Sample records for enhancing nuclear safeguards

  1. A new approach to nuclear fuel safeguard enhancement through radionuclide profiling

    NASA Astrophysics Data System (ADS)

    Peterson, Aaron Dawon

    The United States has led the effort to promote peaceful use of nuclear power amongst states actively utilizing it as well as those looking to deploy the technology in the near future. With the attraction being demonstrated by various countries towards nuclear power comes the concern that a nation may have military aspirations for the use of nuclear energy. The International Atomic Energy Agency (IAEA) has established nuclear safeguard protocols and procedures to mitigate nuclear proliferation. The work herein proposed a strategy to further enhance existing safeguard protocols by considering safeguard in nuclear fuel design. The strategy involved the use of radionuclides to profile nuclear fuels. Six radionuclides were selected as identifier materials. The decay and transmutation of these radionuclides were analyzed in reactor operation environment. MCNPX was used to simulate a reactor core. The perturbation in reactivity of the core due to the loading of the radionuclides was insignificant. The maximum positive and negative reactivity change induced was at day 1900 with a value of 0.00185 +/- 0.00256 and at day 2000 with -0.00441 +/- 0.00249, respectively. The mass of the radionuclides were practically unaffected by transmutation in the core; the change in radionuclide inventory was dominated by natural decay. The maximum material lost due to transmutation was 1.17% in Eu154. Extraneous signals from fission products identical to the radionuclide compromised the identifier signals. Eu154 saw a maximum intensity change at EOC and 30 days post-irradiation of 1260% and 4545%, respectively. Cs137 saw a minimum change of 12% and 89%, respectively. Mitigation of the extraneous signals is cardinal to the success of the proposed strategy. The predictability of natural decay provides a basis for the characterization of the signals from the radionuclide.

  2. Nuclear materials safeguards for the future

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Tape, J.W.

    Basic concepts of domestic and international safeguards are described, with an emphasis on safeguards systems for the fuel cycles of commercial power reactors. Future trends in institutional and technical measures for nuclear materials safeguards are outlined. The conclusion is that continued developments in safeguards approaches and technology, coupled with institutional measures that facilitate the global management and protection of nuclear materials, are up to the challenge of safeguarding the growing inventories of nuclear materials in commercial fuel cycles in technologically advanced States with stable governments that have signed the nonproliferation treaty. These same approaches also show promise for facilitating internationalmore » inspection of excess weapons materials and verifying a fissile materials cutoff convention.« less

  3. Safeguards Guidance Document for Designers of Commercial Nuclear Facilities: International Nuclear Safeguards Requirements and Practices For Uranium Enrichment Plants

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Robert Bean; Casey Durst

    2009-10-01

    This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called “Safeguards-by-Design.” This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichmentmore » plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, “International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,” published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is

  4. Technical Training Workshop on International Safeguards: An Introduction to Safeguards for Emerging Nuclear States

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Frazar, Sarah L.; Gastelum, Zoe N.; Olson, Jarrod

    2009-10-06

    The U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA) hosted a workshop from May 4-22, 2009, on the fundamental elements of international safeguards. Entitled "A Technical Training Workshop on International Safeguards," the workshop introduced post-graduate students from Malaysia, Vietnam, Indonesia, Thailand, Morocco, Egypt, Algeria and Tunisia to the fundamental issues and best practices associated with international safeguards and encouraged them to explore potential career paths in safeguards. Workshops like these strengthen the international safeguards regime by promoting the development of a "safeguards culture" among young nuclear professionals within nascent nuclear countries. While this concept of safeguards culture is sometimes hardmore » to define and even harder to measure, this paper will demonstrate that the promotion of safeguards cultures through workshops like these justifies the investment of U.S. taxpayer dollars.« less

  5. Nuclear proliferation-resistance and safeguards for future nuclear fuel cycle

    NASA Astrophysics Data System (ADS)

    Kuno, Y.; Inoue, N.; Senzaki, M.

    2009-03-01

    Corresponding to the world nuclear security concerns, future nuclear fuel cycle (NFC) should have high proliferation-resistance (PR) and physical protection (PP), while promotion of the peaceful use of the nuclear energy must not be inhibited. In order to accomplish nuclear non-proliferation from NFC, a few models of the well-PR systems should be developed so that international community can recognize them as worldwide norms. To find a good balance of 'safeguard-ability (so-called extrinsic measure or institutional barrier)' and 'impede-ability (intrinsic feature or technical barrier)' will come to be essential for NFC designers to optimize civilian nuclear technology with nuclear non-proliferation, although the advanced safeguards with high detectability can still play a dominant role for PR in the states complying with full institutional controls. Accomplishment of such goal in a good economic efficiency is a future key challenge.

