National Library of Energy BETA

Sample records for nuclear age 1945-present

  1. Manhattan Project: Postscript--The Nuclear Age, 1945-Present

    Office of Scientific and Technical Information (OSTI)

    In November 1945, the United States, Britain, and Canada agreed to approach the Soviet Union about negotiating an agreement on international control at the new United Nations. ...

  2. Nuclear Deterrence in the Age of Nonproliferation

    SciTech Connect (OSTI)

    Richardson, J

    2009-01-21

    The fallacy of zero nuclear weapons, even as a virtual goal, is discussed. Because the complete abolition of nuclear weapons is not verifiable, nuclear weapons will always play a role in the calculus of assure, dissuade, deter and defeat (ADDD). However, the relative contribution of nuclear weapons to international security has diminished. To reconstitute the Cold War nuclear capability, with respect to both the nuclear weapons capability and their associated delivery systems, is fiscally daunting and not warranted due to competing budgetary pressures and their relative contribution to international security and nonproliferation. A proposed pathway to a sustainable nuclear weapons capability end-state is suggested which provides enough ADDD; a Dyad composed of fewer delivery and weapon systems, with trickle production at the National Laboratories and private sector to maintain capability and guard against technological surprise.

  3. Nuclear plant-aging research on reactor protection systems

    SciTech Connect (OSTI)

    Meyer, L.C.

    1988-01-01

    This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed.

  4. Computational Age Dating of Special Nuclear Materials

    SciTech Connect (OSTI)

    2012-06-30

    This slide-show presented an overview of the Constrained Progressive Reversal (CPR) method for computing decays, age dating, and spoof detecting. The CPR method is: Capable of temporal profiling a SNM sample; Precise (compared with known decay code, such a ORIGEN); Easy (for computer implementation and analysis).  We have illustrated with real SNM data using CPR for age dating and spoof detection. If SNM is pure, may use CPR to derive its age. If SNM is mixed, CPR will indicate that it is mixed or spoofed.

  5. Aging management guideline for commercial nuclear power plants - heat exchangers

    SciTech Connect (OSTI)

    Booker, S.; Lehnert, D.; Daavettila, N.; Palop, E.

    1994-06-01

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in commercial nuclear power plant heat exchangers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  6. Y-12 hosts NNSA aging infrastructure workshop | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) hosts NNSA aging infrastructure workshop Friday, April 17, 2015 - 3:52pm Y-12 hosts NNSA aging infrastructure workshop Personnel from throughout NNSA and private industry recently gathered in Oak Ridge, Tenn., to discuss lessons learned and brainstorm solutions for dealing with the aging nuclear infrastructure. By focusing on successes in the public and private sectors, attendees were able to discuss the issues in three categories-maintenance, standards and

  7. CP-1 Anniversary: Nuclear Pioneers Remember the Dawn of the Nuclear Age |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Argonne National Laboratory Anniversary: Nuclear Pioneers Remember the Dawn of the Nuclear Age Share Topic Energy Energy sources Nuclear energy On December 2, 1942, 49 scientists, led by Enrico Fermi, made history when Chicago Pile 1 went critical and produced the world's first self-sustaining, controlled nuclear chain reaction. Seventy years later, two of the last surviving CP-1 pioneers, Harold Agnew and Warren Nyer, recall that historic day

  8. Nuclear power plant Generic Aging Lessons Learned (GALL). Appendix B

    SciTech Connect (OSTI)

    Kasza, K.E.; Diercks, D.R.; Holland, J.W.; Choi, S.U.

    1996-12-01

    The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This report consists of Volume 2, which consists of the GALL literature review tables for the NUMARC Industry Reports reviewed for the report.

  9. Report on aging of nuclear power plant reinforced concrete structures

    SciTech Connect (OSTI)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.

    1996-03-01

    The Structural Aging Program provides the US Nuclear Regulatory Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures. The program was organized under four task areas: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technology, and Quantitative Methodology for Continued Service Determinations. Under these tasks, over 90 papers and reports were prepared addressing pertinent aspects associated with aging management of nuclear power plant reinforced concrete structures. Contained in this report is a summary of program results in the form of information related to longevity of nuclear power plant reinforced concrete structures, a Structural Materials Information Center presenting data and information on the time variation of concrete materials under the influence of environmental stressors and aging factors, in-service inspection and condition assessments techniques, repair materials and methods, evaluation of nuclear power plant reinforced concrete structures, and a reliability-based methodology for current and future condition assessments. Recommendations for future activities are also provided. 308 refs., 61 figs., 50 tabs.

  10. Aging management guideline for commercial nuclear power plants-pumps

    SciTech Connect (OSTI)

    Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D.

    1994-03-01

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  11. Aging assessment of large electric motors in nuclear power plants

    SciTech Connect (OSTI)

    Villaran, M.; Subudhi, M.

    1996-03-01

    Large electric motors serve as the prime movers to drive high capacity pumps, fans, compressors, and generators in a variety of nuclear plant systems. This study examined the stressors that cause degradation and aging in large electric motors operating in various plant locations and environments. The operating history of these machines in nuclear plant service was studied by review and analysis of failure reports in the NPRDS and LER databases. This was supplemented by a review of motor designs, and their nuclear and balance of plant applications, in order to characterize the failure mechanisms that cause degradation, aging, and failure in large electric motors. A generic failure modes and effects analysis for large squirrel cage induction motors was performed to identify the degradation and aging mechanisms affecting various components of these large motors, the failure modes that result, and their effects upon the function of the motor. The effects of large motor failures upon the systems in which they are operating, and on the plant as a whole, were analyzed from failure reports in the databases. The effectiveness of the industry`s large motor maintenance programs was assessed based upon the failure reports in the databases and reviews of plant maintenance procedures and programs.

  12. Aging assessment of surge protective devices in nuclear power plants

    SciTech Connect (OSTI)

    Davis, J.F.; Subudhi, M.; Carroll, D.P.

    1996-01-01

    An assessment was performed to determine the effects of aging on the performance and availability of surge protective devices (SPDs), used in electrical power and control systems in nuclear power plants. Although SPDs have not been classified as safety-related, they are risk-important because they can minimize the initiating event frequencies associated with loss of offsite power and reactor trips. Conversely, their failure due to age might cause some of those initiating events, e.g., through short circuit failure modes, or by allowing deterioration of the safety-related component(s) they are protecting from overvoltages, perhaps preventing a reactor trip, from an open circuit failure mode. From the data evaluated during 1980--1994, it was found that failures of surge arresters and suppressers by short circuits were neither a significant risk nor safety concern, and there were no failures of surge suppressers preventing a reactor trip. Simulations, using the ElectroMagnetic Transients Program (EMTP) were performed to determine the adequacy of high voltage surge arresters.

  13. Developing 226Ra and 227Ac age-dating techniques for nuclear...

    Office of Scientific and Technical Information (OSTI)

    The model age or 'date of purification' of a nuclear material is an important nuclear forensic signature. In this study, chemical separation and MC-ICP-MS measurement techniques ...

  14. New Technologies for Repairing Aging Cables in Nuclear Power Plants

    SciTech Connect (OSTI)

    Simmons, Kevin L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westman, Matthew P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-09-11

    The goal of this project is to demonstrate a proof-of-concept for a technique to repair aging cables that have been subjected to degradation associated with long-term thermal and radiation exposure in nuclear power plants. The physical degradation of the aging cables manifests itself primarily as cracking and increased brittleness of the polymeric electrical insulation. Therefore, the proposed cable-repair concept comprises development of techniques to impart a softening agent within the deteriorated polymer insulation jacket so as to regain the ability of the insulation to stretch without failing and possibly to heal existing cracks in the insulation. Our approach is to use commercially available ethylene-propylene rubber (EPR) as the relevant test material, demonstrate the adsorption of chemical treatments in the EPR and quantify changes in resulting physical and mechanical properties. EPR cable samples have been thermally treated in air to produce specimens corresponding to the full range of cable age-performance points from new (>350% elongation at break) to end-of-life (<50% elongation at break). The current focus is on two chemical treatments selected as candidates for restoring age-related cable elasticity loss: a rubber plasticizer and a reactive silane molecule. EPR specimens of 200, 150, 100, and 50% elongation at break have been soaked in the candidate chemical treatments and the kinetics of chemical uptake, measured by change in mass of the samples, has been determined. Mechanical properties as a function of aging and chemical treatment have been measured including ultimate tensile strength, tensile modulus at 50% strain, elongation at break, and storage modulus. Dimensional changes with treatment and changes in glass transition temperature were also investigated. These ongoing experiments are expected to provide insight into the physical-chemical nature of the effect of thermal degradation on EPR rejuvenation limits and to advance novel methods for

  15. Little known heroes of the nuclear age, part 3

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    first to find out the nature of the Soviet nuclear weapons program after World War II,' said Samuel Cohen, the physicist who invented the neutron bomb. 'He got hold of good...

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

    SciTech Connect (OSTI)

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

    1987-08-01

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

  17. Radiation and Thermal Ageing of Nuclear Waste Glass

    SciTech Connect (OSTI)

    Weber, William J [ORNL

    2014-01-01

    The radioactive decay of fission products and actinides incorporated into nuclear waste glass leads to self-heating and self-radiation effects that may affect the stability, structure and performance of the glass in a closed system. Short-lived fission products cause significant self-heating for the first 600 years. Alpha decay of the actinides leads to self-radiation damage that can be significant after a few hundred years, and over the long time periods of geologic disposal, the accumulation of helium and radiation damage from alpha decay may lead to swelling, microstructural evolution and changes in mechanical properties. Four decades of research on the behavior of nuclear waste glass are reviewed.

  18. Living in the Nuclear Age: Families and the threat of nuclear war

    SciTech Connect (OSTI)

    Demorest, D.M.

    1991-01-01

    The main interest of this research was to add to the body of knowledge about the possible psychological impact of the nuclear threat on the family unit. Data were utilized from the Family Interaction, Stress and Nuclear War study conducted by Jules Riskin, M.D. and Victoria Dickerson, Ph.D. at the Mental Research Institute in Palo Alto, California. The sample consisted of ten families who were recruited for this study. In order to examine family-interaction variables and the impact of the threat of nuclear war, a standardized semi-structured family interview was conducted. Topics ranged from ordinary activities to external, non-nuclear stresses such as landslides or hurricanes, to the topic of nuclear war. A distinction is drawn between a family's level of nuclear concern while they discuss nuclear issues and a family's level of nuclear concern when viewed in the context of their overall pattern of family communication. In terms of family coping, family nuclear concern was found to be significantly related to two family-coping strategies. Families who utilized the coping strategies of seeking spiritual support and mobilizing the family to acquire and accept help were significantly less concerned about the threat of nuclear war.

  19. Aging management guideline for commercial nuclear power plants - tanks and pools

    SciTech Connect (OSTI)

    Blocker, E.; Smith, S.; Philpot, L.; Conley, J.

    1996-02-01

    Continued operation of nuclear power plants for periods that extend beyond their original 40-year license period is a desirable option for many U.S. utilities. U.S. Nuclear Regulatory Commission (NRC) approval of operating license renewals is necessary before continued operation becomes a reality. Effective aging management for plant components is important to reliability and safety, regardless of current plant age or extended life expectations. However, the NRC requires that aging evaluations be performed and the effectiveness of aging management programs be demonstrated for components considered within the scope of license renewal before granting approval for operation beyond 40 years. Both the NRC and the utility want assurance that plant components will be highly reliable during both the current license term and throughout the extended operating period. In addition, effective aging management must be demonstrated to support Maintenance Rule (10 CFR 50.65) activities.

  20. Seapower in the nuclear age: NATO as a maritime alliance

    SciTech Connect (OSTI)

    Sokolsky, J.J.

    1986-01-01

    This study examines the North Atlantic Treaty Organization, (NATO), from the perspective of its collective maritime forces; how those forces were organized, what task they were given, and how they related to the broader strategic and political doctrines of the Alliance. Drawing upon much heretofore classified material, the study begins with a history and analysis of the cold water at sea. It then examines the impact of the growth in Soviet maritime capabilities and the adoption by NATO of a strategy of flexible response upon the allied posture at sea. A single chapter is devoted to the reinforcement sealift problem. The concluding chapter discusses NATO and the war at sea in the early 1980s. The study comes to the following basic conclusions: (1) the collective maritime forces of the Alliance, both nuclear and conventional, have had as their tasks the traditional task all maritime forces have had in the past - to exploit the strategic value of the seas for the purposes of conveyance and projection and to deny these usages to the enemy; (2) NATO's maritime posture has been consistent with the overall strategies of the Alliance (3) the strategy of flexible response only increased NATO's need to exploit that strategic value of the seas, but did so at a time when the Soviets were becoming increasingly able to deny NATO effective use of the sea to support its position on the European continent.

  1. Preliminary Aging Assessment of Nuclear Air-Treatment and Cooling System Fans

    SciTech Connect (OSTI)

    Winegardner,, W. K.

    1995-07-01

    A preliminary aging assessment of the fans used in nuclear air treatment and cooling systems was performed by the Pacific Northwest Laboratory as part of the U.S. Nuclear Regulatory Commission's Nuclear Plant Aging Research Program. Details from guides and standards for the design, testing, and installation of fans; results of failure surveys; and information concerning stressors, related aging mechanisms, and inspection, surveillance, and monitoring methods (ISMM) were compiled. Failure surveys suggest that about half of the failures reported for fans are primarily associated with aging. Aging mechanisms associated with the various fan components and resulting from mechanical, thermal, and environmental stressors include wear, fatigue, corrosion, and erosion of metals and the deterioration of belts and lubricants. A bearing is the component most frequently linked to fan failure. The assessment also suggests that ISMM that will detect irregularities arising from improper lubrication, cooling, alignment, and balance of the various components should aid in counteracting many of the aging effects that could impair fan performance. An expanded program, to define and evaluate the adequacy of current ISMM and maintenance practices and to include a documented Phase I aging assessment, is recommended.

  2. Managing aging in nuclear power plants: Insights from NRC`s Maintenance Team Inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.

    1992-12-31

    A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of sixty-seven of the reports issued on these in-depth team inspections have been reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant structures, systems, and components (SSCs). Relevant information has been extracted from these inspection reports sorted into several categories; including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified.

  3. Managing aging in nuclear power plants: Insights from NRC's Maintenance Team Inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.

    1992-01-01

    A plant's maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of sixty-seven of the reports issued on these in-depth team inspections have been reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant structures, systems, and components (SSCs). Relevant information has been extracted from these inspection reports sorted into several categories; including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified.

  4. Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.; Gunther, W.; Grove, E.; Taylor, J.

    1993-12-01

    A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of 67 of the reports issued on these in-depth team inspections were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant systems, structures, and components. Relevant information was extracted from these inspection reports and sorted into several categories, including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified. The information also was sorted according to systems and components, including: Auxiliary Feedwater, Main Feedwater, High Pressure Injection for both BWRs and PWRs, Service Water, Instrument Air, and Emergency Diesel Generator Air Start Systems, and Emergency Diesel Generators Air Start Systems, emergency diesel generators, electrical components such as switchgear, breakers, relays, and motor control centers, motor operated valves and check valves. This information was compared to insights gained from the Nuclear Plant Aging Research (NPAR) Program. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue also are discussed.

  5. Nuclear power plant Generic Aging Lessons Learned (GALL). Main report and appendix A

    SciTech Connect (OSTI)

    Kaza, K.E.; Diercks, D.R.; Holland, J.W.; Choi, S.U.

    1996-12-01

    The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This document is Volume 1, consisting of the executive summary, summary and observations, and an appendix listing the GALL literature review tables.

  6. Aging Management Guideline for commercial nuclear power plants: Motor control centers; Final report

    SciTech Connect (OSTI)

    Toman, G.; Gazdzinski, R.; O`Hearn, E.

    1994-02-01

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) commercial nuclear power plant motor control centers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  7. Aging management guideline for commercial nuclear power plants-stationary batteries. Final report

    SciTech Connect (OSTI)

    Berg, R.; Shao, J.; Krencicki, G.; Giachetti, R.

    1994-03-01

    The Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant stationary batteries important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  8. Aging Management Guideline for commercial nuclear power plants: Electrical switchgear. Final report

    SciTech Connect (OSTI)

    Toman, G.; Gazdzinski, R.; Schuler, K.

