclear Safety Program is to make comprehensive improvements in the physical conditions of the power plants, plant operations, infrastructures, and safety cultures of countries operating Soviet-designed reactors. This status report summarizes the Internatioal Nuclear Safety Program`s activities that have been completed as of September 1994 and discusses those activities currently in progress.

  7. Nuclear Explosion Monitoring History and Research and Development

    NASA Astrophysics Data System (ADS)

    Hawkins, W. L.; Zucca, J. J.

    2008-12-01

    Within a year after the nuclear detonations over Hiroshima and Nagasaki the Baruch Plan was presented to the newly formed United Nations Atomic Energy Commission (June 14, 1946) to establish nuclear disarmament and international control over all nuclear activities. These controls would allow only the peaceful use of atomic energy. The plan was rejected through a Security Council veto primarily because of the resistance to unlimited inspections. Since that time there have been many multilateral, and bilateral agreements, and unilateral declarations to limit or eliminate nuclear detonations. Almost all of theses agreements (i.e. treaties) call for some type of monitoring. We will review a timeline showing the history of nuclear testing and the more important treaties. We will also describe testing operations, containment, phenomenology, and observations. The Comprehensive Nuclear Test Ban Treaty (CTBT) which has been signed by 179 countries (ratified by 144) established the International Monitoring System global verification regime which employs seismic, infrasound, hydroacoustic and radionuclide monitoring techniques. The CTBT also includes on-site inspection to clarify whether a nuclear explosion has been carried out in violation of the Treaty. The US Department of Energy (DOE) through its National Nuclear Security Agency's Ground-Based Nuclear Explosion Monitoring R&D Program supports research by US National Laboratories, and universities and industry internationally to detect, locate, and identify nuclear detonations. This research program builds on the broad base of monitoring expertise developed over several decades. Annually the DOE and the US Department of Defense jointly solicit monitoring research proposals. Areas of research include: seismic regional characterization and wave propagation, seismic event detection and location, seismic identification and source characterization, hydroacoustic monitoring, radionuclide monitoring, infrasound monitoring, and

  8. Latest Developments in Nuclear Emulsion Technology

    NASA Astrophysics Data System (ADS)

    Morishima, Kunihiro

    Nuclear emulsion is high sensitive photographic film used for detection of three-dimensional trajectory of charged particles. These trajectories are recorded as tracks consist of a lot of silver grains. The size of silver grain is about 1 μm, so that nuclear emulsion has submicron three-dimensional spatial resolution, which gives us a few mrad three-dimensional angular resolution. The important technical progress was speed-up of the read-out technique of nuclear emulsions built with optical microscope system. We succeeded in developing a high-speed three-dimensional read-out system named Super Ultra Track Selector (S-UTS) with the operating read-out speed of approximately 50 cm2/h. Nowadays we are developing the nuclear emulsion gel independently in Nagoya University by introducing emulsion gel production machine. Moreover, we are developing nuclear emulsion production technologies (gel production, poring and mass production). In this paper, development of nuclear emulsion technologies for the OPERA experiment, applications by the technologies and current development are described.

  9. 76 FR 66089 - Access Authorization Program for Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-25

    ...The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision to Regulatory Guide 5.66, ``Access Authorization Program for Nuclear Power Plants.'' This guide describes a method that NRC staff considers acceptable to implement the requirements related to an access authorization...

  10. Program development fund: FY 1987

    SciTech Connect

    Not Available

    1989-03-01

    It is the objective of the Fund to encourage innovative research to maintain the Laboratory's position at the forefront of science. Funds are used to explore new ideas and concepts that may potentially develop into new directions of research for the Laboratory and that are consistent with the major needs, overall goals, and mission of the Laboratory and the DOE. The types of projects eligible for support from PDF include: work in forefront areas of science and technology for the primary purpose of enriching Laboratory research and development capabilities; advanced study of new hypotheses, new experimental concepts, or innovative approaches to energy problems; experiments directed toward ''proof of principle'' or early determination of the utility of a new concept; and conception, design analyses, and development of experimental devices, instruments, or components. This report is a review of these research programs.