  6. Brain Science and International Nuclear Safeguards: Implications from Cognitive Science and Human Factors Research on the Provision and Use of Safeguards-Relevant Information in the Field

    DOE PAGES

    Gastelum, Zoe Nellie; Matzen, Laura E.; Smartt, Heidi A.; ...

    2017-06-01

    Today’s international nuclear safeguards inspectors have access to an increasing volume of supplemental information about the facilities under their purview, including commercial satellite imagery, nuclear trade data, open source information, and results from previous safeguards activities. In addition to completing traditional in-field safeguards activities, inspectors are now responsible for being able to act upon this growing corpus of supplemental safeguards-relevant data and for maintaining situational awareness of unusual activities taking place in their environment. However, cognitive science research suggests that maintaining too much information can be detrimental to a user’s understanding, and externalizing information (for example, to a mobile device)more » to reduce cognitive burden can decrease cognitive function related to memory, navigation, and attention. Given this dichotomy, how can international nuclear safeguards inspectors better synthesize information to enhance situational awareness, decision making, and performance in the field? This paper examines literature from the fields of cognitive science and human factors in the areas of wayfinding, situational awareness, equipment and technical assistance, and knowledge transfer, and describes the implications for the provision of, and interaction with, safeguards-relevant information for international nuclear safeguards inspectors working in the field.« less

  7. Brain Science and International Nuclear Safeguards: Implications from Cognitive Science and Human Factors Research on the Provision and Use of Safeguards-Relevant Information in the Field

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gastelum, Zoe Nellie; Matzen, Laura E.; Smartt, Heidi A.

    Today’s international nuclear safeguards inspectors have access to an increasing volume of supplemental information about the facilities under their purview, including commercial satellite imagery, nuclear trade data, open source information, and results from previous safeguards activities. In addition to completing traditional in-field safeguards activities, inspectors are now responsible for being able to act upon this growing corpus of supplemental safeguards-relevant data and for maintaining situational awareness of unusual activities taking place in their environment. However, cognitive science research suggests that maintaining too much information can be detrimental to a user’s understanding, and externalizing information (for example, to a mobile device)more » to reduce cognitive burden can decrease cognitive function related to memory, navigation, and attention. Given this dichotomy, how can international nuclear safeguards inspectors better synthesize information to enhance situational awareness, decision making, and performance in the field? This paper examines literature from the fields of cognitive science and human factors in the areas of wayfinding, situational awareness, equipment and technical assistance, and knowledge transfer, and describes the implications for the provision of, and interaction with, safeguards-relevant information for international nuclear safeguards inspectors working in the field.« less

  8. Deterring Nuclear Proliferation: The Importance of IAEA Safeguards: A TEXTBOOK

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rosenthal, M.D.; Fishbone, L.G.; Gallini, L.

    2012-03-13

    Nuclear terrorism and nuclear proliferation are among the most pressing challenges to international peace and security that we face today. Iran and Syria remain in non-compliance with the safeguards requirements of the NPT, and the nuclear ambitions of North Korea remain unchecked. Despite these challenges, the NPT remains a cornerstone of the nuclear non-proliferation regime, and the safeguards implemented by the International Atomic Energy Agency (IAEA) under the NPT play a critical role in deterring nuclear proliferation.How do they work? Where did they come from? And what is their future? This book answers these questions. Anyone studying the field ofmore » nuclear non-proliferation will benefit from reading this book, and for anyone entering the field, the book will enable them to get a running start. Part I describes the foundations of the international safeguards system: its origins in the 1930s - when new discoveries in physics made it clear immediately that nuclear energy held both peril and promise - through the entry into force in 1970 of the NPT, which codified the role of IAEA safeguards as a means to verify states NPT commitments not to acquire nuclear weapons. Part II describes the NPT safeguards system, which is based on a model safeguards agreement developed specifically for the NPT, The Structure and Content of Agreements between the Agency and States required in connection with the Treaty on the Non-Proliferation of Nuclear Weapons, which has been published by the IAEA as INFCIRC/153. Part III describes events, especially in South Africa, the DPRK, and Iraq in the early 1990s, that triggered a transformation in the way in which safeguards were conceptualized and implemented.« less

  9. Nuclear safeguards in Brazil and Argentina: 25 years of ABACC

    NASA Astrophysics Data System (ADS)

    Kassenova, Togzhan

    2017-11-01

    As possessors of advanced nuclear technology, Brazil and Argentina bear special responsibility for helping the international community and neighbors in their region feel confident that their nuclear programs are peaceful, secure, and safe. Over the past 25 years, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) has played an indispensable role in strengthening such confidence by implementing nuclear safeguards in the two countries. Today, ABACC carries out safeguards inspections at a total of 76 nuclear facilities in Brazil and Argentina. This article describes how Brazil and Argentina view trends in the global nonproliferation regime and international nuclear safeguards, and explains how these trends relate to unique challenges and opportunities facing Brazil, Argentina, and ABACC.