    1993-07-01

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant electrical switchgear important to license renewal. The latent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance, to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  9. Aging Management Guideline for commercial nuclear power plants: Power and distribution transformers

    SciTech Connect (OSTI)

    Toman, G.; Gazdzinski, R.

    1994-05-01

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in power and distribution transformers important to license renewal in commercial nuclear power plants. The intent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  10. Structural aging program to assess the adequacy of critical concrete components in nuclear power plants

    SciTech Connect (OSTI)

    Naus, D.J.; Marchbanks, M.F.; Oland, C.B.; Arndt, E.G.

    1989-01-01

    The Structural Aging (SAG) Program is carried out by the Oak Ridge National Laboratory (ORNL) under sponsorship of the United States Nuclear Regulatory Commission (USNRC). The Program has evolved from preliminary studies conducted to evaluate the long-term environmental challenges to light-water reactor safety-related concrete civil structures. An important conclusion of these studies was that a damage methodology, which can provide a quantitative measure of a concrete structure's durability with respect to potential future requirements, needs to be developed. Under the SAG Program, this issue is being addressed through: establishment of a structural materials information center, evaluation of structural component assessment and repair technologies, and development of a quantitative methodology for structural aging determinations. Progress to date of each of these activities is presented as well as future plans. 7 refs., 5 figs.

  11. Aging assessment of essential HVAC chillers used in nuclear power plants. Phase 1, Volume 1

    SciTech Connect (OSTI)

    Blahnik, D.E.; Klein, R.F.

    1993-09-01

    The Pacific Northwest Laboratory conducted a Phase I aging assessment of chillers used in the essential safety air-conditioning systems of nuclear power plants. Centrifugal chillers in the 75- to 750-ton refrigeration capacity range are the predominant type used. The chillers used, and air-conditioning systems served, vary in design from plant-to-plant. It is crucial to keep chiller internals very clean and to prevent the leakage of water, air, and other contaminants into the refrigerant containment system. Periodic operation on a weekly or monthly basis is necessary to remove moisture and noncondensable gases that gradually build up inside the chiller. This is especially desirable if a chiller is required to operate only as an emergency standby unit. The primary stressors and aging mechanisms that affect chillers include vibration, excessive temperatures and pressures, thermal cycling, chemical attack, and poor quality cooling water. Aging is accelerated by moisture, non-condensable gases (e.g., air), dirt, and other contamination within the refrigerant containment system, excessive start/stop cycling, and operating below the rated capacity. Aging is also accelerated by corrosion and fouling of the condenser and evaporator tubes. The principal cause of chiller failures is lack of adequate monitoring. Lack of performing scheduled maintenance and human errors also contribute to failures.

  12. Cable Polymer Aging and Condition Monitoring Research at Sandia National Laboratores Under the Nuclear Energy Plant Optimization (NEPO) Program

    SciTech Connect (OSTI)

    K. Gillen; R. Assink; R. Bernstein

    2005-12-23

    This report describes cable polymer aging and condition monitoring research performed at Sandia National Laboratories under the Nuclear Energy Plant Optimization (NEPO) Program from 2000 to 2005. The research results apply to low-voltage cable insulation and Program from 2000 to 2005. The research results apply to low-voltage cable insulation and jacket materials that are commonly used in U.S. nuclear power plants. The research builds upon and is liked to research performed at Sandia from 1977 through 1986, sponsored by the U.S. Nuclear Regulatory Commission. Aged and unaged specimens from that research remained available and were subjected to further testing under the NEPO research effort.The documented results from the earlier research were complemented by subjecting the specimens to new condition monitoring tests. Additional aging regimens were applied to additional specimens to develop aging models for key cable jacket and insulation materials

  13. Aging assessment of essential HVAC chillers used in nuclear power plants

    SciTech Connect (OSTI)

    Blahnik, D.E.; Camp, T.W.

    1996-09-01

    The Pacific Northwest Laboratory conducted a comprehensive aging assessment of chillers used in the essential safety air-conditioning systems in nuclear power plants (NPPs). The chillers used, and air-conditioning systems served, vary in design from plant to plant. The review of operating experience indicated that chillers experience aging degradation and failures. The primary aging factors of concern for chillers include vibration, excessive temperatures and pressures, thermal cycling, chemical attack, and poor quality cooling water. The evaluation of Licensee Event Reports (LERs) indicated that about 38% of the failures were primarily related to aging, 55% were partially aging related, and 7% of the failures were unassignable. About 25% of the failures were primarily caused by human, design, procedure, and other errors. The large number of errors is probably directly related to the complexity of chillers and their interfacing systems. Nearly all of the LERs were the result of entering plant Technical Specification Limiting Condition for Operation (LCO) that initiated remedial actions like plant shutdown procedures. The trend for chiller-related LERs has stabilized at about 0.13 LERs per plant year since 1988. Carefully following the vendor procedures and monitoring the equipment can help to minimize and/or eliminate most of the premature failures. Recording equipment performance can be useful for trending analysis. Periodic operation for a few hours on a weekly or monthly basis is useful to remove moisture and non-condensable gases that gradually build up inside the chiller. Chiller pressurization kits are available that will help minimize the amount of moisture and air ingress to low-pressure chillers during standby periods. The assessment of service life condition monitoring of chillers indicated there are many simple to sophisticated methods available that can help in chiller surveillance and monitoring.

  14. FORMATION AND EVOLUTION OF NUCLEAR STAR CLUSTERS WITH IN SITU STAR FORMATION: NUCLEAR CORES AND AGE SEGREGATION

    SciTech Connect (OSTI)

    Aharon, Danor; Perets, Hagai B.

    2015-02-01

    Nuclear stellar cluster (NSCs) are known to exist around massive black holes (MBHs) in galactic nuclei. Two formation scenarios were suggested for their origin: (1) buildup of NSCs from consecutive infall of stellar clusters and (2) continuous in situ star formation. Though the cluster infall scenario has been extensively studied, the in situ formation scenario has been hardly explored. Here we use Fokker-Planck (FP) calculations to study the effects of star formation on the buildup of NSCs and its implications for their long-term evolution and their resulting structure. We use the FP equation to describe the evolution of stellar populations and add appropriate source terms to account for the effects of newly formed stars. We show that continuous star formation even 1-2 pc away from the MBH can lead to the buildup of an NSC with properties similar to those of the Milky Way NSC. We find that the structure of the old stellar population in the NSC with in situ star formation could be very similar to the steady-state Bahcall-Wolf cuspy structure. However, its younger populations do not yet achieve a steady state. In particular, formed/evolved NSCs with in situ star formation contain differential age-segregated stellar populations that are not yet fully mixed. Younger stellar populations formed in the outer regions of the NSC have a cuspy structure toward the NSC outskirts, while showing a core-like distribution inward, with younger populations having larger core sizes. In principal, such a structure can give rise to an apparent core-like radial distribution of younger stars, as observed in the Galactic center.

  15. NMR (Nuclear Magnetic Resonance) studies of aging effects in palladium tritide

    SciTech Connect (OSTI)

    Abell, G.C.; Attalla, A.

    1988-01-01

    This paper presents Nuclear Magnetic Resonance (NMR) studies of aging phenomena in palladium tritide. /sup 3/He NMR relaxation parameters have been measured as a function of temperature for 6-, 13-, and 22-month-old beta phase palladium tritide. The most significant result of this study is the observation of a solid/fluid phase transition near 250/degree/K of /sup 3/He that has accumulated in the PdT/sub x/ substrate via triton decay. Although the existence of solid helium at relatively high temperatures had been predicted for helium in metals, it had not previously been confirmed in any metal/helium system. The observed melting temperatures, together with the known equation of state for /sup 4/He, allow a determination of the helium density as a function of age. The atomic density obtained in this way is approximately 2.0 times that of palladium metal, agreeing with densities inferred from dilatometric measurements of other metal tritides and also with predictions based on the concept of dislocation loop punching by highly overpressurized He bubbles. The /sup 3/He signal in the 22-month-old sample was sufficiently strong to allow a detailed study of melting as a function of temperature, and provides information on the distribution of densities over the ensemble of bubbles.

  16. Review of nuclear power plant safety cable aging studies with recommendations for improved approaches and for future work.

    SciTech Connect (OSTI)

    Gillen, Kenneth Todd; Bernstein, Robert

    2010-11-01

    Many U. S. nuclear power plants are approaching 40 years of age and there is a desire to extend their life for up to 100 total years. Safety-related cables were originally qualified for nuclear power plant applications based on IEEE Standards that were published in 1974. The qualifications involved procedures to simulate 40 years of life under ambient power plant aging conditions followed by simulated loss of coolant accident (LOCA). Over the past 35 years or so, substantial efforts were devoted to determining whether the aging assumptions allowed by the original IEEE Standards could be improved upon. These studies led to better accelerated aging methods so that more confident 40-year lifetime predictions became available. Since there is now a desire to potentially extend the life of nuclear power plants way beyond the original 40 year life, there is an interest in reviewing and critiquing the current state-of-the-art in simulating cable aging. These are two of the goals of this report where the discussion is concentrated on the progress made over the past 15 years or so and highlights the most thorough and careful published studies. An additional goal of the report is to suggest work that might prove helpful in answering some of the questions and dealing with some of the issues that still remain with respect to simulating the aging and predicting the lifetimes of safety-related cable materials.

  17. Aging Management Guideline for commercial nuclear power plants: Battery chargers, inverters and uninterruptible power supplies. Final report

    SciTech Connect (OSTI)

    Berg, R.; Stroinski, M.; Giachetti, R.

    1994-02-01

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant battery chargers, inverters and uninterruptible power supplies important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already, experienced) and aging management program activities to the more generic results and recommendations presented herein.

  18. Ancient Glass in the Nuclear Age- Denis Strachan and Joseph Ryan

    Broader source: Energy.gov [DOE]

    PNNL scientists are studying pieces of ancient Roman glass from 1,800-year-old shipwrecks and ruins to assist today's efforts to safely store nuclear waste.

  19. Nuclear power plant cable materials : review of qualification and currently available aging data for margin assessments in cable performance.

    SciTech Connect (OSTI)

    Celina, Mathias Christopher; Gillen, Kenneth Todd; Lindgren, Eric Richard

    2013-05-01

    A selective literature review was conducted to assess whether currently available accelerated aging and original qualification data could be used to establish operational margins for the continued use of cable insulation and jacketing materials in nuclear power plant environments. The materials are subject to chemical and physical degradation under extended radiationthermal- oxidative conditions. Of particular interest were the circumstances under which existing aging data could be used to predict whether aged materials should pass loss of coolant accident (LOCA) performance requirements. Original LOCA qualification testing usually involved accelerated aging simulations of the 40-year expected ambient aging conditions followed by a LOCA simulation. The accelerated aging simulations were conducted under rapid accelerated aging conditions that did not account for many of the known limitations in accelerated polymer aging and therefore did not correctly simulate actual aging conditions. These highly accelerated aging conditions resulted in insulation materials with mostlyinert' aging processes as well as jacket materials where oxidative damage dropped quickly away from the air-exposed outside jacket surface. Therefore, for most LOCA performance predictions, testing appears to have relied upon heterogeneous aging behavior with oxidation often limited to the exterior of the cable cross-section - a situation which is not comparable with the nearly homogenous oxidative aging that will occur over decades under low dose rate and low temperature plant conditions. The historical aging conditions are therefore insufficient to determine with reasonable confidence the remaining operational margins for these materials. This does not necessarily imply that the existing 40-year-old materials would fail if LOCA conditions occurred, but rather that unambiguous statements about the current aging state and anticipated LOCA performance cannot be provided based on original

  20. Round-robin 230Th–234U age dating of bulk uranium for nuclear forensics

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Gaffney, Amy M.; Hubert, Amélie; Kinman, William S.; Magara, Masaaki; Okubo, Ayako; Pointurier, Fabien; Schorzman, Kerri C.; Steiner, Robert E.; Williams, Ross W.

    2015-07-30

    In an inter-laboratory measurement comparison study, four laboratories determined 230Th–234U model ages of uranium certified reference material NBL U050 using isotope dilution mass spectrometry. The model dates determined by the participating laboratories range from 9 March 1956 to 19 October 1957, and are indistinguishable given the associated measurement uncertainties. As a result, these model ages are concordant with to slightly older than the known production age of NBL U050.

  1. New Technologies for Repairing Aging Cables in Nuclear Power Plants: M3LW-14OR0404015 Cable Rejuvenation Report

    SciTech Connect (OSTI)

    Simmons, Kevin L.; Fifield, Leonard S.; Westman, Matthew P.; Roberts, John A.

    2014-09-08

    The goal of this project is to conceptually demonstrate techniques to repair cables that have degraded through subjection to long-term thermal and radiation exposure in nuclear power plants. In fiscal year 2014 (FY14) we focused on commercially available ethylene-propylene rubber (EPR) as the relevant test material, isolated a high surface area form of the EPR material to facilitate chemical treatment screening and charaterization, and measured chemical changes in the material due to aging and treatment using Fourier Transfrom Infrared (FTIR) spectroscopy.

  2. nuclear

    National Nuclear Security Administration (NNSA)

    2%2A en U.S-, Japan Exchange Best Practices on Nuclear Emergency Response http:nnsa.energy.govmediaroompressreleasesu.s-japan-exchange-best-practices-nuclear-emergency-respon...

  3. LWR Sustainability: Assessment of Aging of Nuclear Power Plant Safety Related Concrete Strutures

    SciTech Connect (OSTI)

    Graves III, Herman; Naus, Dan J

    2013-01-01

    Current regulatory testing and inspection requirements are reviewed and a summary of degradation experience is presented. Techniques commonly used to inspect NPP concrete structures to assess and quantify age-related degradation are summarized. An approach for conduct of condition assessments of structures in NPPs is presented. Criteria, based primarily on visual indications, are provided for use in classification and assessment of concrete degradation. Materials and techniques for repair of degraded structures are generally discussed.

  4. State of the Art Assessment of NDE Techniques for Aging Cable Management in Nuclear Power Plants FY2015

    SciTech Connect (OSTI)

    Glass, Samuel W.; Fifield, Leonard S.; Dib, Gerges; Tedeschi, Jonathan R.; Jones, Anthony M.; Hartman, Trenton S.

    2015-09-08

    This milestone report presents an update on the state-of-the-art review and research being conducted to identify key indicators of in-containment cable aging at nuclear power plants (NPPs), and devise in-situ measurement techniques that are sensitive to these key indicators. The motivation for this study stems from the need to address open questions related to nondestructive evaluation (NDE) of aging cables for degradation detection and estimation of condition-based remaining service life. These questions arise within the context of a second round of license extension for NPPs that would extend the operating license to 60 and 80 years. Within the introduction, a review of recently published U.S. and international research and guidance for cable aging management programs including NDE technologies is provided. As with any “state-of-the-art” report, the observations are deemed accurate as of the publication date but cannot anticipate evolution of the technology. Moreover, readers are advised that research and development of cable NDE technology is an ongoing issue of global concern.

  5. Nuclear Energy Plant Optimization (NEPO) final report on aging and condition monitoring of low-voltage cable materials.

    SciTech Connect (OSTI)

    Assink, Roger Alan; Gillen, Kenneth Todd; Bernstein, Robert

    2005-11-01

    This report summarizes results generated on a 5-year cable-aging program that constituted part of the Nuclear Energy Plant Optimization (NEPO) program, an effort cosponsored by the U. S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The NEPO cable-aging effort concentrated on two important issues involving the development of better lifetime prediction methods as well as the development and testing of novel cable condition-monitoring (CM) techniques. To address improved life prediction methods, we first describe the use of time-temperature superposition principles, indicating how this approach improves the testing of the Arrhenius model by utilizing all of the experimentally generated data instead of a few selected and processed data points. Although reasonable superposition is often found, we show several cases where non-superposition is evident, a situation that violates the constant acceleration assumption normally used in accelerated aging studies. Long-term aging results over extended temperature ranges allow us to show that curvature in Arrhenius plots for elongation is a common occurrence. In all cases the curvature results in a lowering of the Arrhenius activation energy at lower temperatures implying that typical extrapolation of high temperature results over-estimates material lifetimes. The long-term results also allow us to test the significance of extrapolating through the crystalline melting point of semi-crystalline materials. By utilizing ultrasensitive oxygen consumption (UOC) measurements, we show that it is possible to probe the low temperature extrapolation region normally inaccessible to conventional accelerated aging studies. This allows the quantitative testing of the often-used Arrhenius extrapolation assumption. Such testing indicates that many materials again show evidence of ''downward'' curvature (E{sub a} values drop as the aging temperature is lowered) consistent with the limited elongation results and

  6. Flaw Stability Considering Residual Stress for Aging Management of Spent Nuclear Fuel Multiple-Purpose Canisters

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Lam, Poh-Sang; Sindelar, Robert L.