  11. Commercial Development Suborbital Rocket Program

    NASA Technical Reports Server (NTRS)

    1993-01-01

    The enclosed report provides information on the sixth flight of the Consort suborbital rocket series. Consort 6 is currently scheduled for launch on February 19, 1993, with lift off at 11:00 a.m., Mountain Time. It will carry seven materials and biotechnology experiments, two accelerometer systems, a controller and battery packs in a module nearly 12 feet tall and weighing approximately 1,004 pounds. Consort 6 will reach an apogee of approximately 200 miles providing about 7 minutes of microgravity time. The entire mission, from launch to touchdown, is expected to last approximately 15 minutes. The Consort series is part of a unique suborbital rocket launch services program conducted by the Office of Advanced Concepts and Technology (OACT) in conjunction with its Centers for the Commercial Development of Space (CCDS). This service is managed through the Consortium for Materials Development in Space (CMDS), a CCDS based University of Alabama in Huntsville (UAH). at the This suborbital rocket program provides CCDS investigators with a microgravity environment to achieve commercial development objectives, or to test developmental hardware or techniques in preparation for orbital flights or additional follow-on work. Rocket and launch services for Consort 6, including use of the Starfire 1 launch vehicle, are provided by EER Systems Corporation. Integration of the payload into Starfire 1 will be handled by McDonnell Douglas Space Systems Company.

  12. Nuclear science outreach program for high school girls

    SciTech Connect

    Foster, D.E.; Stone, C.A.

    1996-12-31

    The authors have developed a 2-week summer school on nuclear science for high school girls. This summer school is an outgrowth of a recent American Nuclear Society high school teachers workshop held at San Jose State University. Young scientists are introduced to concepts in nuclear science through a combination of lectures, laboratory experiments, literature research, and visits to local national laboratories and nuclear facilities. Lectures cover a range of topics, including radioactivity and radioactive decay, statistics, fission and fusion, nuclear medicine, and food irradiation. A variety of applications of nuclear science concepts are also presented.

  13. Development and Implementation of a Program Management Maturity Model

    SciTech Connect

    Hartwig, Laura; Smith, Matt

    2008-12-15

    In 2006, Honeywell Federal Manufacturing & Technologies (FM&T) announced an updatedvision statement for the organization. The vision is “To be the most admired team within the NNSA [National Nuclear Security Administration] for our relentless drive to convert ideas into the highest quality products and services for National Security by applying the right technology, outstanding program management and best commercial practices.” The challenge to provide outstanding program management was taken up by the Program Management division and the Program Integration Office (PIO) of the company. This article describes how Honeywell developed and deployed a program management maturity model to drive toward excellence.

  14. Program summary for the Civilian Reactor Development Program

    SciTech Connect

    1982-07-01

    This Civilian Reactor Development Program document has the prime purpose of summarizing the technical programs supported by the FY 1983 budget request. This section provides a statement of the overall program objectives and a general program overview. Section II presents the technical programs in a format intended to show logical technical interrelationships, and does not necessarily follow the structure of the formal budget presentation. Section III presents the technical organization and management structure of the program.

  15. Automotive Stirling Engine Development Program

    NASA Technical Reports Server (NTRS)

    Nightingale, N.; Richey, A.; Farrell, R.; Riecke, G.; Ernst, W.; Howarth, R.; Cronin, M.; Simetkosky, M.; Smith, G.; Meacher, J.

    1985-01-01

    Development test activities on Mod I engines directed toward evaluating technologies for potential inclusion in the Mod II engine are summarized. Activities covered include: test of a 12-tube combustion gas recirculation combustor; manufacture and flow-distribution test of a two-manifold annular heater head; piston rod/piston base joint; single-solid piston rings; and a digital air/fuel concept. Also summarized are results of a formal assessment of candidate technologies for the Mod II engine, and preliminary design work for the Mod II. The overall program philosophy weight is outlined, and data and test results are presented.