  10. Termination of Safeguards for Accountable Nuclear Materials at the Idaho National Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Michael Holzemer; Alan Carvo

    2012-04-01

    Termination of safeguards ends requirements of Nuclear Material Control and Accountability (MC&A) and thereby removes the safeguards basis for applying physical protection requirements for theft and diversion of nuclear material, providing termination requirements are met as described. Department of Energy (DOE) M 470.4 6 (Nuclear Material Control and Accountability [8/26/05]) stipulates: 1. Section A, Chapter I (1)( q) (1): Safeguards can be terminated on nuclear materials provided the following conditions are met: (a) 'If the material is special nuclear material (SNM) or protected as SNM, it must be attractiveness level E and have a measured value.' (b) 'The material hasmore » been determined by DOE line management to be of no programmatic value to DOE.' (c) 'The material is transferred to the control of a waste management organization where the material is accounted for and protected in accordance with waste management regulations. The material must not be collocated with other accountable nuclear materials.' Requirements for safeguards termination depend on the safeguards attractiveness levels of the material. For attractiveness level E, approval has been granted from the DOE Idaho Operations Office (DOE ID) to Battelle Energy Alliance, LLC (BEA) Safeguards and Security (S&S). In some cases, it may be necessary to dispose of nuclear materials of attractiveness level D or higher. Termination of safeguards for such materials must be approved by the Departmental Element (this is the DOE Headquarters Office of Nuclear Energy) after consultation with the Office of Security.« less

  11. A Priority-Based View of Future Challenges in International Nuclear Safeguards.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Matteucci, Kayla

    The international nuclear safeguards community is faced with a host of challenges in the coming years, many of which have been outlined but have not been described in terms of their urgency. Literature regarding safeguards challenges is either broad and devoid of any reference to prioritization or tailored to a specific problem and removed from the overall goals of the safeguards community. For example, developing new methods of environmental sampling, improving containment and surveillance (C/S) technologies to increase efficiency and decrease inspection time, advancing nuclear material accountancy (NMA) techniques, and planning safeguards approaches for new types of nuclear facilities aremore » all important. They have not, however, been distinctly prioritized at a high level within the safeguards community. Based on a review of existing literature and interviews with experts on these upcoming challenges, this paper offers a high-level summary of present and future priorities in safeguards, with attention both to what is feasible and to what is most imperative. In doing so, the paper addresses the potential repercussions for failing to prioritize, with a focus on the risk of diversion of nuclear material. Within the context of shifts in the American political landscape, and keeping in mind that nonproliferation issues may take a backseat to others in the near future, a prioritized view of safeguards objectives will be vital. In the interest of expanding upon this work, the paper offers several potential conceptual models for prioritization which can be explored in greater depth upon further research.« less

  12. International training course on nuclear materials accountability for safeguards purposes

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1980-12-01

    The two volumes of this report incorporate all lectures and presentations at the International Training Course on Nuclear Materials Accountability and Control for Safeguards Purposes, held May 27-June 6, 1980, at the Bishop's Lodge near Santa Fe, New Mexico. The course, authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, was developed to provide practical training in the design, implementation, and operation of a National system of nuclear materials accountability and control that satisfies both National and IAEA International safeguards objectives. Volume I, covering the firstmore » week of the course, presents the background, requirements, and general features of material accounting and control in modern safeguard systems. Volume II, covering the second week of the course, provides more detailed information on measurement methods and instruments, practical experience at power reactor and research reactor facilities, and examples of operating state systems of accountability and control.« less

  13. Organizational Culture for Safety, Security, and Safeguards in New Nuclear Power Countries

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kovacic, Donald N

    2015-01-01

    This chapter will contain the following sections: Existing international norms and standards for developing the infrastructure to support new nuclear power programs The role of organizational culture and how it supports the safe, secure, and peaceful application of nuclear power Identifying effective and efficient strategies for implementing safety, security and safeguards in nuclear operations Challenges identified in the implementation of safety, security and safeguards Potential areas for future collaboration between countries in order to support nonproliferation culture