    2016-04-28

    A typical multipurpose canister (MPC) is made of austenitic stainless steel and is loaded with spent nuclear fuel assemblies. Because heat treatment for stress relief is not required for the construction of the MPC, the canister is susceptible to stress corrosion cracking in the weld or heat affected zone regions under long-term storage conditions. Logic for flaw acceptance is developed should crack-like flaws be detected by Inservice Inspection. The procedure recommended by API 579-1/ASME FFS-1, Fitness-for-Service, is used to calculate the instability crack length or depth by failure assessment diagram. It is demonstrated that the welding residual stress has amore » strong influence on the results.« less

  7. Development of flaw acceptance criteria for aging management of spent nuclear fuel multi-purpose canisters

    SciTech Connect (OSTI)

    Lam, Poh -Sang; Sindelar, Robert L.

    2015-03-09

    A typical multipurpose canister (MPC) is made of austenitic stainless steel and is loaded with spent nuclear fuel assemblies. The canister may be subject to service-induced degradation when it is exposed to aggressive atmospheric environments during a possibly long-term storage period if the permanent repository is yet to be identified and readied. Because heat treatment for stress relief is not required for the construction of an MPC, stress corrosion cracking may be initiated on the canister surface in the welds or in the heat affected zone. An acceptance criteria methodology is being developed for flaw disposition should the crack-like defects be detected by periodic in-service Inspection. The first-order instability flaw sizes has been determined with bounding flaw configurations, that is, through-wall axial or circumferential cracks, and part-through-wall long axial flaw or 360° circumferential crack. The procedure recommended by the American Petroleum Institute (API) 579 Fitness-for-Service code (Second Edition) is used to estimate the instability crack length or depth by implementing the failure assessment diagram (FAD) methodology. The welding residual stresses are mostly unknown and are therefore estimated with the API 579 procedure. It is demonstrated in this paper that the residual stress has significant impact on the instability length or depth of the crack. The findings will limit the applicability of the flaw tolerance obtained from limit load approach where residual stress is ignored and only ligament yielding is considered.

  8. Development of flaw acceptance criteria for aging management of spent nuclear fuel multiple-purpose canisters

    SciTech Connect (OSTI)

    Lam, P.; Sindelar, R.

    2015-03-09

    A typical multipurpose canister (MPC) is made of austenitic stainless steel and is loaded with spent nuclear fuel assemblies. The canister may be subject to service-induced degradation when it is exposed to aggressive atmospheric environments during a possibly long-term storage period if the permanent repository is yet to be identified and readied. Because heat treatment for stress relief is not required for the construction of an MPC, stress corrosion cracking may be initiated on the canister surface in the welds or in the heat affected zone. An acceptance criteria methodology is being developed for flaw disposition should the crack-like defects be detected by periodic In-service Inspection. The first-order instability flaw sizes has been determined with bounding flaw configurations, that is, through-wall axial or circumferential cracks, and part-through-wall long axial flaw or 360° circumferential crack. The procedure recommended by the American Petroleum Institute (API) 579 Fitness-for-Service code (Second Edition) is used to estimate the instability crack length or depth by implementing the failure assessment diagram (FAD) methodology. The welding residual stresses are mostly unknown and are therefore estimated with the API 579 procedure. It is demonstrated in this paper that the residual stress has significant impact on the instability length or depth of the crack. The findings will limit the applicability of the flaw tolerance obtained from limit load approach where residual stress is ignored and only ligament yielding is considered.

  9. Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants – Interim Study FY13

    SciTech Connect (OSTI)

    Simmons, Kevin L.; Fifield, Leonard S.; Westman, Matthew P.; Ramuhalli, Pradeep; Pardini, Allan F.; Tedeschi, Jonathan R.; Jones, Anthony M.

    2013-09-27

    warning of aging and degradation. Examples of such key indicators include changes in chemical structure, mechanical modulus, and dielectric permittivity. While some of these indicators are the basis of currently used technologies, there is a need to increase the volume of cable that may be inspected with a single measurement, and if possible, to develop techniques for in-situ inspection (i.e., while the cable is in operation). This is the focus of the present report.

  10. Light Water Reactor Sustainability (LWRS) Program – Non-Destructive Evaluation (NDE) R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants

    SciTech Connect (OSTI)

    Simmons, Kevin L.; Ramuhalli, Pradeep; Brenchley, David L.; Coble, Jamie B.; Hashemian, Hash; Konnik, Robert; Ray, Sheila

    2012-09-14

    The purpose of the non-destructive evaluation (NDE) R&D Roadmap for Cables is to support the Materials Aging and Degradation (MAaD) R&D pathway. The focus of the workshop was to identify the technical gaps in detecting aging cables and predicting their remaining life expectancy. The workshop was held in Knoxville, Tennessee, on July 30, 2012, at Analysis and Measurement Services Corporation (AMS) headquarters. The workshop was attended by 30 experts in materials, electrical engineering, U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) National Laboratories (Oak Ridge National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and Idaho National Engineering Laboratory), NDE instrumentation development, universities, commercial NDE services and cable manufacturers, and Electric Power Research Institute (EPRI). The motivation for the R&D roadmap comes from the need to address the aging management of in-containment cables at nuclear power plants (NPPs).

  11. Developing 226Ra and 227Ac age-dating techniques for nuclear forensics to gain insight from concordant and non-concordant radiochronometers

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Kayzar, Theresa M.; Williams, Ross W.

    2015-09-26

    The model age or ‘date of purification’ of a nuclear material is an important nuclear forensic signature. In this study, chemical separation and MC-ICP-MS measurement techniques were developed for 226 Ra and 227Ac: grand-daughter nuclides in the 238U and 235U decay chains respectively. The 230Th-234U, 226Ra-238U, 231Pa-235U, and 227Ac-235U radiochronometers were used to calculate model ages for CRM-U100 standard reference material and two highly-enriched pieces of uranium metal from the International Technical Working Group Round Robin 3 Exercise. In conclusion, the results demonstrate the accuracy of the 226Ra-238U and 227Ac-235U chronometers and provide information about nuclide migration during uranium processing.

  12. Multipurpose Transportation, Aging, and Disposal Canisters for Used Nuclear Fuel - Getting From Here to There and Beyond

    SciTech Connect (OSTI)

    McCullum, R.

    2008-07-01

    The idea of a universal canister system, in which used fuel can be placed at reactor sites, transported and - without ever needing to be re-opened -, disposed of in a geologic repository, is certainly not new. Originally proposed by DOE in the early 1990's as the Multi-Purpose Canister (MPC) system, this common sense idea has always had considerable appeal as a means to reduce used fuel handling and simplify repository surface facility operations. However, difficulties in launching the development of such a system, in the face of large uncertainties in repository design and limited program funding, caused the original MPC project to be abandoned in 1997. Then, after eight years of inactivity in this area, DOE, while experiencing difficulty completing the repository surface facility design and having missed a December 2004 deadline for submittal of a repository license application to the Nuclear Regulatory Commission (NRC), re-proposed the concept. Under this renewed initiative, the MPC systems were renamed as Transportation, Aging, and Disposal or TAD canister systems. DOE's repository design had advanced significantly at this point and industry, having gained considerable experience through the design, licensing, manufacture, and loading of over 800 used fuel dry storage systems, was well positioned to provide DOE with the meaningful technical input that would be necessary to bring the TAD concept to reality. With a firm foundation on which to build, industry actively engaged DOE in an extensive series of interactions to facilitate TAD development. This paper describes the evolution of the TAD concept through the industry/DOE dialogue that occurred over an 18 month period beginning in January 2006. It discusses the technical issues that were addressed and resolved through this collaboration. Successful completion of this dialogue led to the issuance, by DOE, of a final TAD design specification in July, 2007. This specification is being used by DOE as a fundamental

  13. International Atomic Energy Agency specialists meeting on experience in ageing, maintenance, and modernization of instrumentation and control systems for improving nuclear power plant availability

    SciTech Connect (OSTI)

    Not Available

    1993-10-01

    This report presents the proceedings of the Specialist`s Meeting on Experience in Aging, Maintenance and Modernization of Instrumentation and Control Systems for Improving Nuclear Power Plant Availability that was held at the Ramada Inn in Rockville, Maryland on May 5--7, 1993. The Meeting was presented in cooperation with the Electric Power Research Institute, Oak Ridge National Laboratory and the International Atomic Energy Agency. There were approximately 65 participants from 13 countries at the Meeting. Individual reports have been cataloged separately.

  14. Light Water Reactor Sustainability (LWRS) Program – Non-Destructive Evaluation (NDE) R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants

    SciTech Connect (OSTI)

    Simmons, K.L.; Ramuhali, P.; Brenchley, D.L.; Coble, J.B.; Hashemian, H.M.; Konnick, R.; Ray, S.

    2012-09-01

    Executive Summary [partial] The purpose of the non-destructive evaluation (NDE) R&D Roadmap for Cables is to support the Materials Aging and Degradation (MAaD) R&D pathway. A workshop was held to gather subject matter experts to develop the NDE R&D Roadmap for Cables. The focus of the workshop was to identify the technical gaps in detecting aging cables and predicting their remaining life expectancy. The workshop was held in Knoxville, Tennessee, on July 30, 2012, at Analysis and Measurement Services Corporation (AMS) headquarters. The workshop was attended by 30 experts in materials, electrical engineering, and NDE instrumentation development from the U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) National Laboratories (Oak Ridge National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and Idaho National Engineering Laboratory), universities, commercial NDE service vendors and cable manufacturers, and the Electric Power Research Institute (EPRI).

  15. Evaluating the Effects of Aging on Electronic Instrument and Control Circuit Boards and Components in Nuclear Power Plants

    SciTech Connect (OSTI)

    G. William Hannaman; C. Dan Wilkinson

    2005-05-15

    The report describes potentially useful techniques for monitoring the aging of I&C boards. The techniques have been grouped into: periodic testing, reliability modeling, resistance measures, signal comparison, eternal measures, and internal measures, each representing distinct theoretical approaches to detection and evaluation.

  16. Aging and service wear of air-operated valves used in safety-related systems at nuclear power plants

    SciTech Connect (OSTI)

    Cox, D.F.; McElhaney, K.L.; Staunton, R.H.

    1995-05-01

    Air-operated valves (AOVs) are used in a variety of safety-related applications at nuclear power plants. They are often used where rapid stroke times are required or precise control of the valve obturator is required. They can be designed to operate automatically upon loss of power, which is often desirable when selecting components for response to design basis conditions. The purpose of this report is to examine the reported failures of AOVs and determine whether there are identifiable trends in the failures related to predictable causes. This report examines the specific components that comprise a typical AOV, how those components fail, when they fail, and how such failures are discovered. It also examines whether current testing frequencies and methods are effective in predicting such failures.

  17. Review of Recent Aging-Related Degradation Occurrences of Structures and Passive Components in U.S. Nuclear Power Plants

    SciTech Connect (OSTI)

    Nie,J.; Braverman, J.; Hofmayer, C.; Choun, Y.-S.; Kim, M.K.; Choi, I.-K.

    2009-04-02

    The Korea Atomic Energy Research Institute (KAERI) and Brookhaven National Laboratory (BNL) are collaborating to develop seismic capability evaluation technology for degraded structures and passive components (SPCs) under a multi-year research agreement. To better understand the status and characteristics of degradation of SPCs in nuclear power plants (NPPs), the first step in this multi-year research effort was to identify and evaluate degradation occurrences of SPCs in U.S. NPPs. This was performed by reviewing recent publicly available information sources to identify and evaluate the characteristics of degradation occurrences and then comparing the information to the observations in the past. Ten categories of SPCs that are applicable to Korean NPPs were identified, comprising of anchorage, concrete, containment, exchanger, filter, piping system, reactor pressure vessel, structural steel, tank, and vessel. Software tools were developed to expedite the review process. Results from this review effort were compared to previous data in the literature to characterize the overall degradation trends.

  18. Final LDRD report : nanoscale mechanisms in advanced aging of materials during storage of spent %22high burnup%22 nuclear fuel.

    SciTech Connect (OSTI)

    Clark, Blythe G.; Rajasekhara, Shreyas; Enos, David George; Dingreville, Remi Philippe Michel; Doyle, Barney Lee; Hattar, Khalid Mikhiel; Weiner, Ruth F.

    2013-09-01

    We present the results of a three-year LDRD project focused on understanding microstructural evolution and related property changes in Zr-based nuclear cladding materials towards the development of high fidelity predictive simulations for long term dry storage. Experiments and modeling efforts have focused on the effects of hydride formation and accumulation of irradiation defects. Key results include: determination of the influence of composition and defect structures on hydride formation; measurement of the electrochemical property differences between hydride and parent material for understanding and predicting corrosion resistance; in situ environmental transmission electron microscope observation of hydride formation; development of a predictive simulation for mechanical property changes as a function of irradiation dose; novel test method development for microtensile testing of ionirradiated material to simulate the effect of neutron irradiation on mechanical properties; and successful demonstration of an Idaho National Labs-based sample preparation and shipping method for subsequent Sandia-based analysis of post-reactor cladding.

  19. Submerged Medium Voltage Cable Systems at Nuclear Power Plants. A Review of Research Efforts Relevant to Aging Mechanisms and Condition Monitoring

    SciTech Connect (OSTI)

    Brown, Jason; Bernstein, Robert; White, II, Gregory Von; Glover, Steven F.; Neely, Jason C.; Pena, Gary; Williamson, Kenneth Martin; Zutavern, Fred J.; Gelbard, Fred

    2015-03-01

    and industrial literature was performed to identify : 1) findings regarding the degradation mechanisms of submerged cabling and 2) condition monitoring methods that may prove useful in predict ing the remaining lifetime of submerged medium voltage p ower cables . The re search was conducted by a multi - disciplinary team , and s ources includ ed official NRC reports, n ational l aboratory reports , IEEE standards, conference and journal proceedings , magazine articles , PhD dissertations , and discussions with experts . The purpose of this work was to establish the current state - of - the - art in material degradation modeling and cable condition monitoring techniques and to identify research gaps . Subsequently, future areas of focus are recommended to address these research gaps and thus strengthen the efficacy of the NRC's developing cable condition monitoring program . Results of this literature review and details of the test ing recommendations are presented in this report . FOREWORD To ensure the safe, re liable, and cost - effective long - term operation of nuclear power plants, many systems, structures, and components must be continuously evaluated. The Nuclear Regulatory Commission (NRC) has identified that cables in submerged environments are of concern, particularly as plants are seeking license renewal. To date, there is a lack of consensus on aging and degradation mechanisms even though the area of submerged cables has been extensively studied. Consequently, the ability to make lifetime predictions for submerged cable does not yet exist. The NRC has engaged Sandia National Laboratories (SNL) to lead a coordinated effort to help elucidate the aging and degradation of cables in submerged environments by collaborating with cable manufacturers, utilities, universities, and other government agencies. A team of SNL experts was assembled from the laboratories including electrical condition monitoring, mat erial science, polymer degradation, plasma physics

  20. Round-robin 230Th–234U age dating of bulk uranium for nuclear forensics

    SciTech Connect (OSTI)

    Gaffney, Amy M.; Hubert, Amélie; Kinman, William S.; Magara, Masaaki; Okubo, Ayako; Pointurier, Fabien; Schorzman, Kerri C.; Steiner, Robert E.; Williams, Ross W.