  16. Microbial studies in the Canadian nuclear fuel waste management program.

    PubMed

    Stroes-Gascoyne, S; West, J M

    1997-07-01

    Atomic Energy of Canada Limited (AECL) has developed a concept for permanent geological disposal of used nuclear fuel in Canada. This concept, based on a multibarrier system, would involve disposal of nuclear fuel waste in titanium or copper containers, surrounded by compacted clay-based buffer and backfill materials, in a vault 500-1000 m deep in granitic rock of the Canadian Shield. Subsurface environments will not be sterile and an experimental program was initiated in 1991 by AECL to address and quantify the potential effects of microbial action on the integrity of the disposal vault. This microbial program focuses on answering specific questions in areas such as the survival of bacteria in compacted clay-based buffer materials under relevant radiation, temperature and desiccation conditions; mobility of microbes in compacted buffer materials; the potential for microbially influenced corrosion of containers; microbial gas production in backfill material; introduction of nutrients as a result of vault excavation and operation; the presence and activity of microbes in deep granitic groundwaters; and the effects of biofilms on radionuclide migration in the geosphere. This paper summarizes the results to date from the research activities at AECL. PMID:9299719

  17. 23 CFR 660.109 - Program development.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 23 Highways 1 2011-04-01 2011-04-01 false Program development. 660.109 Section 660.109 Highways... PROGRAMS (DIRECT FEDERAL) Forest Highways § 660.109 Program development. (a) The FHWA will arrange and... program will be selected considering the following criteria: (1) The development, utilization,...

  18. 23 CFR 660.109 - Program development.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 23 Highways 1 2010-04-01 2010-04-01 false Program development. 660.109 Section 660.109 Highways... PROGRAMS (DIRECT FEDERAL) Forest Highways § 660.109 Program development. (a) The FHWA will arrange and... program will be selected considering the following criteria: (1) The development, utilization,...

  19. Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

    SciTech Connect

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-09-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  20. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2007-01-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  1. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-12-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  2. Nuclear Engineering Academic Programs Survey, 2002 Data

    SciTech Connect

    Oak Ridge Institute for Science and Education

    2003-10-01

    The survey includes degrees granted between July 1, 2001 and June 30, 2002. Enrollment information refers to the fall term 2002. Thirty-five academic programs were in the survey universe and all responded (100% response rate). One of the 35 programs reported that it was discontinued after the 2001-2002 academic year. Also, two programs were discontinued after the previous academic year (2000-2001) and were not included in 2002 survey.

  3. CELSS research and development program

    NASA Technical Reports Server (NTRS)

    Bubenheim, David

    1990-01-01

    Research in Controlled Ecological Life Support Systems (CELSS) conducted by NASA indicate that plant based systems are feasible candidates for human support in space. Ames has responsibility for research and development, systems integration and control, and space flight experiment portions of the CELSS program. Important areas for development of new methods and technologies are biomass production, waste processing, water purification, air revitalization, and food processing. For the plant system, the approach was to identify the flexibility and response time for the food, water, and oxygen production, and carbon dioxide consumption processes. Tremendous increases in productivity, compared with terrestrial agriculture, were realized. Waste processing research emphasizes recycle (transformation) of human wastes, trash, and inedible biomass to forms usable as inputs to the plant production system. Efforts to improve efficiency of the plant system, select new CELSS crops for a balanced diet, and initiate closed system research with the Crop Growth Research Chambers continue. The System Control and Integration program goal is to insure orchestrated system operation of the biological, physical, and chemical operation of the biological, physical, and chemical component processors of the CELSS. Space flight studies are planned to verify adequate operation of the system in reduced gravity or microgravity environments.

  4. Advanced Emission Control Development Program.

    SciTech Connect

    Evans, A.P.