  14. Integrated Process Monitoring based on Systems of Sensors for Enhanced Nuclear Safeguards Sensitivity and Robustness

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Humberto E. Garcia

    This paper illustrates safeguards benefits that process monitoring (PM) can have as a diversion deterrent and as a complementary safeguards measure to nuclear material accountancy (NMA). In order to infer the possible existence of proliferation-driven activities, the objective of NMA-based methods is often to statistically evaluate materials unaccounted for (MUF) computed by solving a given mass balance equation related to a material balance area (MBA) at every material balance period (MBP), a particular objective for a PM-based approach may be to statistically infer and evaluate anomalies unaccounted for (AUF) that may have occurred within a MBP. Although possibly being indicativemore » of proliferation-driven activities, the detection and tracking of anomaly patterns is not trivial because some executed events may be unobservable or unreliably observed as others. The proposed similarity between NMA- and PM-based approaches is important as performance metrics utilized for evaluating NMA-based methods, such as detection probability (DP) and false alarm probability (FAP), can also be applied for assessing PM-based safeguards solutions. To this end, AUF count estimates can be translated into significant quantity (SQ) equivalents that may have been diverted within a given MBP. A diversion alarm is reported if this mass estimate is greater than or equal to the selected value for alarm level (AL), appropriately chosen to optimize DP and FAP based on the particular characteristics of the monitored MBA, the sensors utilized, and the data processing method employed for integrating and analyzing collected measurements. To illustrate the application of the proposed PM approach, a protracted diversion of Pu in a waste stream was selected based on incomplete fuel dissolution in a dissolver unit operation, as this diversion scenario is considered to be problematic for detection using NMA-based methods alone. Results demonstrate benefits of conducting PM under a system

  15. Possible Nuclear Safeguards Applications: Workshop on Next-Generation Laser Compton Gamma Source

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Durham, J. Matthew

    2016-11-17

    These are a set of slides for the development of a next-generation photon source white paper. The following topics are covered in these slides: Nuclear Safeguards; The Nuclear Fuel Cycle; Precise isotopic determination via NRF; UF 6 Enrichment Assay; and Non-Destructive Assay of Spent Nuclear Fuel. In summary: A way to non-destructively measure precise isotopics of ~kg and larger samples has multiple uses in nuclear safeguards; Ideally this is a compact, fieldable device that can be used by international inspectors. Must be rugged and reliable; A next-generation source can be used as a testing ground for these techniques as technologymore » develops.« less

  16. The U.S./IAEA Workshop on Software Sustainability for Safeguards Instrumentation: Report to the NNSA DOE Office of International Nuclear Safeguards (NA-241)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pepper, Susan E.; Pickett, Chris A.; Queirolo, Al

    The U.S Department of Energy (DOE) National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) and the International Atomic Energy Agency (IAEA) convened a workshop on Software Sustainability for Safeguards Instrumentation in Vienna, Austria, May 6-8, 2014. Safeguards instrumentation software must be sustained in a changing environment to ensure existing instruments can continue to perform as designed, with improved security. The approaches to the development and maintenance of instrument software used in the past may not be the best model for the future and, therefore, the organizers’ goal was to investigate these past approaches and to determine an optimalmore » path forward. The purpose of this report is to provide input for the DOE NNSA Office of International Nuclear Safeguards (NA-241) and other stakeholders that can be utilized when making decisions related to the development and maintenance of software used in the implementation of international nuclear safeguards. For example, this guidance can be used when determining whether to fund the development, upgrade, or replacement of a particular software product. The report identifies the challenges related to sustaining software, and makes recommendations for addressing these challenges, supported by summaries and detailed notes from the workshop discussions. In addition the authors provide a set of recommendations for institutionalizing software sustainability practices in the safeguards community. The term “software sustainability” was defined for this workshop as ensuring that safeguards instrument software and algorithm functionality can be maintained efficiently throughout the instrument lifecycle, without interruption and providing the ability to continue to improve that software as needs arise.« less

  17. Scoping Study of Machine Learning Techniques for Visualization and Analysis of Multi-source Data in Nuclear Safeguards

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cui, Yonggang

    In implementation of nuclear safeguards, many different techniques are being used to monitor operation of nuclear facilities and safeguard nuclear materials, ranging from radiation detectors, flow monitors, video surveillance, satellite imagers, digital seals to open source search and reports of onsite inspections/verifications. Each technique measures one or more unique properties related to nuclear materials or operation processes. Because these data sets have no or loose correlations, it could be beneficial to analyze the data sets together to improve the effectiveness and efficiency of safeguards processes. Advanced visualization techniques and machine-learning based multi-modality analysis could be effective tools in such integratedmore » analysis. In this project, we will conduct a survey of existing visualization and analysis techniques for multi-source data and assess their potential values in nuclear safeguards.« less

  18. The European Safeguards Research and Development Association Addresses Safeguards and Nonproliferation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Janssens-Maenhout, Greet; Kusumi, R.; Daures, Pascal A.