    2015-07-30

    In an inter-laboratory measurement comparison study, four laboratories determined 230Th–234U model ages of uranium certified reference material NBL U050 using isotope dilution mass spectrometry. The model dates determined by the participating laboratories range from 9 March 1956 to 19 October 1957, and are indistinguishable given the associated measurement uncertainties. As a result, these model ages are concordant with to slightly older than the known production age of NBL U050.

  1. Round-robin 230Th234U age dating of bulk uranium for nuclear forensics

    SciTech Connect (OSTI)

    Gaffney, Amy M.; Hubert, Amlie; Kinman, William S.; Magara, Masaaki; Okubo, Ayako; Pointurier, Fabien; Schorzman, Kerri C.; Steiner, Robert E.; Williams, Ross W.

    2015-07-30

    In an inter-laboratory measurement comparison study, four laboratories determined 230Th234U model ages of uranium certified reference material NBL U050 using isotope dilution mass spectrometry. The model dates determined by the participating laboratories range from 9 March 1956 to 19 October 1957, and are indistinguishable given the associated measurement uncertainties. As a result, these model ages are concordant with to slightly older than the known production age of NBL U050.

  2. Light Water Reactor Sustainability Program – Non-Destructive Evaluation R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants

    Broader source: Energy.gov [DOE]

    The purpose of the non-destructive evaluation (NDE) R&D Roadmap for Cables is to support the Materials Aging and Degradation (MAaD) R&D pathway. A workshop was held to gather subject matter...

  3. Influence of long-term thermal aging on the microstructural evolution of nuclear reactor pressure vessel materials: An atom probe study

    SciTech Connect (OSTI)

    Pareige, P.; Russell, K.F.; Stoller, R.E.; Miller, M.K.

    1998-03-01

    Atom probe field ion microscopy (APFIM) investigations of the microstructure of unaged (as-fabricated) and long-term thermally aged ({approximately} 100,000 h at 280 C) surveillance materials from commercial reactor pressure vessel steels were performed. This combination of materials and conditions permitted the investigation of potential thermal-aging effects. This microstructural study focused on the quantification of the compositions of the matrix and carbides. The APFIM results indicate that there was no significant microstructural evolution after a long-term thermal exposure in weld, plate, or forging materials. The matrix depletion of copper that was observed in weld materials was consistent with the copper concentration in the matrix after the stress-relief heat treatment. The compositions of cementite carbides aged for 100,000 h were compared with the Thermocalc{trademark} prediction. The APFIM comparisons of materials under these conditions are consistent with the measured change in mechanical properties such as the Charpy transition temperature.

  4. Developing 226Ra and 227Ac age-dating techniques for nuclear forensics to gain insight from concordant and non-concordant radiochronometers

    SciTech Connect (OSTI)

    Kayzar, Theresa M.; Williams, Ross W.

    2015-09-26

    The model age or ‘date of purification’ of a nuclear material is an important nuclear forensic signature. In this study, chemical separation and MC-ICP-MS measurement techniques were developed for 226 Ra and 227Ac: grand-daughter nuclides in the 238U and 235U decay chains respectively. The 230Th-234U, 226Ra-238U, 231Pa-235U, and 227Ac-235U radiochronometers were used to calculate model ages for CRM-U100 standard reference material and two highly-enriched pieces of uranium metal from the International Technical Working Group Round Robin 3 Exercise. In conclusion, the results demonstrate the accuracy of the 226Ra-238U and 227Ac-235U chronometers and provide information about nuclide migration during uranium processing.

  5. Signatures of aging

    SciTech Connect (OSTI)

    Cornwall, J.; Dyson, F.; Garwin, R.; Hammer, D.; Happer, W.; Lewis, N.; Schwitters, R.; Sullivan, J.; Williams, E.

    1998-01-06

    The Department of Energy and its three weapons laboratories (LANL, LLNL, and SNL) have developed a Stockpile Stewardship and Management Program (SSMP) in response to their designated mission of maintaining an effective, i.e. reliable and safe, nuclear deterrent without underground nuclear tests (UGTs). The need to ensure the effectiveness of an aging stockpile presents new challenges of major importance. In this study we review what is known about the aging of critical constituents, particularly the high explosives, polymers, and metals in the enduring stockpile. We discuss data that are required to provide a fuller understanding of aging, and how to obtain that data as a basis for anticipating and addressing potential stockpile problems. Our particular concern is problems that may arise in the short term, i.e. within the next 5 to 10 years, and their implied requirements for preventive maintenance and remanufacture.

  6. Nuclear Energy Advisory Committee

    Broader source: Energy.gov (indexed) [DOE]

    ... aging of used nuclear fuel in storage (dry casks). ... fast reactors has been signed with France and Japan. ... the Air Force asked for SMRs to power air force bases. ...

  7. Coal Fleet Aging Meeting

    U.S. Energy Information Administration (EIA) Indexed Site

    7, 2016 MEMORANDUM TO: Dr. Ian Mead Assistant Administrator for Energy Analysis Jim Diefenderfer Director, Office of Electricity, Coal, Nuclear, and Renewables Analysis FROM: Coal and Uranium Analysis Team SUBJECT: Notes from the Coal Fleet Aging Meeting held on June 14, 2016 Attendees (36) *Indicates attendance via WebEx. 2 Framing the question This adjunct meeting of the AEO Coal Working Group (CWG) was held as a follow up to the previous Future Operating and Maintenance Considerations for the

  8. Nuclear Science

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Science Nuclear Science Experimental and theoretical nuclear research carried out at NERSC is driven by the quest for improving our understanding of the building blocks of...

  9. Design Evolution Study - Aging Options

    SciTech Connect (OSTI)

    P. McDaniel

    2002-04-05

    The purpose of this study is to identify options and issues for aging commercial spent nuclear fuel received for disposal at the Yucca Mountain Mined Geologic Repository. Some early shipments of commercial spent nuclear fuel to the repository may be received with high-heat-output (younger) fuel assemblies that will need to be managed to meet thermal goals for emplacement. The capability to age as much as 40,000 metric tons of heavy metal of commercial spent nuclear he1 would provide more flexibility in the design to manage this younger fuel and to decouple waste receipt and waste emplacement. The following potential aging location options are evaluated: (1) Surface aging at four locations near the North Portal; (2) Subsurface aging in the permanent emplacement drifts; and (3) Subsurface aging in a new subsurface area. The following aging container options are evaluated: (1) Complete Waste Package; (2) Stainless Steel inner liner of the waste package; (3) Dual Purpose Canisters; (4) Multi-Purpose Canisters; and (5) New disposable canister for uncanistered commercial spent nuclear fuel. Each option is compared to a ''Base Case,'' which is the expected normal waste packaging process without aging. A Value Engineering approach is used to score each option against nine technical criteria and rank the options. Open issues with each of the options and suggested future actions are also presented. Costs for aging containers and aging locations are evaluated separately. Capital costs are developed for direct costs and distributable field costs. To the extent practical, unit costs are presented. Indirect costs, operating costs, and total system life cycle costs will be evaluated outside of this study. Three recommendations for aging commercial spent nuclear fuel--subsurface, surface, and combined surface and subsurface are presented for further review in the overall design re-evaluation effort. Options that were evaluated but not recommended are: subsurface aging in a new

  10. AGING GAUGE

    DOE Patents [OSTI]

    Betts, Robert E.; Crawford, John F.

    1989-04-04

    An aging gauge comprising a container having a fixed or a variable sized t opening with a cap which can be opened to control the sublimation rate of a thermally sublimational material contained within the container. In use, the aging gauge is stored with an item to determine total heat the item is subjected to and also the maximum temperature to which the item has been exposed. The aging gauge container contains a thermally sublimational material such as naphthalene or similar material which has a low sublimation rate over the temperature range from about 70.degree. F. to about 160.degree. F. The aging products determined by analyses of a like item aged along with the aging gauge for which the sublimation amount is determined is employed to establish a calibration curve for future aging evaluation. The aging gauge is provided with a means for determining the maximum temperature exposure (i.e., a thermally indicating material which gives an irreversible color change, Thermocolor pigment). Because of the relationship of doubling reaction rates for increases of 10.degree. C., equivalency of item used in accelerated aging evaluation can be obtained by referring to a calibration curve depicting storage temperature on the abscissa scale and multiplier on the ordinate scale.

  11. Aging gauge

    DOE Patents [OSTI]

    Betts, Robert E.; Crawford, John F.

    1989-01-01

    An aging gauge comprising a container having a fixed or a variable sized t opening with a cap which can be opened to control the sublimation rate of a thermally sublimational material contained within the container. In use, the aging gauge is stored with an item to determine total heat the item is subjected to and also the maximum temperature to which the item has been exposed. The aging gauge container contains a thermally sublimational material such as naphthalene or similar material which has a low sublimation rate over the temperature range from about 70.degree. F. to about 160.degree. F. The aging products determined by analyses of a like item aged along with the aging gauge for which the sublimation amount is determined is employed to establish a calibration curve for future aging evaluation. The aging gauge is provided with a means for determining the maximum temperature exposure (i.e., a thermally indicating material which gives an irreversible color change, Thermocolor pigment). Because of the relationship of doubling reaction rates for increases of 10.degree. C., equivalency of item used in accelerated aging evaluation can be obtained by referring to a calibration curve depicting storage temperature on the abscissa scale and multiplier on the ordinate scale.

  12. Aging gauge

    DOE Patents [OSTI]

    Betts, Robert E.; Crawford, John F.

    1989-04-04

    An aging gauge comprising a container having a fixed or a variable sized t opening with a cap which can be opened to control the sublimation rate of a thermally sublimational material contained within the container. In use, the aging gauge is stored with an item to determine total heat the item is subjected to and also the maximum temperature to which the item has been exposed. The aging gauge container contains a thermally sublimational material such as naphthalene or similar material which has a low sublimation rate over the temperature range from about 70.degree. F. to about 160.degree. F. The aging products determined by analyses of a like item aged along with the aging gauge for which the sublimation amount is determined is employed to establish a calibration curve for future aging evaluation. The aging gauge is provided with a means for determining the maximum temperature exposure (i.e., a thermally indicating material which gives an irreversible color change, Thermocolor pigment). Because of the relationship of doubling reaction rates for increases of 10.degree. C., equivalency of item used in accelerated aging evaluation can be obtained by referring to a calibration curve depicting storage temperature on the abscissa scale and multiplier on the ordinate scale.

  13. Nuclear Astrophysics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear & Uranium Glossary › FAQS › Overview Data Status of U.S. nuclear outages (interactive) Nuclear power plants Uranium & nuclear fuel Spent nuclear fuel All nuclear data reports Analysis & Projections Major Topics Most popular Nuclear plants and reactors Projections Recurring Uranium All reports Browse by Tag Alphabetical Frequency Tag Cloud Current Issues & Trends See more › U.S. nuclear outages this summer were higher than in summer 2015

  14. Nuclear Forensics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    nuclear forensics Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear explosion, is the application of laboratory analysis and interpretation to provide technical conclusions (provenance, design, etc.) about a nuclear device or interdicted nuclear material. Nuclear forensic analysts can build confidence in their conclusions by employing multiple signatures that collectively minimize the

  15. Nuclear Facilities

    Broader source: Energy.gov [DOE]

    The nuclear sites list and map shows how DOE nuclear operations are mostly divided between nuclear weapons stockpile maintenance, research and environmental cleanup. The operations are performed within several different facilities supporting nuclear reactor operations, nuclear research, weapons disassembly, maintenance and testing, hot cell operations, nuclear material storage and processing and waste disposal.

  16. Little known heroes of the nuclear age

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    entire bodies. Two soldiers just outside the room, Pvt. John E. Tompkins and Pvt. John Hoffman, both Special Engineer Detachment soldiers, were also critically injured. Hoffman...

  17. nuclear security

    National Nuclear Security Administration (NNSA)

    3%2A en Shaping the future of nuclear detection http:nnsa.energy.govblogshaping-future-nuclear-detection

    Learning techniques to combat nuclear trafficking, touring the...

  18. AGING FACILITY CRITICALITY SAFETY CALCULATIONS

    SciTech Connect (OSTI)

    C.E. Sanders

    2004-09-10

    The purpose of this design calculation is to revise and update the previous criticality calculation for the Aging Facility (documented in BSC 2004a). This design calculation will also demonstrate and ensure that the storage and aging operations to be performed in the Aging Facility meet the criticality safety design criteria in the ''Project Design Criteria Document'' (Doraswamy 2004, Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''SNF Aging System Description Document'' (BSC [Bechtel SAIC Company] 2004f, p. 3-12). The scope of this design calculation covers the systems and processes for aging commercial spent nuclear fuel (SNF) and staging Department of Energy (DOE) SNF/High-Level Waste (HLW) prior to its placement in the final waste package (WP) (BSC 2004f, p. 1-1). Aging commercial SNF is a thermal management strategy, while staging DOE SNF/HLW will make loading of WPs more efficient (note that aging DOE SNF/HLW is not needed since these wastes are not expected to exceed the thermal limits form emplacement) (BSC 2004f, p. 1-2). The description of the changes in this revised document is as follows: (1) Include DOE SNF/HLW in addition to commercial SNF per the current ''SNF Aging System Description Document'' (BSC 2004f). (2) Update the evaluation of Category 1 and 2 event sequences for the Aging Facility as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004c, Section 7). (3) Further evaluate the design and criticality controls required for a storage/aging cask, referred to as MGR Site-specific Cask (MSC), to accommodate commercial fuel outside the content specification in the Certificate of Compliance for the existing NRC-certified storage casks. In addition, evaluate the design required for the MSC that will accommodate DOE SNF/HLW. This design calculation will achieve the objective of providing the criticality safety results to support the preliminary design of the Aging

  19. Nuclear Science

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    and Engineering Education Sourcebook 2013 American Nuclear Society US Department of Energy Nuclear Science & Engineering Education Sourcebook 2013 North American Edition American Nuclear Society Education, Training, and Workforce Division US Department of Energy Office of Nuclear Energy Editor and Founder John Gilligan Professor of Nuclear Engineering North Carolina State University Version 5.13 Welcome to the 2013 Edition of the Nuclear Science and Engineering Education (NS&EE)

  20. Structural aging program status report

    SciTech Connect (OSTI)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.; Graves, H.L. III

    1994-12-31

    Research is being conducted at the Oak Ridge National Laboratory under Nuclear Regulatory Commission (USNRC) sponsorship to address aging management of safety-related concrete structures. Documentation is being prepared to provide the USNRC with potential structural safety issues and acceptance criteria for use in continued service evaluations of nuclear power plants. Program accomplishments have included development of the Structural Materials Information Center containing data and information on the time variation of 144 material properties under the influence of pertinent environmental stressors or aging factors, performance assessments of reinforced concrete structures in several United Kingdom nuclear power facilities, evaluation of European and North American repair practices for concrete, an evaluation of factors affecting the corrosion of metals embedded in concrete, and application of the time-dependent reliability methodology to reinforced concrete flexure and shear structural elements to investigate the role of in-service inspection and repair on their probability of failure.

  1. Structural aging program status report

    SciTech Connect (OSTI)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.

    1995-04-01

    Research is being conducted at the Oak Ridge National Laboratory (ORNL) under U.S. Nuclear Regulatory Commission (USNRC) sponsorship to address aging management of safety-related concrete structures. Documentation is being prepared to provide the USNRC with potential structural safety issues and acceptance criteria for use in continued service evaluations of nuclear power plants. Program accomplishments have included development of the Structural Materials Information Center containing data and information of the time variation of 144 material properties under the influence of pertinent environmental stressors of aging factors, performance assessments of reinforced concrete structures in several United Kingdom nuclear power facilities, evaluation of European and North American repair practices for concrete, an evaluation of factors affecting the corrosion of metals embedded in concrete, and application of the time-dependent reliability methodology to reinforced concrete flexure and shear structural elements to investigate the role of in-service inspection and repair on their probability of failure.

  2. Insights gained from aging research

    SciTech Connect (OSTI)

    Blahnik, D.E.; Casada, D.A.; Edson, J.L.; Fineman, D.L.; Gunther, W.E.; Haynes, H.D.; Hoopingarner, K.R.; Jacobus, M.J.; Jarrell, D.B.; Kryter, R.C.; Magelby, H.L.; Murphy, G.A.; Subudhi, M.M.