    1997-12-31

    Babcock & Wilcox (B&W) is conducting a five-year project aimed at the development of practical, cost-effective strategies for reducing the emissions of hazardous air pollutants (commonly called air toxics) from coal-fired electric utility plants. The need for air toxic emissions controls may arise as the U. S. Environmental Protection Agency proceeds with implementation of Title III of the Clean Air Act Amendment (CAAA) of 1990. Data generated during the program will provide utilities with the technical and economic information necessary to reliably evaluate various air toxics emissions compliance options such as fuel switching, coal cleaning, and flue gas treatment. The development work is being carried out using B&W`s new Clean Environment Development Facility (CEDF) wherein air toxics emissions control strategies can be developed under controlled conditions, and with proven predictability to commercial systems. Tests conducted in the CEDF provide high quality, repeatable, comparable data over a wide range of coal properties, operating conditions, and emissions control systems. Development work to date has concentrated on the capture of mercury, other trace metals, fine particulate, and the inorganic species hydrogen chloride and hydrogen fluoride.

  5. Advanced Emissions Control Development Program

    SciTech Connect

    Evans, A P

    1998-12-03

    Babcock & Wilcox (B&W) is conducting a five-year project aimed at the development of practical, cost-effective strategies for reducing the emissions of hazardous air pollutants (commonly called air toxics) from coal-fired electric utility plants. The need for air toxic emissions controls may arise as the U. S. Environmental Protection Agency proceeds with implementation of Title III of the Clean Air Act Amendment (CAAA) of 1990. Data generated during the program will provide utilities with the technical and economic information necessary to reliably evaluate various air toxics emissions compliance options such as fuel switching, coal cleaning, and flue gas treatment. The development work is being carried out using B&W's new Clean Environment Development Facility (CEDF) wherein air toxics emissions control strategies can be developed under controlled conditions, and with proven predictability to commercial systems. Tests conducted in the CEDF provide high quality, repeatable, comparable data over a wide range of coal properties, operating conditions, and emissions control systems. Development work to date has concentrated on the capture of mercury, other trace metals, fine particulate, and the inorganic species hydrogen chloride and hydrogen fluoride.

  6. Advanced Emissions Control Development Program

    SciTech Connect

    M. J. Holmes

    1998-12-03

    McDermott Technology, Inc. (MTI) is conducting a five-year project aimed at the development of practical, cost-effective strategies for reducing the emissions of hazardous air pollutants (commonly called air toxics) from coal-fired electric utility plants. The need for air toxic emissions controls may arise as the U. S. Environmental Protection Agency proceeds with implementation of Title III of the Clean Air Act Amendment (CAAA) of 1990. Data generated during the program will provide utilities with the technical and economic information necessary to reliably evaluate various air toxics emissions compliance options such as fuel switching, coal cleaning, and flue gas treatment. The development work is being carried out using the Clean Environment Development Facility (CEDF) wherein air toxics emissions control strategies can be developed under controlled conditions, and with proven predictability to commercial systems. Tests conducted in the CEDF provide high quality, repeatable, comparable data over a wide range of coal properties, operating conditions, and emissions control systems. Development work to date has concentrated on the capture of mercury, other trace metals, fine particulate, and hydrogen chloride and hydrogen fluoride.

  7. Advanced Emissions Control Development Program

    SciTech Connect

    A. P. Evans

    1998-12-03

    McDermott Technology, Inc. (MTI) is conducting a five-year project aimed at the development of practical, cost-effective strategies for reducing the emissions of hazardous air pollutants (commonly called air toxics) from coal-fired electric utility plants. The need for air toxic emissions controls may arise as the U. S. Environmental Protection Agency proceeds with implementation of Title III of the Clean Air Act Amendment (CAAA) of 1990. Data generated during the program will provide utilities with the technical and economic information necessary to reliably evaluate various air toxics emissions compliance options such as fuel switching, coal cleaning, and flue gas treatment. The development work is being carried out using the Clean Environment Development Facility (CEDF) wherein air toxics emissions control strategies can be developed under controlled conditions, and with proven predictability to commercial systems. Tests conducted in the CEDF provide high quality, repeatable, comparable data over a wide range of coal properties, operating conditions, and emissions control systems. Development work to date has concentrated on the capture of mercury, other trace metals, fine particulate, and the inorganic species, hydrogen chloride and hydrogen fluoride.