    2010-06-16

    The renaissance of efforts to expand the use of nuclear energy requires the parallel development of a renewed and more sophisticated work force. Growth in the nuclear sector with high standard of safety, safeguards and security requires skilled staff for design, operations, inspections etc. High-quality nuclear technology educational programs are diminished from past years, and the ability of universities to attract students and to meet future staffing requirements of the nuclear industry is becoming seriously compromised. Thus, education and training in nuclear engineering and sciences is one of the cornerstones for the nuclear sector. Teaching in the nuclear field stillmore » seems strongly influenced by national history but it is time to strengthen resources and collaborate. Moreover with the current nuclear security threats it becomes critical that nuclear technology experts master the basic principles not only of safety, but also of nuclear safeguards, nonproliferation and nuclear security. In Europe the European Nuclear Education Network (ENEN) Association has established the certificate 'European Master of Science in Nuclear Engineering (EMSNE)' as the classic nuclear engineering program covering reactor operation and nuclear safety. However, it does not include courses on nonproliferation, safeguards, or dual-use technologies. The lack of education in nuclear safeguards was tackled by the European Safeguards Research and Development Association (ESARDA), through development and implementation of safeguards course modules. Since 2005 the ESARDA Working Group, called the Training and Knowledge Management Working Group, (TKMWG) has worked with the Joint Research Centre (JRC) in Ispra, Italy to organize a Nuclear Safeguards and Nonproliferation course. This five-day course is held each spring at the JRC, and continues to show increasing interest as evidenced by the positive responses of international lecturers and students. The standard set of lectures covers

  19. Enhancing Efficiency of Safeguards at Facilities that are Shutdown or Closed-Down, including those being Decommissioned

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moran, B.; Stern, W.; Colley, J.

    International Atomic Energy Agency (IAEA) safeguards involves verification activities at a wide range of facilities in a variety of operational phases (e.g., under construction, start-up, operating, shutdown, closed-down, and decommissioned). Safeguards optimization for each different facility type and operational phase is essential for the effectiveness of safeguards implementation. The IAEA’s current guidance regarding safeguards for the different facility types in the various lifecycle phases is provided in its Design Information Examination (DIE) and Verification (DIV) procedure. 1 Greater efficiency in safeguarding facilities that are shut down or closed down, including those being decommissioned, could allow the IAEA to use amore » greater portion of its effort to conduct other verification activities. Consequently, the National Nuclear Security Administration’s Office of International Nuclear Safeguards sponsored this study to evaluate whether there is an opportunity to optimize safeguards approaches for facilities that are shutdown or closed-down. The purpose of this paper is to examine existing safeguards approaches for shutdown and closed-down facilities, including facilities being decommissioned, and to seek to identify whether they may be optimized.« less

  20. An expanded safeguards role for the DOE safeguards analytical laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bingham, C.D.

    The New Brunswick Laboratory (NBL) is a Government-owned, Government-operated (GOGO) laboratory, with the mission to provide and maintain a nuclear material measurements and standards laboratory. The functional responsibilities of NBL serve as a technical response to the statutory responsibility of the Department of Energy (DOE) to assure the safeguarding of nuclear materials. In the execution of its mission, NBL carries out activities in six safeguards-related programs: measurement development, measurement evaluation, measurement services, safeguards assessment, reference and calibration materials and site-specific assistance. These program activities have been implemented by NBL for many years; their relative emphases, however, have been changed recentlymore » to address the priorities defined by the DOE Office of Safeguards and Security, Defense Programs (OSS/DP). As a consequence, NBL operations are in the ''mainstream'' of domestic safeguards activities. This expanded safeguards role for NBL is discussed in this paper.« less

  1. 10 CFR Appendix C to Part 73 - Nuclear Power Plant Safeguards Contingency Plans

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Nuclear Power Plant Safeguards Contingency Plans C Appendix C to Part 73 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND... sabotage relating to special nuclear material or nuclear facilities licensed under the Atomic Energy Act of...