    1992-03-01

    The US NRC Office of Nuclear Regulatory Research has implemented hardware-oriented engineering research programs to identify and resolve technical issues related to the aging of systems, structures, and components (SSCs) in operating nuclear power plants. This report provides a summary of those research results which have been compiled and published in NUREGS and related technical reports. The systems, components and structures that have been studied are organized by alphabetical order. The research results summary on the SSCs is followed by an assessment guide to emphasize inspection techniques which may be useful for detecting aging degradation in nuclear power plants. This report will be updated periodically to reflect new research results on these or other SSCs.

  3. Y-12 hosts NNSA Aging Infrastructure Workshop | Y-12 National...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    from across the NNSA complex and private industry gathered in Oak Ridge to discuss lessons learned and brainstorm solutions for dealing with the aging nuclear...

  4. nuclear enterprise

    National Nuclear Security Administration (NNSA)

    Outlines Accomplishments in Stockpile Stewardship, Nuclear Nonproliferation, Naval Reactors and Managing the Nuclear Enterprise

    The...

  5. Nuclear Physics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Physics Nuclear Physics Enabling remarkable discoveries and tools that transform our understanding of energy and matter and advance national, economic, and energy security. ...

  6. AGING SYSTEM DESIGN DEVELOPMENT STRATEGY

    SciTech Connect (OSTI)

    J. Beesley

    2005-02-07

    This plan provides an overview, work to date, and the path forward for the design development strategy of the Aging cask for aging commercial spent nuclear fuel (CSNF) at the Yucca Mountain Project (YMP) repository site. Waste for subsurface emplacement at the repository includes US Department of Energy (DOE) high-level radioactive waste (HLW), DOE SNF, commercial fuel in dual-purpose canisters (DPCs), uncanistered bare fuel, naval fuel, and other waste types. Table 1-1 lists the types of radioactive materials that may be aged at YMP, and those materials that will not be placed in an aging cask or module. This plan presents the strategy for design development of the Aging system. The Aging system will not handle naval fuel, DOE HLW, MCOs, or DOE SNF since those materials will be delivered to the repository in a state and sequence that allows them to be placed into waste packages for emplacement. Some CSNF from nuclear reactors, especially CSNF that is thermally too hot for emplacement underground, will need to be aged at the repository.

  7. Spent Nuclear Fuel

    U.S. Energy Information Administration (EIA) Indexed Site

    Nuclear & Uranium Glossary FAQS Overview Data Status of U.S. nuclear outages (interactive) Nuclear power plants Uranium & nuclear fuel Spent nuclear fuel All nuclear data ...

  8. Nuclear Science/Nuclear Chemistry

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    nuclear science nuclear chemistry Nuclear Science/Nuclear Chemistry Nuclear Physics The 10-MV tandem accelerator at CAMS provides a platform for conducting nuclear physics experiment both for basic science and lab mission-related programs. For example, we performed a new cross section measurement of the astrophysically important reaction 40Ca(a,g)44Ti in which high purity CaO targets were irradiated with helium ions at several different discrete energies. The reaction rate was measured on-line

  9. Nuclear Energy!

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Energy Technical Assistance Nuclear Energy Technical Assistance "The United States will continue to promote the safe and secure use of nuclear power worldwide through a variety of bilateral and multilateral engagements. For example, the U.S. Nuclear Regulatory Commission advises international partners on safety and regulatory best practices, and the Department of Energy works with international partners on research and development, nuclear waste and storage, training, regulations,

  10. Nuclear Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Stationary Power/Nuclear Energy Nuclear Energy Tara Camacho-Lopez 2016-06-29T14:02:38+00:00 Contributing to the Next Generation of Nuclear Power Generation Our nuclear energy and fuel cycle technologies supports the safe, secure, reliable, and sustainable use of nuclear power worldwide through strengths in repository science, nonproliferation, safety and security, transportation, modeling, and system demonstrations. Areas of Expertise Defense Waste Management Sandia advises the U.S. Department

  11. Nuclear Materials Management & Safeguards System | National Nuclear...

    National Nuclear Security Administration (NNSA)

    About Our Programs Nuclear Security Nuclear Materials Management & Safeguards System NMMSS U.S. Department of Energy U.S. Nuclear Regulatory Commission Nuclear Materials ...

  12. Nuclear Navy

    SciTech Connect (OSTI)

    1994-12-31

    This video tells the story of the Navy`s development of nuclear power and its application in long-range submarines and the growing nuclear surface force. Narrated by Frank Blair.

  13. Age Dating of Mixed SNM--Preliminary Investigations

    SciTech Connect (OSTI)

    Yuan, D., Guss, P. P., Yfantis, E., Klingensmith, A., Emer, D.

    2011-12-01

    Recently we investigated the nuclear forensics problem of age determination for mixed special nuclear material (SNM). Through limited computational mixing experiments and interactive age analysis, it was observed that age dating results are generally affected by the mixing of samples with different assays or even by small radioactive material contamination. The mixing and contamination can be detected through interactive age analysis, a function provided by the Decay Interaction, Visualization and Analysis (DIVA) software developed by NSTec. It is observed that for mixed SNM with two components, the age estimators typically fall into two distinct clusters on the time axis. This suggests that averaging or other simple statistical methods may not always be suitable for age dating SNM mixtures. Instead, an interactive age analysis would be more suitable for age determination of material components of such SNM mixtures. This work was supported by the National Center for Nuclear Security (NCNS).

  14. Nuclear Physics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Physics Nuclear Physics Enabling remarkable discoveries and tools that transform our understanding of energy and matter and advance national, economic, and energy security. Isotopes» A roadmap of matter that will help unlock the secrets of how the universe is put together The DOE Office of Science's Nuclear Physics (NP) program supports the experimental and theoretical research needed to create this roadmap. This quest requires a broad approach to different, but related, scientific

  15. Nuclear Structure

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Security Administration | (NNSA) Nuclear Security Centers of Excellence: Fact Sheet March 23, 2012 "We [the Participating States]... Acknowledge the need for capacity building for nuclear security and cooperation at bilateral, regional and multilateral levels for the promotion of nuclear security culture through technology development, human resource development, education, and training; and stress the importance of optimizing international cooperation and coordination of

  16. Nuclear Counterterrorism

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2013-08-26

    The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information.) Appendices A and B are Official Use Only. Point of contact is Adam Boyd (NA-82), 202-586-0010. Supersedes DOE O 457.1 and DOE M 457.1-1.

  17. nuclear smuggling

    National Nuclear Security Administration (NNSA)

    13, 2015

    SHANGHAI, CHINA - Today, the Nuclear Security Administration's (NNSA) Principal Assistant Deputy Administrator for Defense...

  18. nuclear material

    National Nuclear Security Administration (NNSA)

    width"300" >WASHINGTON, D.C. - The Department of Energy's (DOE) National Nuclear Security Administration (NNSA), in partnership with the Defense Threat Reduction...

  19. nuclear weapons

    National Nuclear Security Administration (NNSA)

    09, 2015

    WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA) and United States Air Force completed eight successful...

  20. nuclear controls

    National Nuclear Security Administration (NNSA)

    which "international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and...

  1. nuclear forensics

    National Nuclear Security Administration (NNSA)

    serves as the premier technical leader in responding to and successfully resolving nuclear and radiological threats worldwide. When the need arises, NNSA is prepared to...

  2. NUCLEAR ENERGY

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    NUCLEAR ENERGY RESEARCH AND DEVELOPMENT ROADMAP Table of Contents List of Acronyms ................................................................................................... iii Executive Summary ............................................................................................... v 1. Introduction ...................................................................................................... 1 2. Background

  3. Accelerated Aging Studies

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Accelerated Aging Studies LA-UR -15-27339 This document is approved for public release; further dissemination unlimited Property (max) log (aging time) Property (failure) Property (time=0) Accelerated Aging Data Predicted Storage Aging Response log (predicted lifetime) Property (max) log (aging time) Property (failure) Property (time=0) Accelerated Aging Data Predicted Storage Aging Response log (predicted lifetime) Accelerated Aging Studies Factors such as temperature, pressure, or radiation

  4. Nuclear Weapons Journal

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Weapons Journal Nuclear Weapons Journal The Nuclear Weapons Journal ceased publication after Issue 2, 2009. Below are Nuclear Weapons Journal archived issues. Issue 2, 2009 ...

  5. 2013 Nuclear Workforce Development ...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Myths Topics: Can a Nuclear Reactor Explode Like a Bomb? Will Nuclear Waste Be Around for Millions of Years? Is Nuclear Energy Dangerous? Moderator: Suzy Hobbs ...

  6. nuclear | National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration (NNSA)

    nuclear Nuclear Science Week releases 2015 Impact Report and 2016 Request for Proposal Last week the Nuclear Science Week (NSW) National Steering Committee released its impact ...

  7. Nuclear Nonproliferation Program Offices | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy ... and monitor nuclear weapons production, proliferation, and nuclear explosions worldwide. ...

  8. Nuclear Nonproliferation, International Safeguards and Nuclear...

    Office of Scientific and Technical Information (OSTI)

    Conference: Nuclear Nonproliferation, International Safeguards and Nuclear Security in the Middle East Citation Details In-Document Search Title: Nuclear Nonproliferation, ...

  9. Nuclear Nonproliferation Treaty | National Nuclear Security Administra...

    National Nuclear Security Administration (NNSA)

    People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy ... Nuclear Nonproliferation Treaty The Treaty on the Non-Proliferation of Nuclear Weapons off ...

  10. Chernobyl Nuclear Accident | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Chernobyl Nuclear Accident Chernobyl Nuclear Accident Chernobyl, Ukraine A catastrophic nuclear accident occurs at Chernobyl Reactor 4 in the then Soviet Republic of Ukraine

  11. Nuclear Nonproliferation, International Safeguards and Nuclear...

    Office of Scientific and Technical Information (OSTI)

    Nuclear Nonproliferation, International Safeguards and Nuclear Security in the Middle East Citation Details In-Document Search Title: Nuclear Nonproliferation, International ...

  12. Nuclear Counterterrorism

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2006-02-07

    The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information. The Manual is Official Use Only, and is not available on the Directives Portal. The point of contact for the Manual is Randall Weidman, NA-121.2, 202-586-4582.) Canceled by DOE O 457.1A

  13. RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; NUCLEAR MEDICINE; HISTORICAL

    Office of Scientific and Technical Information (OSTI)

    The early days Richards, P. 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; NUCLEAR MEDICINE; HISTORICAL ASPECTS; TECHNETIUM 99; COLLOIDS; MOLYBDENUM...

  14. National Nuclear Security Administration | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  15. nuclear navy

    National Nuclear Security Administration (NNSA)

    7%2A en Powering the Nuclear Navy http:www.nnsa.energy.govourmissionpoweringnavy

    Page...

  16. nuclear navy

    National Nuclear Security Administration (NNSA)

    7%2A en Powering the Nuclear Navy http:nnsa.energy.govourmissionpoweringnavy

    Page...

  17. Nuclear option

    SciTech Connect (OSTI)

    Olson, P.S.

    1983-03-01

    The energy demand complexion of this country is always changing and promises to change in the future. The nuclear industry is responding to changing energy demands through standards writing activities. Since the oil embargo of 1973, there has been a change in the mix of fuels contributing to energy growth in this country; virtually all of the energy growth has come from coal and nuclear power. The predicted expansion of coal use by 1985, over 1977 level, is 37%, while the use of oil is expected to decline by 17%. Use of nuclear power is expected to increase 62% from the 1977 level. The feasibility of using nuclear energy to meet the needs of the USA for electric power is discussed.

  18. Primer on nuclear exchange models

    SciTech Connect (OSTI)

    Hafemeister, David

    2014-05-09

    Basic physics is applied to nuclear force exchange models between two nations. Ultimately, this scenario approach can be used to try and answer the age old question of 'how much is enough?' This work is based on Chapter 2 of Physics of Societal Issues: Calculations on National Security, Environment and Energy (Springer, 2007 and 2014)

  19. Nuclear Data

    SciTech Connect (OSTI)

    White, Morgan C.

    2014-01-23

    PowerPoint presentation targeted for educational use. Nuclear data comes from a variety of sources and in many flavors. Understanding where the data you use comes from and what flavor it is can be essential to understand and interpret your results. This talk will discuss the nuclear data pipeline with particular emphasis on providing links to additional resources that can be used to explore the issues you will encounter.

  20. Nuclear Nonproliferation

    SciTech Connect (OSTI)

    Atkins-Duffin, C E

    2008-12-10

    With an explosion equivalent of about 20kT of TNT, the Trinity test was the first demonstration of a nuclear weapon. Conducted on July 16, 1945 in Alamogordo, NM this site is now a Registered National Historic Landmark. The concept and applicability of nuclear power was demonstrated on December 20, 1951 with the Experimental Breeder Reactor Number One (EBR-1) lit four light bulbs. This reactor is now a Registered National Historic Landmark, located near Arco, ID. From that moment forward it had been clearly demonstrated that nuclear energy has both peaceful and military applications and that the civilian and military fuel cycles can overlap. For the more than fifty years since the Atoms for Peace program, a key objective of nuclear policy has been to enable the wider peaceful use of nuclear energy while preventing the spread of nuclear weapons. Volumes have been written on the impact of these two actions on the world by advocates and critics; pundits and practioners; politicians and technologists. The nations of the world have woven together a delicate balance of treaties, agreements, frameworks and handshakes that are representative of the timeframe in which they were constructed and how they have evolved in time. Collectively these vehicles attempt to keep political will, nuclear materials and technology in check. This paper captures only the briefest abstract of the more significant aspects on the Nonproliferation Regime. Of particular relevance to this discussion is the special nonproliferation sensitivity associated with the uranium isotope separation and spent fuel reprocessing aspects of the nuclear fuel cycle.

  1. Evaluation of NRC maintenance team inspection reports for managing aging

    SciTech Connect (OSTI)

    Fresco, A.; Gunther, W.

    1991-01-01

    A nuclear power plant's maintenance program is the principal vehicle through which age-related degradation is managed. Over the past two years, the NRC (Nuclear Regulatory Commission) has evaluated the maintenance program of every nuclear power plant in the U.S. The reports issued on these in-depth team inspections have been reviewed to ascertain the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear power plant systems, structures, and components. Selected results of this review are presented in this paper, including examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue are also discussed. 6 refs., 1 tab.

  2. Accelerated Aging Studies

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Accelerated Aging Studies LA-UR -15-27339 This document is approved for public release; further dissemination unlimited Property (max) log (aging time) Property (failure) Property ...

  3. Nuclear Models

    SciTech Connect (OSTI)

    Fossion, Ruben [Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Apartado Postal 70-543, Mexico D. F., C.P. 04510 (Mexico)

    2010-09-10

    The atomic nucleus is a typical example of a many-body problem. On the one hand, the number of nucleons (protons and neutrons) that constitute the nucleus is too large to allow for exact calculations. On the other hand, the number of constituent particles is too small for the individual nuclear excitation states to be explained by statistical methods. Another problem, particular for the atomic nucleus, is that the nucleon-nucleon (n-n) interaction is not one of the fundamental forces of Nature, and is hard to put in a single closed equation. The nucleon-nucleon interaction also behaves differently between two free nucleons (bare interaction) and between two nucleons in the nuclear medium (dressed interaction).Because of the above reasons, specific nuclear many-body models have been devised of which each one sheds light on some selected aspects of nuclear structure. Only combining the viewpoints of different models, a global insight of the atomic nucleus can be gained. In this chapter, we revise the the Nuclear Shell Model as an example of the microscopic approach, and the Collective Model as an example of the geometric approach. Finally, we study the statistical properties of nuclear spectra, basing on symmetry principles, to find out whether there is quantum chaos in the atomic nucleus. All three major approaches have been rewarded with the Nobel Prize of Physics. In the text, we will stress how each approach introduces its own series of approximations to reduce the prohibitingly large number of degrees of freedom of the full many-body problem to a smaller manageable number of effective degrees of freedom.