  8. Uterine development and endometrial programming.

    PubMed

    Bartol, F F; Wiley, A A; Bagnell, C A

    2006-01-01

    Structural patterning and functional programming of uterine tissues are mechanistically coupled. These processes ensure anteroposterior differentiation of uterine tissues from adjacent segments of the developing female reproductive tract (FRT) and radial patterning that establishes uterine-specific histoarchitecture and functionality. Uterine organogenesis begins prenatally and is completed postnatally. Genes required for FRT development include Pax2, Lim1 and Emx2, genes in the abdominal-B Hoxa cluster, and members of both Wnt and Hedgehog (Hh) gene families. Disruption of morphoregulatory gene expression patterns can prevent FRT development entirely or compromise uterine organogenesis specifically. Oestrogen receptor-alpha (ER) -dependent events associated with development of the neonatal porcine uterus can be altered by administration of oestrogen (E) or relaxin (RLX). Expression of the RLX receptor is detectable in porcine endometrium at birth, before onset of ER expression and uterine gland genesis. Uterotrophic effects of both E and RLX can be inhibited with the ER antagonist ICl 182,780, indicating that RLX may act via crosstalk with the ER system in neonatal tissues. Exposure of neonatal gilts to E alters temporospatial patterns of Hh, Wnt and Hoxa expression in the uterine wall. Oestrogen given for two weeks from birth produced hypoplastic adult porcine uteri that were less responsive to periattachment conceptus signals as reflected by reduced growth response and luminal fluid protein accumulation, altered endometrial gene expression, and reduced capacity for conceptus support. Data reinforce the concept that factors affecting signalling events in uterine tissues that produce changes in morphoregulatory gene expression patterns during critical organisational periods can alter the developmental trajectory of the uterus with lasting consequences. Thus, uterine tissues can be programmed epigenetically for success or failure during perinatal life. PMID

  9. Developing a career advancement program.

    PubMed

    Pinette, Shirley L

    2003-01-01

    Have you ever asked yourself, "What will I be doing five or ten years from now?" "Will I be doing the same thing I'm doing right now?" How would you feel if the answer were "yes"? I often wonder if any of my employees think the same thing. If they do, and the answer is "yes," just how does that make them feel? A day's work for managers can run the gamut--from billing and coding, to patient issues, to staff performance reviews, to CQI, to JCAHO-just to name a few. We're NEVER bored. Can we say the same of our employees, or do they do the same thing day in and day out? If so, it's no wonder that attitudes may become negative and motivation and productivity may decline. What are we as healthcare managers and administrators doing to value and continually train our employees so that staff morale, productivity and patient satisfaction remain high? What are we doing to keep those highly motivated employees motivated and challenged so that they don't get bored and want to move across town to our neighboring hospital or healthcare center? What are we doing to stop our employees from developing the "same job, different day" attitude? A Career Ladder program holds many benefits and opportunities for the motivated employee who seeks and needs additional challenges on the job. It affords them opportunities to learn new skills, demonstrate initiative, accept additional responsibilities and possibly advance into new positions. It also affords them opportunities to grow, to be challenged and to feel like an important and valued member of the radiology team and radiology department. For the manager, a Career Ladder program affords opportunities to retain valuable employees, attract new high-quality employees and maintain a workforce of well-trained highly motivated employees, which in turn will provide high quality products and services to our customers. A Career Ladder program is a "win-win" situation for everyone. For the last twelve months, I have been working with other

  10. Safety program considerations for space nuclear reactor systems

    SciTech Connect

    Cropp, L.O.

    1984-08-01

    This report discusses the necessity for in-depth safety program planning for space nuclear reactor systems. The objectives of the safety program and a proposed task structure is presented for meeting those objectives. A proposed working relationship between the design and independent safety groups is suggested. Examples of safety-related design philosophies are given.