  2. 10 CFR Appendix C to Part 73 - Nuclear Power Plant Safeguards Contingency Plans

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Nuclear Power Plant Safeguards Contingency Plans C Appendix C to Part 73 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND... sabotage relating to special nuclear material or nuclear facilities licensed under the Atomic Energy Act of...

  3. Application of Framework for Integrating Safety, Security and Safeguards (3Ss) into the Design Of Used Nuclear Fuel Storage Facility

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Badwan, Faris M.; Demuth, Scott F

    Department of Energy’s Office of Nuclear Energy, Fuel Cycle Research and Development develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development focused on used nuclear fuel recycling and waste management to meet U.S. needs. Used nuclear fuel is currently stored onsite in either wet pools or in dry storage systems, with disposal envisioned in interim storage facility and, ultimately, in a deep-mined geologic repository. The safe management and disposition of used nuclear fuel and/or nuclear waste is amore » fundamental aspect of any nuclear fuel cycle. Integrating safety, security, and safeguards (3Ss) fully in the early stages of the design process for a new nuclear facility has the potential to effectively minimize safety, proliferation, and security risks. The 3Ss integration framework could become the new national and international norm and the standard process for designing future nuclear facilities. The purpose of this report is to develop a framework for integrating the safety, security and safeguards concept into the design of Used Nuclear Fuel Storage Facility (UNFSF). The primary focus is on integration of safeguards and security into the UNFSF based on the existing Nuclear Regulatory Commission (NRC) approach to addressing the safety/security interface (10 CFR 73.58 and Regulatory Guide 5.73) for nuclear power plants. The methodology used for adaptation of the NRC safety/security interface will be used as the basis for development of the safeguards /security interface and later will be used as the basis for development of safety and safeguards interface. Then this will complete the integration cycle of safety, security, and safeguards. The overall methodology for integration of 3Ss will be proposed, but only the integration of safeguards and security will be applied to the design

  4. Self-Reliability and Motivation in a Nuclear Security Culture Enhancement Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Crawford, Cary E.; de Boer, Gloria; De Castro, Kara

    2010-10-01

    The threat of nuclear terrorism has become a global concern. Many countries continue to make efforts to strengthen nuclear security by enhancing systems of nuclear material protection, control, and accounting (MPC&A). Though MPC&A systems can significantly upgrade nuclear security, they do not eliminate the “human factor.” Gen. Eugene Habiger, a former “Assistant Secretary for Safeguards and Security” at the U.S. Department of Energy’s (DOE) nuclear-weapons complex and a former commander of U.S. strategic nuclear forces, has observed that “good security is 20% equipment and 80% people.”1 Although eliminating the “human factor” is not possible, accounting for and mitigating the riskmore » of the insider threat is an essential element in establishing an effective nuclear security culture. This paper will consider the organizational role in mitigating the risk associated with the malicious insider through monitoring and enhancing human reliability and motivation as well as enhancing the nuclear security culture.« less

  5. Self-Reliability and Motivation in a Nuclear Security Culture Enhancement Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rogers,E.; deBoer,G.; Crawford, C.

    2009-10-19

    The threat of nuclear terrorism has become a global concern. Many countries continue to make efforts to strengthen nuclear security by enhancing systems of nuclear material protection, control, and accounting (MPC&A). Though MPC&A systems can significantly upgrade nuclear security, they do not eliminate the "human factor." Gen. Eugene Habiger, a former "Assistant Secretary for Safeguards and Security" at the U.S. Department of Energy’s (DOE) nuclear-weapons complex and a former commander of U.S. strategic nuclear forces, has observed that "good security is 20% equipment and 80% people." Although eliminating the "human factor" is not possible, accounting for and mitigating the riskmore » of the insider threat is an essential element in establishing an effective nuclear security culture. This paper will consider the organizational role in mitigating the risk associated with the malicious insider through monitoring and enhancing human reliability and motivation as well as enhancing the nuclear security culture.« less

  6. Safeguards by Design Challenge

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Alwin, Jennifer Louise

    The International Atomic Energy Agency (IAEA) defines Safeguards as a system of inspection and verification of the peaceful uses of nuclear materials as part of the Nuclear Nonproliferation Treaty. IAEA oversees safeguards worldwide. Safeguards by Design (SBD) involves incorporation of safeguards technologies, techniques, and instrumentation during the design phase of a facility, rather that after the fact. Design challenge goals are the following: Design a system of safeguards technologies, techniques, and instrumentation for inspection and verification of the peaceful uses of nuclear materials. Cost should be minimized to work with the IAEA’s limited budget. Dose to workers should always bemore » as low are reasonably achievable (ALARA). Time is of the essence in operating facilities and flow of material should not be interrupted significantly. Proprietary process information in facilities may need to be protected, thus the amount of information obtained by inspectors should be the minimum required to achieve the measurement goal. Then three different design challenges are detailed: Plutonium Waste Item Measurement System, Marine-based Modular Reactor, and Floating Nuclear Power Plant (FNPP).« less