  4. Nuclear pursuits

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    This table lists quantities of warheads (in stockpile, peak number per year, total number built, number of known test explosions), weapon development milestones (developers of the atomic bomb and hydrogen bomb, date of first operational ICBM, first nuclear-powered naval SSN in service, first MIRVed missile deployed), and testing milestones (first fission test, type of boosted fission weapon, multistage thermonuclear test, number of months from fission bomb to multistage thermonuclear bomb, etc.), and nuclear infrastructure (assembly plants, plutonium production reactors, uranium enrichment plants, etc.). Countries included in the tally are the United States, Soviet Union, Britain, France, and China.

  5. Defense Nuclear Facility | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Defense Nuclear Facility NNSA's safety office accredited and recognized for leadership in safe operation of defense nuclear facilities Part of NNSA's commitment to maintaining the nation's safe, secure, and effective nuclear deterrent are relentlessly high standards for technically capable nuclear enterprise personnel qualifications for all aspects of Defense Nuclear Facility operations. In December 2015, the Department of Energy

  6. Nuclear Controls | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Control Nuclear Controls Challenge: Detect/deter illicit transfers of nuclear/dual-use materials, technology, and commodities. Solution: Build domestic and international capacity to implement and meet export control obligations. Related Topics international security international security policy NIS nuclear controls safeguards safeguards and security verification Related News Nuclear Verification International Nuclear Safeguards Nonproliferation Policy Nonproliferation and Arms Control NIS

  7. Nuclear Verification | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Control Nuclear Verification Challenge: Maintain the U.S. ability to monitor and verify nuclear reduction agreements and detect violations of treaties and other nuclear nonproliferation commitments. Solution: Develop and deploy measures to ensure verifiable compliance with treaties and other international agreements, implement regimes to reduce nuclear weapons, and detect and dismantle undeclared nuclear programs. Specific subprogram activities include: Implementing current and developing future

  8. nuclear controls | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    controls Nuclear Verification Challenge: Maintain the U.S. ability to monitor and verify nuclear reduction agreements and detect violations of treaties and other nuclear nonproliferation commitments. Solution: Develop and deploy measures to ensure verifiable compliance with treaties and other international agreements,... International Nuclear Safeguards Challenge: Detect/deter undeclared nuclear materials and activities. Solution: Build capacity of the International Atomic Energy Agency and

  9. SNF AGING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    L.L. Swanson

    2005-04-06

    The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF) aging system and associated bases, which will allow the design effort to proceed. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in the SDD reflects the current results of the design process. Throughout this SDD, the term aging cask applies to vertical site-specific casks and to horizontal aging modules. The term overpack is a vertical site-specific cask that contains a dual-purpose canister (DPC) or a disposable canister. Functional and operational requirements applicable to this system were obtained from ''Project Functional and Operational Requirements'' (F&OR) (Curry 2004 [DIRS 170557]). Other requirements that support the design process were taken from documents such as ''Project Design Criteria Document'' (PDC) (BSC 2004 [DES 171599]), ''Site Fire Hazards Analyses'' (BSC 2005 [DIRS 172174]), and ''Nuclear Safety Design Bases for License Application'' (BSC 2005 [DIRS 171512]). The documents address requirements in the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]). This SDD includes several appendices. Appendix A is a Glossary; Appendix B is a list of key system charts, diagrams, drawings, lists and additional supporting information; and Appendix C is a list of

  10. Nuclear Science & Technology

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Science & Technology Nuclear Science & Technology1354608000000Nuclear Science & TechnologySome of these resources are LANL-only and will require Remote Access. No...

  11. 2013 Nuclear Workforce Development ...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Energy Impact Topics: Today's & Tomorrow's New Nuclear Energy Construction & the Workforce Outlook Current New Nuclear Energy Construction Projects Small Modular...

  12. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Starr, C.

    1963-01-01

    This patent relates to a combination useful in a nuclear reactor and is comprised of a casing, a mass of graphite irapregnated with U compounds in the casing, and at least one coolant tube extending through the casing. The coolant tube is spaced from the mass, and He is irtroduced irto the space between the mass and the coolant tube. (AEC)

  13. Defense Nuclear Nonproliferation | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Defense Nuclear Nonproliferation NNSA Announces Elimination of Highly Enriched Uranium (HEU) from Indonesia All of Southeast Asia Now HEU-Free (WASHINGTON, D.C.) - The U.S. Department of Energy's National Nuclear Security Administration (DOE/NNSA), Indonesian Nuclear Industry, LLC (PT INUKI), the National Nuclear Energy Agency (BATAN), and the Nuclear Energy Regulatory Agency (BAPETEN) of the... NNSA program strengthens national security from afar The Nuclear Smuggling Detection and Deterrence

  14. Nuclear Security Enterprise | National Nuclear Security Administration...

    National Nuclear Security Administration (NNSA)

    Nuclear Security Enterprise The Nuclear Security Enterprise ... efficient 21stcentury NSE with less environmental impact. ... is referred to as Stockpile Stewardship and Management. ...

  15. Nuclear / Radiological Advisory Team | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Nuclear Radiological Advisory Team (NRAT) provides an emergency response capability for on-scene scientific and technical advice for both domestic and international nuclear or ...

  16. Nuclear Incident Team | National Nuclear Security Administration...

    National Nuclear Security Administration (NNSA)

    Incident Team NNSA houses the Nuclear Incident Team (NIT), which is responsible for deploying assets at the request of coordinating agencies in response to a nuclear or ...

  17. Nuclear Energy Systems Laboratory (NESL) / Transient Nuclear...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Transient Nuclear Fuels Testing - Sandia Energy Energy Search Icon Sandia Home Locations ... Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & ...

  18. nuclear science week | National Nuclear Security Administration...

    National Nuclear Security Administration (NNSA)

    science week Nuclear Science Week releases 2015 Impact Report and 2016 Request for Proposal Last week the Nuclear Science Week (NSW) National Steering Committee released its impact ...

  19. Nuclear and Radiological Material Security | National Nuclear...

    National Nuclear Security Administration (NNSA)

    This includes NNSA's work to advance physical protection standards for nuclear facilities and to strengthen nuclear safeguards, which are criteria for the physical security and the ...

  20. Nuclear Forensics | National Nuclear Security Administration...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Forensics Forensics Operations The National Technical Nuclear Forensics (NTNF) program is a Homeland Security Council and National Security Council-sponsored policy ...

  1. Nuclear Security Enterprise | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    About Our Programs Defense Programs Nuclear Security Enterprise The Nuclear Security Enterprise (NSE) mission is to ensure the Nation sustains a safe, secure, and effective ...

  2. Nuclear Verification | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Challenge: Maintain the U.S. ability to monitor and verify nuclear reduction agreements and detect violations of treaties and other nuclear nonproliferation commitments. Solution: ...

  3. Nuclear Suppliers Group & Regimes | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency ...

  4. Nuclear Controls | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Controls | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy ...

  5. Nuclear structure and nuclear reactions | Argonne Leadership...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear structure and nuclear reactions PI Name: James Vary PI Email: jvary@iastate.edu Institution: Iowa State University Allocation Program: INCITE Allocation Hours at ALCF: 15 ...

  6. nuclear emergency | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home nuclear emergency nuclear emergency Fukushima: Five Years Later After the March 11, 2011, Japan earthquake, tsunami, and ...

  7. Nuclear | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nuclear Nuclear Radioisotope Power Systems, a strong partnership between the Energy Department's Office of Nuclear Energy and NASA, has been providing the energy for deep space exploration. Nuclear power is the use of sustained nuclear fission to generate heat and electricity. Nuclear power plants provide about 6 percent of the world's energy and 13-14 percent of the world's electricity. Featured Moving Forward to Address Nuclear Waste Storage and Disposal Three trucks transport nuclear waste

  8. NUCLEAR REACTORS

    DOE Patents [OSTI]

    Long, E.; Ashby, J.W.

    1958-09-16

    ABS>A graphite moderator structure is presented for a nuclear reactor compriscd of an assembly of similarly orientated prismatic graphite blocks arranged on spaced longitudinal axes lying in common planes wherein the planes of the walls of the blocks are positioned so as to be twisted reintive to the planes of said axes so thatthe unlmpeded dtrect paths in direction wholly across the walls of the blocks are limited to the width of the blocks plus spacing between the blocks.

  9. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  10. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Grebe, J.J.

    1959-07-14

    High temperature reactors which are uniquely adapted to serve as the heat source for nuclear pcwered rockets are described. The reactor is comprised essentially of an outer tubular heat resistant casing which provides the main coolant passageway to and away from the reactor core within the casing and in which the working fluid is preferably hydrogen or helium gas which is permitted to vaporize from a liquid storage tank. The reactor core has a generally spherical shape formed entirely of an active material comprised of fissile material and a moderator material which serves as a diluent. The active material is fabricated as a gas permeable porous material and is interlaced in a random manner with very small inter-connecting bores or capillary tubes through which the coolant gas may flow. The entire reactor is divided into successive sections along the direction of the temperature gradient or coolant flow, each section utilizing materials of construction which are most advantageous from a nuclear standpoint and which at the same time can withstand the operating temperature of that particular zone. This design results in a nuclear reactor characterized simultaneously by a minimum critiral size and mass and by the ability to heat a working fluid to an extremely high temperature.

  11. Recommendations for the treatment of aging in standard technical specifications

    SciTech Connect (OSTI)

    Orton, R.D.; Allen, R.P.

    1995-09-01

    As part of the US Nuclear Regulatory Commission`s Nuclear Plant Aging Research Program, Pacific Northwest Laboratory (PNL) evaluated the standard technical specifications for nuclear power plants to determine whether the current surveillance requirements (SRs) were effective in detecting age-related degradation. Nuclear Plant Aging Research findings for selected systems and components were reviewed to identify the stressors and operative aging mechanisms and to evaluate the methods available to detect, differentiate, and trend the resulting aging degradation. Current surveillance and testing requirements for these systems and components were reviewed for their effectiveness in detecting degraded conditions and for potential contributions to premature degradation. When the current surveillance and testing requirements appeared ineffective in detecting aging degradation or potentially could contribute to premature degradation, a possible deficiency in the SRs was identified that could result in undetected degradation. Based on this evaluation, PNL developed recommendations for inspection, surveillance, trending, and condition monitoring methods to be incorporated in the SRs to better detect age- related degradation of these selected systems and components.

  12. workforce | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    workforce NNSA administrator shows NM congressional delegation the Albuquerque Complex to make case for new facility WASHINGTON, DC - Lt. Gen. Frank Klotz (Ret.), Administrator of the Department of Energy's National Nuclear Security Administration, hosted two members of the New Mexico congressional delegation on Feb. 18 for a tour of the aging facilities occupied by 1,200 NNSA employees at the Albuquerque Complex... DOE Celebrates LGBT Pride Month To recognize the accomplishments of Lesbian,

  13. Nuclear Detonation Detection | National Nuclear Security Administration |

    National Nuclear Security Administration (NNSA)

    (NNSA) Research and Development Nuclear Detonation Detection The Office of Nuclear Detonation Detection (NDD) develops and provide continuous, global capabilities to detect foreign nuclear weapon detonations, including for test ban treaty monitoring needs and military requirements. These efforts are aligned along three functional areas: Space-based Detection of Nuclear Detonations: Develops and builds space sensors for the nation's operational nuclear test treaty monitoring and Integrated

  14. nuclear threat science | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    threat science Counterterrorism Counterterrorism Policy and Cooperation Nuclear Threat Science Office of Nuclear Threat Science The Office of Nuclear Threat Science is responsible for overseeing the Nuclear Counterterrorism Program, an NNSA program that sustains specialized expertise and integrates and executes key activities to advise and enable technical aspects of U.S. Government nuclear counterterrorism and... Office of Counterterrorism Policy and Cooperation The 2011 National Strategy for

  15. nuclear science | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    science Nuclear Science Week releases 2015 Impact Report and 2016 Request for Proposal Last week the Nuclear Science Week (NSW) National Steering Committee released its impact report from the 2015 event, detailing the many ways people were educated about all things nuclear as a result of the event. Nuclear Science Week is an international weeklong celebration to focus interest on... Consortium Led by University of California, Berkeley Awarded $25M NNSA Grant for Nuclear Science and Security

  16. NUCLEAR REACTORS

    DOE Patents [OSTI]

    Long, E.; Ashley, J.W.

    1958-12-16

    A graphite moderator structure is described for a gas-cooled nuclear reactor having a vertical orlentation wherein the structure is physically stable with regard to dlmensional changes due to Wigner growth properties of the graphite, and leakage of coolant gas along spaces in the structure is reduced. The structure is comprised of stacks of unlform right prismatic graphite blocks positioned in layers extending in the direction of the lengths of the blocks, the adjacent end faces of the blocks being separated by pairs of tiles. The blocks and tiles have central bores which are in alignment when assembled and are provided with cooperatlng keys and keyways for physical stability.

  17. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Young, G.

    1963-01-01

    This patent covers a power-producing nuclear reactor in which fuel rods of slightly enriched U are moderated by heavy water and cooled by liquid metal. The fuel rods arranged parallel to one another in a circle are contained in a large outer closed-end conduit that extends into a tank containing the heavy water. Liquid metal is introduced into the large conduit by a small inner conduit that extends within the circle of fuel rods to a point near the lower closed end of the outer conduit. (AEC) Production Reactors

  18. Nuclear Data Links

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Links to Other Useful Sites Online Journals Institutions and Programs Related to Nuclear Physics U.S. Nuclear Data Program: All evaluated nuclear data supported by the U.S. Department of Energy. National Nuclear Data Center: Brookhaven National Laboratory; Evaluated Nuclear Structure Data Files (ENSDF), Nuclear Science References (NSR) and other databases. Isotopes Project: (E.O.L. Berkeley National Laboratory) Table of Isotopes, Isotope Explorer, XUNDL, Nuclear Data Dissemination Homepage, and

  19. Aging study of boiling water reactor high pressure injection systems

    SciTech Connect (OSTI)

    Conley, D.A.; Edson, J.L.; Fineman, C.F.

    1995-03-01

    The purpose of high pressure injection systems is to maintain an adequate coolant level in reactor pressure vessels, so that the fuel cladding temperature does not exceed 1,200{degrees}C (2,200{degrees}F), and to permit plant shutdown during a variety of design basis loss-of-coolant accidents. This report presents the results of a study on aging performed for high pressure injection systems of boiling water reactor plants in the United States. The purpose of the study was to identify and evaluate the effects of aging and the effectiveness of testing and maintenance in detecting and mitigating aging degradation. Guidelines from the United States Nuclear Regulatory Commission`s Nuclear Plant Aging Research Program were used in performing the aging study. Review and analysis of the failures reported in databases such as Nuclear Power Experience, Licensee Event Reports, and the Nuclear Plant Reliability Data System, along with plant-specific maintenance records databases, are included in this report to provide the information required to identify aging stressors, failure modes, and failure causes. Several probabilistic risk assessments were reviewed to identify risk-significant components in high pressure injection systems. Testing, maintenance, specific safety issues, and codes and standards are also discussed.

  20. Evidence of aging effects on certain safety-related components

    SciTech Connect (OSTI)

    Magleby, H.L.; Atwood, C.L.; MacDonald, P.E.; Edson, J.L.; Bramwell, D.L.

    1996-01-01

    In response to interest shown by the Nuclear Energy Agency (NEA), Principal Working Group I (PWG- 1) of the Committee on the Safety of Nuclear Installations (CSNI) conducted a generic study on the effects of aging of active components in nuclear power plants. (This focus on active components is consistent with PWG-l`s mandate; passive components are primarily within the mandate of PWG-3.) Representatives from France, Sweden, Finland, Japan, the United States, and the United Kingdom participated in the study by submitting reports documenting aging studies performed in their countries. This report consists of summaries of those reports, along with a comparison of the various statistical analysis methods used in the studies. The studies indicate that with some exceptions, active components generally do not present a significant aging problem in nuclear power plants. Design criteria and effective preventative maintenance programs, including timely replacement of components, are effective in mitigating potential aging problems. However, aging studies (such as qualitative and statistical analyses of failure modes and maintenance data) are an important part of efforts to identify and solve potential aging problems. Solving these problems typically includes such strategies as replacing suspect components with improved components, and implementing improved maintenance programs.

  1. Fifty years of nuclear fission: Nuclear data and measurements...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Fifty years of nuclear fission: Nuclear data and measurements series Citation Details In-Document Search Title: Fifty years of nuclear fission: Nuclear data and ...