  7. Certified reference materials and reference methods for nuclear safeguards and security.

    PubMed

    Jakopič, R; Sturm, M; Kraiem, M; Richter, S; Aregbe, Y

    2013-11-01

    Confidence in comparability and reliability of measurement results in nuclear material and environmental sample analysis are established via certified reference materials (CRMs), reference measurements, and inter-laboratory comparisons (ILCs). Increased needs for quality control tools in proliferation resistance, environmental sample analysis, development of measurement capabilities over the years and progress in modern analytical techniques are the main reasons for the development of new reference materials and reference methods for nuclear safeguards and security. The Institute for Reference Materials and Measurements (IRMM) prepares and certifices large quantities of the so-called "large-sized dried" (LSD) spikes for accurate measurement of the uranium and plutonium content in dissolved nuclear fuel solutions by isotope dilution mass spectrometry (IDMS) and also develops particle reference materials applied for the detection of nuclear signatures in environmental samples. IRMM is currently replacing some of its exhausted stocks of CRMs with new ones whose specifications are up-to-date and tailored for the demands of modern analytical techniques. Some of the existing materials will be re-measured to improve the uncertainties associated with their certified values, and to enable laboratories to reduce their combined measurement uncertainty. Safeguards involve the quantitative verification by independent measurements so that no nuclear material is diverted from its intended peaceful use. Safeguards authorities pay particular attention to plutonium and the uranium isotope (235)U, indicating the so-called 'enrichment', in nuclear material and in environmental samples. In addition to the verification of the major ratios, n((235)U)/n((238)U) and n((240)Pu)/n((239)Pu), the minor ratios of the less abundant uranium and plutonium isotopes contain valuable information about the origin and the 'history' of material used for commercial or possibly clandestine purposes, and

  8. Nuclear Resonance Fluorescence Measurements on ^237Np for Security and Safeguards Applications

    NASA Astrophysics Data System (ADS)

    Angell, C. T.; Joshi, T.; Yee, Ryan; Norman, E. B.; Kulp, W. D.; Warren, G. A.; Korbly, S.; Klimenko, A.; Wilson, C.; Copping, R.; Shuh, D. K.

    2009-10-01

    The smuggling of nuclear material and the diversion of fissile material for covert weapon programs both present grave risks to world security. Methods are needed to detect nuclear material smuggled in cargo, and for proper material accountability in civilian fuel re-processing facilities. Nuclear resonance fluorescence (NRF) is a technique that can address both needs. It is a non-destructive active interrogation method that provides isotope-specific information. It works by using a γ-ray beam to resonantly excite levels in a nucleus and observing the γ-rays emitted whose energy and intensity are characteristic of that isotope. ^237Np presents significant safeguard challenges; it is fissile yet currently has fewer safeguard restrictions. NRF measurements on ^237Np will expand the nuclear database and will permit designing interrogation and assay systems. Measurements were made using the bremsstrahlung beam at the HVRL at MIT on a 7 g target of ^237Np with two incident electron energies of 2.8 and 3.1 MeV. Results will be presented with discussion of the relevant nuclear structure necessary to predict levels in other actinides.

  9. NNSA Signs Memorandum with Kuwait to Increase Cooperation on Nuclear Safeguards and Nonproliferation

    ScienceCinema

    Thomas D'Agostino

    2017-12-09

    On June 23, 2010, the National Nuclear Security Administration (NNSA) signed a Memorandum of Cooperation on nuclear safeguards and other nonproliferation topics with the Kuwait National Nuclear Energy Committee (KNNEC). NNSA Administrator Thomas D'Agostino and KNNEC's Secretary General, Dr. Ahmad Bishara, signed the memorandum at a ceremony at U.S. Department of Energy headquarters in Washington.