  2. Fifty years of nuclear fission: Nuclear data and measurements...

    Office of Scientific and Technical Information (OSTI)

    Fifty years of nuclear fission: Nuclear data and measurements series Citation Details In-Document Search Title: Fifty years of nuclear fission: Nuclear data and measurements series ...

  3. Little known heroes of the nuclear age, part 2

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    He would become one of the first people injured in the Manhattan Project. The S-50 Thermal Diffusion Plant was being constructed at the K-25 Gaseous Diffusion Plant site....

  4. US nuclear engineering education: Status and prospects

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

    This study, conducted under the auspices of the Energy Engineering Board of the National Research Council, examines the status of and outlook for nuclear engineering education in the United States. The study resulted from a widely felt concern about the downward trends in student enrollments in nuclear engineering, in both graduate and undergraduate programs. Concerns have also been expressed about the declining number of US university nuclear engineering departments and programs, the aging of their faculties, the appropriateness of their curricula and research funding for industry and government needs, the availability of scholarships and research funding, and the increasing ratio of foreign to US graduate students. A fundamental issue is whether the supply of nuclear engineering graduates will be adequate for the future. Although such issues are more general, pertaining to all areas of US science and engineering education, they are especially acute for nuclear engineering education. 30 refs., 12 figs., 20 tabs.

  5. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Grebe, J.J.

    1959-12-15

    A reactor which is particularly adapted tu serve as a heat source for a nuclear powered alrcraft or rocket is described. The core of this reactor consists of a porous refractory modera;or body which is impregnated with fissionable nuclei. The core is designed so that its surface forms tapered inlet and outlet ducts which are separated by the porous moderator body. In operation a gaseous working fluid is circulated through the inlet ducts to the surface of the moderator, enters and passes through the porous body, and is heated therein. The hot gas emerges into the outlet ducts and is available to provide thrust. The principle advantage is that tremendous quantities of gas can be quickly heated without suffering an excessive pressure drop.

  6. Nuclear reactor

    DOE Patents [OSTI]

    Wade, Elman E.

    1979-01-01

    A nuclear reactor including two rotatable plugs and a positive top core holddown structure. The top core holddown structure is divided into two parts: a small core cover, and a large core cover. The small core cover, and the upper internals associated therewith, are attached to the small rotating plug, and the large core cover, with its associated upper internals, is attached to the large rotating plug. By so splitting the core holddown structures, under-the-plug refueling is accomplished without the necessity of enlarging the reactor pressure vessel to provide a storage space for the core holddown structure during refueling. Additionally, the small and large rotating plugs, and their associated core covers, are arranged such that the separation of the two core covers to permit rotation is accomplished without the installation of complex lifting mechanisms.

  7. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  8. TUNL Nuclear Data Evaluation Group

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    TUNL Nuclear Data Evaluation Group As a part of the United States Nuclear Data Network and the international Nuclear Structure and Decay Data Evaluators' Network, the Nuclear Data...

  9. Parylene C Aging Studies.

    SciTech Connect (OSTI)

    Achyuthan, Komandoor; Sawyer, Patricia Sue.; Mata, Guillermo Adrian; White II, Gregory Von; Bernstein, Robert

    2014-09-01

    Parylene C is used in a device because of its conformable deposition and other advantages. Techniques to study Parylene C aging were developed, and %22lessons learned%22 that could be utilized for future studies are the result of this initial study. Differential Scanning Calorimetry yielded temperature ranges for Parylene C aging as well as post-deposition treatment. Post-deposition techniques are suggested to improve Parylene C performance. Sample preparation was critical to aging regimen. Short-term (~40 days) aging experiments with free standing and ceramic-supported Parylene C films highlighted %22lessons learned%22 which stressed further investigations in order to refine sample preparation (film thickness, single sided uniform coating, machine versus laser cutting, annealing time, temperature) and testing issues (%22necking%22) for robust accelerated aging of Parylene C.

  10. Studying Nuclear Astrophysics at NIF

    SciTech Connect (OSTI)

    Boyd, R; Bernstein, L; Brune, C

    2009-07-01

    The National Ignition Facility's primary goal is to generate fusion energy. But the starlike conditions that it creates will also enable NIF scientists to study astrophysically important nuclear reactions. When scientists at the stadium-sized National Ignition Facility attempt to initiate fusion next year, 192 powerful lasers will direct 1.2 MJ of light energy toward a two-mm-diameter pellet of deuterium ({sup 2}H, or D) and tritium ({sup 3}H, or T). Some of that material will be gaseous, but most will be in a frozen shell. The idea is to initiate 'inertial confinement fusion', in which the two hydrogen isotopes fuse to produce helium-4, a neutron, and 17.6 MeV of energy. The light energy will be delivered to the inside walls of a hohlraum, a heavy-metal, centimeter-sized cylinder that houses the pellet. The container's heated walls will produce x rays that impinge on the pellet and ablate its outer surface. The exiting particles push inward on the pellet and compresses the DT fuel. Ultimately a hot spot develops at the pellet's center, where fusion produces {sup 4}He nuclei that have sufficient energy to propagate outward, trigger successive reactions, and finally react the frozen shell. Ignition should last several tens of picoseconds and generate more than 10 MJ of energy and roughly 10{sup 19} neutrons. The temperature will exceed 10{sup 8} K and fuel will be compressed to a density of several hundred g/cm{sup 3}, both considerably greater than at the center of the Sun. The figure shows a cutaway view of NIF. The extreme conditions that will be produced there simulate those in nuclear weapons and inside stars. For that reason, the facility is an important part of the US stockpile stewardship program, designed to assess the nation's aging nuclear stockpile without doing nuclear tests. In this Quick Study we consider a third application of NIF - using the extraordinary conditions it will produce to perform experiments in basic science. We will focus on

  11. Aging assessment of reactor instrumentation and protection system components. Aging-related operating experiences

    SciTech Connect (OSTI)

    Gehl, A.C.; Hagen, E.W.

    1992-07-01

    A study of the aging-related operating experiences throughout a five-year period (1984--1988) of six generic instrumentation modules (indicators, sensors, controllers, transmitters, annunciators, and recorders) was performed as a part of the Nuclear Plant Aging Research Program. The effects of aging from operational and environmental stressors were characterized from results depicted in Licensee Event Reports (LERs). The data are graphically displayed as frequency of events per plant year for operating plant ages from 1 to 28 years to determine aging-related failure trend patterns. Three main conclusions were drawn from this study: (1) Instrumentation and control (I&C) modules make a modest contribution to safety-significant events: 17% of LERs issued during 1984--1988 dealt with malfunctions of the six I&C modules studied, and 28% of the LERs dealing with these I&C module malfunctions were aging related (other studies show a range 25--50%); (2) Of the six modules studied, indicators, sensors, and controllers account for the bulk (83%) of aging-related failures; and (3) Infant mortality appears to be the dominant aging-related failure mode for most I&C module categories (with the exception of annunciators and recorders, which appear to fail randomly).

  12. Nuclear Explosive Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2014-07-10

    The Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs).

  13. Nuclear Materials Disposition

    Broader source: Energy.gov [DOE]

    In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel.  These are not waste. They are nuclear materials no longer needed for...

  14. Office of Nuclear Safety

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Office of Nuclear Safety establishes nuclear safety requirements and expectations for the Department to ensure protection of workers and the public from the hazards associated with nuclear operations with all Department operations.

  15. Nuclear Quadrupole Moments and Nuclear Shell Structure

    DOE R&D Accomplishments [OSTI]

    Townes, C. H.; Foley, H. M.; Low, W.

    1950-06-23

    Describes a simple model, based on nuclear shell considerations, which leads to the proper behavior of known nuclear quadrupole moments, although predictions of the magnitudes of some quadrupole moments are seriously in error.

  16. Nuclear Incident Team | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home Nuclear Incident Team Nuclear Incident Team Fukushima: Five Years Later After the March 11, 2011, Japan earthquake, tsunami, ...

  17. Idaho Site Taps Old World Process to Treat Nuclear Waste

    Office of Energy Efficiency and Renewable Energy (EERE)

    IDAHO FALLS, Idaho – The EM program at the Idaho site is using an age-old process to treat transuranic (TRU) waste left over from nuclear reactor experiments.

  18. Nuclear Energy Programs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Services » Nuclear Energy Advisory Committee Nuclear Energy Advisory Committee The Nuclear Energy Advisory Committee (NEAC), formerly the Nuclear Energy Research Advisory Committee (NERAC), was established on October 1, 1998, to provide independent advice to the Office of Nuclear Energy (NE) on complex science and technical issues that arise in the planning, managing, and implementation of DOE's nuclear energy program. NEAC periodically reviews the elements of the NE program and based on these

  19. Civilian Nuclear Program

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Civilian Nuclear Program Civilian Nuclear Program Los Alamos is committed to using its advanced nuclear expertise and unique facilities to meet the civilian nuclear national security demands of the future. CONTACT US Program Director Venkateswara Rao Dasari (Rao) (505) 667-5098 Email Los Alamos partners extensively with other laboratories, universities, industry, and the international nuclear community to address real-world technical challenges The Civilian Nuclear Program is the focal point for

  20. Nuclear & Radiological Material Removal | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    & Radiological Material Removal | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation...

  1. International Nuclear Security | National Nuclear Security Administration |

    National Nuclear Security Administration (NNSA)

    (NNSA) International Nuclear Security The International Nuclear Security program collaborates with partners world-wide to improve the security of proliferation-sensitive materials, particularly weapons-usable nuclear material in both civilian and non-civilian use in key countries. As part of these efforts, INS works with partner countries to: Upgrade and sustain physical security and material control and accounting systems; Develop national-level nuclear security infrastructure in areas such

  2. Nuclear Materials Information Program | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Information Program | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the...

  3. Nuclear Security Summit | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  4. Nuclear Forensics | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Nuclear Forensics Forensics Operations The National Technical Nuclear Forensics (NTNF) program is a Homeland Security Council and National Security Council-sponsored policy initiative that establishes federal agency missions and institutionalizes roles and responsibilities to enable operational support for materials, pre-detonation device, and post-detonation nuclear or radiological forensics programs with the broader goal of attribution. Technical nuclear forensics utilizes the data from

  5. Nuclear Physics: Campaigns

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Free-Electron Laser (FEL) Medical Imaging Physics Topics Campaigns The Structure of the Nuclear Building Blocks The Structure of Nuclei Symmetry Tests in Nuclear Physics Meetings ...

  6. 2013 Nuclear Workforce Development ...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Practice in Nuclear Medicine Radiopharmacy Patient Care Medical Imaging & Computers Moderator: Deborah M. Gibbs, MEd, PET, CNMT Lead Nuclear Medicine PET Facility...

  7. Advanced Nuclear Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Energy - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us ... Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & ...

  8. Nuclear Data Links

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Links to Useful Online Nuclear Physics Journals Important Online Resources Science Direct ... Elsevier Physics Online: Nuclear Physics A, B, Physics Repots, Physics Letters B and more. ...

  9. Nuclear Controls Checklist

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Controls Yes No 1) Is your Facility involved in the research on or development, design, manufacture, construction, testing or maintenance of any nuclear explosive ...

  10. Nuclear Energy Advisory Committee

    Broader source: Energy.gov [DOE]

    The Nuclear Energy Advisory Committee (NEAC), formerly the Nuclear Energy Research Advisory Committee (NERAC), was established on October 1, 1998, to provide independent advice to the Office of...

  11. Nuclear | Open Energy Information

    Open Energy Info (EERE)

    High construction costs for nuclear plants, especially relative to natural-gas-fired plants, make other options for new nuclear capacity uneconomical even in the alternative...

  12. Nuclear Security Summit

    National Nuclear Security Administration (NNSA)

    Joint Research Centre and the United States Department of Energy's National Nuclear Security Administration regarding the reduction of excess nuclear material http:...

  13. Sandia Energy Nuclear Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    afety-expert-elected-to-national-academy-of-engineeringfeed 0 Sandia Teaches Nuclear Safety Course http:energy.sandia.govsandia-teaches-nuclear-safety-course http:...

  14. Nuclear Energy University Programs

    Energy Savers [EERE]

    (NSUF) Gateway to Nuclear Research J. Rory Kennedy Director, NSUF Idaho National ... to NSUF (Integration into CINR) * Nuclear Energy Infrastructure Database (NEID) * ...

  15. Sandia's Nuclear Weapons Mission

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Weapons Mission Ensuring that the nation's stockpile is safe, secure and effective, and that it meets military requirements America's Nuclear Weapons Systems Engineering ...

  16. Nuclear War Against Cancer

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear War Against Cancer 1663 Los Alamos science and technology magazine Latest Issue:March 2016 past issues All Issues submit Nuclear War Against Cancer Los Alamos, in ...

  17. Nuclear weapons modernizations

    SciTech Connect (OSTI)

    Kristensen, Hans M.

    2014-05-09

    This article reviews the nuclear weapons modernization programs underway in the world's nine nuclear weapons states. It concludes that despite significant reductions in overall weapons inventories since the end of the Cold War, the pace of reductions is slowing - four of the nuclear weapons states are even increasing their arsenals, and all the nuclear weapons states are busy modernizing their remaining arsenals in what appears to be a dynamic and counterproductive nuclear competition. The author questions whether perpetual modernization combined with no specific plan for the elimination of nuclear weapons is consistent with the nuclear Non-Proliferation Treaty and concludes that new limits on nuclear modernizations are needed.

  18. Advancing Global Nuclear Security

    Broader source: Energy.gov [DOE]

    Today world leaders gathered at The Hague for the Nuclear Security Summit, a meeting to measure progress and take action to secure sensitive nuclear materials.

  19. Nuclear Energy Systems Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management ...

  20. NUCLEAR REGULATORY COMMISSION

    Office of Environmental Management (EM)

    NUCLEAR REGULATORY COMMISSION 10 CFR Parts 71 and 73 RIN 3150-AG41 Advance Notification to Native American Tribes of Transportation of Certain Types of Nuclear Waste AGENCY: ...

  1. Nuclear Safety Regulatory Framework

    Energy Savers [EERE]

    Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural ...

  2. National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    U.S. Department of Energy National Nuclear Security Administration Federal Equal ... A. Name and Address of Agency National Nuclear Security Administration Office of ...

  3. National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration FY 2013 PER Babcock & Wilcox Technical Services Y-12, LLC Performance Evaluation Report NNSA Production Office Y-12 Nuclear Security Complex ...

  4. Nuclear Materials Science

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Materials Science Our multidisciplinary expertise comprises the core actinide materials science and metallurgical capability within the nuclear weapons production and ...

  5. National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    U.S. Department of Energy National Nuclear Security Administration Federal Equal ... A. Name and Address of Agency National Nuclear Security Administration 1000 Independence ...

  6. National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    15 National Nuclear Security Administration FY 2013 PER Babcock & Wilcox Technical ... The National Nuclear Security Administration (NNSA) Production Office (NPO) took into ...

  7. Sandia Energy - Nuclear Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Sandia's Brayton-Cycle Turbine Boosts Small Nuclear Reactor Efficiency Energy, Energy Efficiency, News, News & Events, Nuclear Energy Sandia's Brayton-Cycle Turbine Boosts Small...

  8. International Nuclear Safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    | (NNSA) International Nuclear Safeguards Challenge: Detect/deter undeclared nuclear materials and activities. Solution: Build capacity of the International Atomic Energy Agency and Member States to implement and meet safeguards obligations. The Office of International Nuclear Safeguards develops and supports the policies, concepts, technologies, expertise, and international safeguards infrastructure necessary to strengthen and sustain the international safeguards system as it evolves to

  9. nuclear enterprise | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    enterprise New Report from NNSA Highlights Major Achievements for 2015 Outlines Accomplishments in Stockpile Stewardship, Nuclear Nonproliferation, Naval Reactors and Managing the Nuclear Enterprise The National Nuclear Security Administration (NNSA) today released "NNSA Achievements: 2015 By the Numbers," a report highlighting major accomplishments and milestones

  10. nuclear reactors | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    nuclear reactors NNSA Researchers Advance Technology for Remote Reactor Monitoring NNSA's Defense Nuclear Nonproliferation Research and Development Program drives the innovation of technical capabilities to detect, identify, and characterize foreign nuclear weapons development activities. To achieve this, NNSA leverages the unique capabilities of the national laboratories

  11. Nuclear reactor

    DOE Patents [OSTI]

    Thomson, Wallace B.

    2004-03-16

    A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

  12. State Nuclear Profiles - Energy Information Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear & Uranium Glossary FAQS Overview Data Status of U.S. nuclear outages (interactive) Nuclear power plants Uranium & nuclear fuel Spent nuclear fuel All nuclear data ...

  13. Cancer and Aging

    SciTech Connect (OSTI)

    Campisi, Julie

    2015-05-06

    Berkeley Lab biochemist Judy Campisi discusses her work on understanding the molecular and cellular basis of aging and the control of cellular senescence and its role in tumor suppression.

  14. The Joys of Nuclear Engineering

    ScienceCinema (OSTI)

    Jon Carmack

    2010-01-08

    Nuclear fuels researcher Jon Carmack talks about the satisfactions of a career in nuclear engineering.

  15. Nuclear reactor

    DOE Patents [OSTI]

    Yant, Howard W.; Stinebiser, Karl W.; Anzur, Gregory C.

    1977-01-01

    A nuclear reactor, particularly a liquid-metal breeder reactor, whose upper internals include outlet modules for channeling the liquid-metal coolant from selected areas of the outlet of the core vertically to the outlet plenum. The modules are composed of a highly-refractory, high corrosion-resistant alloy, for example, INCONEL-718. Each module is disposed to confine and channel generally vertically the coolant emitted from a subplurality of core-component assemblies. Each module has a grid with openings, each opening disposed to receive the coolant from an assembly of the subplurality. The grid in addition serves as a holdown for the assemblies of the corresponding subplurality preventing their excessive ejection upwardly from the core. In the region directly over the core the outlet modules are of such peripheral form that they nest forming a continuum over the core-component assemblies whose outlet coolant they confine. Each subassembly includes a chimney which confines the coolant emitted by its corresponding subassemblies to generally vertical flow between the outlet of the core and the outlet plenum. Each subplurality of assemblies whose emitted coolant is confined by an outlet module includes assemblies which emit lower-temperature coolant, for example, a control-rod assembly, or fertile assemblies, and assemblies which emit coolant of substantially higher temperature, for example, fuel-rod assemblies. The coolants of different temperatures are mixed in the chimneys reducing the effect of stripping (hot-cold temperature fluctuations) on the remainder of the upper internals which are composed typically of AISI-304 or AISI-316 stainless steel.

  16. Nuclear reactor

    DOE Patents [OSTI]

    Pennell, William E.; Rowan, William J.

    1977-01-01

    A nuclear reactor in which the core components, including fuel-rod assemblies, control-rod assemblies, fertile rod-assemblies, and removable shielding assemblies, are supported by a plurality of separate inlet modular units. These units are referred to as inlet module units to distinguish them from the modules of the upper internals of the reactor. The modular units are supported, each removable independently of the others, in liners in the supporting structure for the lower internals of the reactor. The core assemblies are removably supported in integral receptacles or sockets of the modular units. The liners, units, sockets and assmblies have inlet openings for entry of the fluid. The modular units are each removably mounted in the liners with fluid seals interposed between the opening in the liner and inlet module into which the fluid enters and the upper and lower portion of the liner. Each assembly is similarly mounted in a corresponding receptacle with fluid seals interposed between the openings where the fluid enters and the lower portion of the receptacle or fitting closely in these regions. As fluid flows along each core assembly a pressure drop is produced along the fluid so that the fluid which emerges from each core assembly is at a lower pressure than the fluid which enters the core assembly. However because of the seals interposed in the mountings of the units and assemblies the pressures above and below the units and assemblies are balanced and the units are held in the liners and the assemblies are held in the receptacles by their weights as they have a higher specific gravity than the fluid. The low-pressure spaces between each module and its liner and between each core assembly and its module is vented to the low-pressure regions of the vessel to assure that fluid which leaks through the seals does not accumulate and destroy the hydraulic balance.

  17. Nuclear Resonance Fluorescence for Materials Assay

    SciTech Connect (OSTI)

    Quiter, Brian J.; Ludewigt, Bernhard; Mozin, Vladimir; Prussin, Stanley

    2009-06-29

    This paper discusses the use of nuclear resonance fluorescence (NRF) techniques for the isotopic and quantitative assaying of radioactive material. Potential applications include age-dating of an unknown radioactive source, pre- and post-detonation nuclear forensics, and safeguards for nuclear fuel cycles Examples of age-dating a strong radioactive source and assaying a spent fuel pin are discussed. The modeling work has ben performed with the Monte Carlo radiation transport computer code MCNPX, and the capability to simulate NRF has bee added to the code. Discussed are the limitations in MCNPX?s photon transport physics for accurately describing photon scattering processes that are important contributions to the background and impact the applicability of the NRF assay technique.

  18. Nuclear Resonance Fluorescence for Materials Assay

    SciTech Connect (OSTI)

    Quiter, Brian; Ludewigt, Bernhard; Mozin, Vladimir; Prussin, Stanley

    2009-06-05

    This paper discusses the use of nuclear resonance fluorescence (NRF) techniques for the isotopic and quantitative assaying of radioactive material. Potential applications include age-dating of an unknown radioactive source, pre- and post-detonation nuclear forensics, and safeguards for nuclear fuel cycles Examples of age-dating a strong radioactive source and assaying a spent fuel pin are discussed. The modeling work has ben performed with the Monte Carlo radiation transport computer code MCNPX, and the capability to simulate NRF has bee added to the code. Discussed are the limitations in MCNPX's photon transport physics for accurately describing photon scattering processes that are important contributions to the background and impact the applicability of the NRF assay technique.

  19. 2016 Nuclear Science Week

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Science Week October 17 - 21, 2016 Nuclear Science Week is a national, broadly observed week-long celebration that focuses on all aspects of nuclear science. Events during this week will provide many learning opportunities about contributions, innovation and careers that can be found by exploring nuclear science. 6-22-16

  20. Advanced nuclear fuel

    SciTech Connect (OSTI)

    Terrani, Kurt

    2014-07-14

    Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

  1. Advanced nuclear fuel

    ScienceCinema (OSTI)

    Terrani, Kurt

    2014-07-15

    Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

  2. Nuclear and Particle Futures

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    (NNSA) Nuclear Weapons Life Cycle Nuclear weapons are developed, produced, and maintained in the stockpile, and then retired and dismantled. This sequence of events is known as the nuclear weapons life cycle. The Department of Energy (DOE) through the National Nuclear Security Administration (NNSA) and in partnership with Department of Defense (DoD) conducts activities in a joint nuclear weapons life cycle process. The major steps, or phases, of the life cycle are described below. Currently,

  3. Spent Nuclear Fuel

    Gasoline and Diesel Fuel Update (EIA)

    Spent Nuclear Fuel Release date: December 7, 2015 Next release date: Late 2018 Spent nuclear fuel data are collected by the U.S. Energy Information Administration (EIA) for the Department of Energy's Office of Standard Contract Management (Office of the General Counsel) on the Form GC-859, "Nuclear Fuel Data Survey." The data include detailed characteristics of spent nuclear fuel discharged from commercial U.S. nuclear power plants and currently stored at commercial sites in the United

  4. Nuclear Security Summit | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Security Summit U.S. and China Continue Cooperative Partnership to Advance Safe, Secure Civil Nuclear Energy for Clean Energy Future DOE/NNSA Hosts 11th U.S.-China Peaceful Uses of Nuclear Technology Meeting at Savannah River National Laboratory in Aiken, South Carolina (Aiken, South Carolina) - On May 10-11, 2016 the U.S. Department of Energy's (DOE) National Nuclear Security Administration (NNSA) and the China... Statement on Signing of the Administrative Arrangement to the Agreement for

  5. defense nuclear security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    defense nuclear security NNSA Announces 2014 Security Professional of the Year Awards WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA) today announced the recipients of the 2014 Bradley A. Peterson Federal and Contractor Security Professional of the Year Awards. Pamela Valdez from the Los Alamos Field Office will receive the federal award and Randy Fraser from... Michael Lempke receives NNSA's Gold Medal of Excellence DOE Undersecretary for Nuclear Security and NNSA

  6. nuclear security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    security U.S. and China Continue Cooperative Partnership to Advance Safe, Secure Civil Nuclear Energy for Clean Energy Future DOE/NNSA Hosts 11th U.S.-China Peaceful Uses of Nuclear Technology Meeting at Savannah River National Laboratory in Aiken, South Carolina (Aiken, South Carolina) - On May 10-11, 2016 the U.S. Department of Energy's (DOE) National Nuclear Security Administration (NNSA) and the China... Secretary Moniz awards Hutcheon memorial nonproliferation fellowship to Thomas Gray

  7. nuclear weapons | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    weapons DOE, NNSA leaders open summit on the physical security of nuclear weapons Deputy Secretary of Energy Elizabeth Sherwood-Randall, NNSA Principal Deputy Administrator Madelyn Creedon, and numerous speakers from throughout the Nuclear Security Enterprise spoke at the 2016 Nuclear Weapons Physical Security Collaboration Summit earlier this month at Joint Base Andrews in... Y-12 National Security Complex Completes W69 Dismantlement The man who trains everyone on the bombs Mark Meyer, training

  8. Nuclear Detonation Detection | National Nuclear Security Administratio...

    National Nuclear Security Administration (NNSA)

    the entire planet from space to detect and report surface, atmospheric, or space nuclear detonations; produces and updates the regional geophysical datasets enabling...

  9. Nuclear Safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy ... site link , and the emergence of new proliferation threats from both state and non-state ...

  10. Nuclear Detonation Detection | National Nuclear Security Administratio...

    National Nuclear Security Administration (NNSA)

    NNSA builds the nation's operational sensors that monitor the entire planet from space to detect and report surface, atmospheric, or space nuclear detonations; produces and updates...

  11. National Nuclear Security Administration | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) National Nuclear Security Administration FY15 Year End Report Semi Annual Report FY14 Year End Report Semi Annual

  12. Wisconsin Nuclear Profile - Point Beach Nuclear Plant

    U.S. Energy Information Administration (EIA) Indexed Site

    Point Beach Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration ...

  13. nuclear smuggling | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    NNSA Deputy Administrator Creedon Travels to China In March, National Nuclear Security Administration (NNSA) Principal Deputy Administrator Madelyn Creedon traveled to China to ...

  14. Nuclear Structure and Nuclear Reactions | Argonne Leadership...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    x2 - triaxiality, and x3 - pairing correlations. Calculations were carried out using nuclear density functional theory. The collective action was minimized using the dynamical...

  15. nuclear material | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Researchers develop a new mathematical tool for analyzing and evaluating nuclear material Lawrence Livermore National Laboratory scientists have created a new method for detecting ...

  16. Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear Waste |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Minimize Nuclear Waste Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear Waste GNEP will increase the efficiency in the management of used nuclear fuel, also known as spent fuel, and defer the need for additional geologic nuclear waste repositories until the next century. Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear Waste (1.2 MB) More Documents & Publications GNEP Element:Develop Enhanced Nuclear Safeguards Global Nuclear Energy

  17. NNSA Celebrates National Nuclear Science Week | National Nuclear...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Celebrates National Nuclear Science Week January 23, 2012 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA) is committed to promoting excellence in nuclear ...

  18. NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 05 NUCLEAR FUELS...

    Office of Scientific and Technical Information (OSTI)

    Title list of documents made publicly available, January 1-31, 1998 NONE 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 05 NUCLEAR FUELS; BIBLIOGRAPHIES; NUCLEAR POWER PLANTS;...

  19. NNSA Nuclear/Radiological Incident Response | National Nuclear...

    National Nuclear Security Administration (NNSA)

    NNSA NuclearRadiological Incident Response December 01, 2008 The National Nuclear Security Administration (NNSA) has over 60 years of nuclear weapons experience in responding to ...

  20. Nuclear Engineering | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Milestones Publications News Press Releases Features Science Highlights In the ... Divisions Energy Systems Global Security Sciences Nuclear Engineering Nuclear Milestones ...

  1. Nuclear Physics from Lattice QCD

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Thursday, May 26, 2011 Exa-Scale Computational Resources Nuclear Astrophysics Accelerator Physics Cold QCD and Nuclear Forces Hot and Dense QCD Nuclear Structure and Reactions ...

  2. budget | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Reflects Commitment to Maintain a Safe, Secure, and Effective Nuclear Deterrent; Prevent, Counter, and Respond to Global Nuclear Dangers; and Effectively Power the Nuclear Navy(...

  3. Seismic ruggedness of aged electrical components: Final report (Phase 2)

    SciTech Connect (OSTI)

    Gleason, J.F.

    1987-01-01

    Seismic tests on new and aged components have shown that, for many types of commonly used nuclear plant electrical components, deterioration due to aging does not significantly affect the ability of the components to function during and after a seismic event. This was demonstrated for capacitors, circuit breakers, contactors (motor starters), control station assemblies, electronic alarms, electronics, fuses, fuse blocks, inductors, meters, motors, pressure transmitters, power supplies, relays, RTDs, solenoid valves, terminal blocks, time delay relays, transformers and switches. A few switch types (limit, pressure and rotary) were observed to be more prone to contact chatter in an aged condition than in an unaged condition. However, the ability of these devices to switch during and after shaking was not affected by aging. These results can be referenced to eliminate the cost of aging prior to seismic qualification testing for many types of electrical components.

  4. Nuclear Regulatory Commission | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Nuclear Regulatory Commission NNSA Receives Excellence Award for Radiological Security Enhancements in Hawaii HONOLULU - At an official event this week, the City and County of Honolulu presented the Department of Energy's (DOE) National Nuclear Security Administration (NNSA) with the Homeland Security Excellence Award for DOE/NNSA's Office of Radiological Security's (ORS) efforts

  5. nuclear safety | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    safety United States and the Republic of Korea Sign Agreement for Civil Nuclear Cooperation Washington, DC - Today Secretary of Energy Ernest J. Moniz and Korean Foreign Minister Yun signed the successor United States - Republic of Korea Agreement for Civil Nuclear Cooperation, or 123 Agreement, as they are referred to in the United States. The United States and the Republic of Korea (ROK

  6. nuclear technology | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    technology NNSA Updates Export Control Regulation WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA) updated the Federal rule (10 CFR Part 810, or Part 810) that regulates the export of unclassified nuclear technology and assistance. The final rule was published in the Federal Register on Feb. 23 and will go into effect on

  7. Naval Nuclear Propulsion | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Naval Nuclear Propulsion Klotz visits Bettis Atomic Power Laboratory Lt. Gen. Frank G. Klotz, DOE Undersecretary for Nuclear Security and NNSA Administrator, visited the Bettis Atomic Power Laboratory in West Mifflin, PA on July 2, 2015. Gen. Klotz toured through several test facilities where Bettis personnel reviewed ongoing development efforts to qualify

  8. nuclear testing | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    testing NNSA scientists find more effective ways to detect nuclear explosions near and far NNSA activities are vital to detecting nuclear explosions and helping verify compliance with the testing ban worldwide. Recent developments at NNSA's Livermore National Laboratory (LLNL) will help NNSA meet this commitment. Using computer-generated models and field experiments, LLNL simulates how

  9. Nuclear Security for Floating Nuclear Power Plants

    SciTech Connect (OSTI)

    Skiba, James M.; Scherer, Carolynn P.

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  10. Signatures of aging revisited

    SciTech Connect (OSTI)

    Drell, S.; Jeanloz, R.; Cornwall, J.; Dyson, F.; Eardley, D.

    1998-03-18

    This study is a follow-on to the review made by JASON during its 1997 Summer Study of what is known about the aging of critical constituents, particularly the high explosives, metals (Pu, U), and polymers in the enduring stockpile. The JASON report (JSR-97-320) that summarized the findings was based on briefings by the three weapons labs (LANL, LLNL, SNL). They presented excellent technical analyses covering a broad range of scientific and engineering problems pertaining to determining signatures of aging. But the report also noted: `Missing, however, from the briefings and the written documents made available to us by the labs and DOE, was evidence of an adequately sharp focus and high priorities on a number of essential near-term needs of maintaining weapons in the stockpile.