  10. INDUSTRIAL CONTROL SYSTEM CYBER SECURITY: QUESTIONS AND ANSWERS RELEVANT TO NUCLEAR FACILITIES, SAFEGUARDS AND SECURITY

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Robert S. Anderson; Mark Schanfein; Trond Bjornard

    2011-07-01

    Typical questions surrounding industrial control system (ICS) cyber security always lead back to: What could a cyber attack do to my system(s) and; how much should I worry about it? These two leading questions represent only a fraction of questions asked when discussing cyber security as it applies to any program, company, business, or organization. The intent of this paper is to open a dialog of important pertinent questions and answers that managers of nuclear facilities engaged in nuclear facility security and safeguards should examine, i.e., what questions should be asked; and how do the answers affect an organization's abilitymore » to effectively safeguard and secure nuclear material. When a cyber intrusion is reported, what does that mean? Can an intrusion be detected or go un-noticed? Are nuclear security or safeguards systems potentially vulnerable? What about the digital systems employed in process monitoring, and international safeguards? Organizations expend considerable efforts to ensure that their facilities can maintain continuity of operations against physical threats. However, cyber threats particularly on ICSs may not be well known or understood, and often do not receive adequate attention. With the disclosure of the Stuxnet virus that has recently attacked nuclear infrastructure, many organizations have recognized the need for an urgent interest in cyber attacks and defenses against them. Several questions arise including discussions about the insider threat, adequate cyber protections, program readiness, encryption, and many more. These questions, among others, are discussed so as to raise the awareness and shed light on ways to protect nuclear facilities and materials against such attacks.« less

  11. Visualizing Safeguards: Software for Conceptualizing and Communicating Safeguards Data

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gallucci, N.

    2015-07-12

    The nuclear programs of states are complex and varied, comprising a wide range of fuel cycles and facilities. Also varied are the types and terms of states’ safeguards agreements with the IAEA, each placing different limits on the inspectorate’s access to these facilities. Such nuances make it difficult to draw policy significance from the ground-level nuclear activities of states, or to attribute ground-level outcomes to the implementation of specific policies or initiatives. While acquiring a firm understanding of these relationships is critical to evaluating and formulating effective policy, doing so requires collecting and synthesizing large bodies of information. Maintaining amore » comprehensive working knowledge of the facilities comprising even a single state’s nuclear program poses a challenge, yet marrying this information with relevant safeguards and verification information is more challenging still. To facilitate this task, Brookhaven National Laboratory has developed a means of capturing the development, operation, and safeguards history of all the facilities comprising a state’s nuclear program in a single graphic. The resulting visualization offers a useful reference tool to policymakers and analysts alike, providing a chronology of states’ nuclear development and an easily digestible history of verification activities across their fuel cycles.« less

  12. Methodology for characterizing potential adversaries of Nuclear Material Safeguards Systems

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kirkwood, C.W.; Pollock, S.M.

    1978-11-01

    The results are described of a study by Woodward--Clyde Consultants to assist the University of California Lawrence Livermore Laboratory in the development of methods to analyze and evaluate Nuclear Material Safeguards (NMS) Systems. The study concentrated on developing a methodology to assist experts in describing, in quantitative form, their judgments about the characteristics of potential adversaries of NMS Systems.

  13. Implementation of Microcalorimeter Array Technology for Safeguards of Nuclear Material

    NASA Astrophysics Data System (ADS)

    Kossmann, Shannon; Mateju, Klara; Koehler, Katrina; Croce, Mark

    2018-03-01

    Safeguards of nuclear materials depend on both destructive and nondestructive assay (DA and NDA, respectively). Ultra-high-resolution microcalorimeter gamma spectroscopy has the potential to substantially reduce the performance gap between NDA and DA methods in determination of plutonium isotopic composition. This paper details the setup of a cryostat and microwave readout system for microcalorimeter gamma spectroscopy, the functionality of which has been successfully demonstrated.

  14. 10 CFR 75.7 - Notification of IAEA safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Notification of IAEA safeguards. 75.7 Section 75.7 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) SAFEGUARDS ON NUCLEAR MATERIAL-IMPLEMENTATION OF US/IAEA AGREEMENT General Provisions § 75.7 Notification of IAEA safeguards. (a) The licensee must inform the NRC...

  15. 10 CFR 75.7 - Notification of IAEA safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Notification of IAEA safeguards. 75.7 Section 75.7 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) SAFEGUARDS ON NUCLEAR MATERIAL-IMPLEMENTATION OF US/IAEA AGREEMENT General Provisions § 75.7 Notification of IAEA safeguards. (a) The licensee must inform the NRC...

  16. 76 FR 64126 - Advisory Committee on Reactor Safeguards; Procedures for Meetings

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-17

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Procedures for Meetings.... Nuclear Regulatory Commission's (NRC's) Advisory Committee on Reactor Safeguards (ACRS) pursuant to the... specified in the Federal Register Notice, care of the Advisory Committee on Reactor Safeguards, U.S. Nuclear...

  17. 78 FR 67205 - Advisory Committee on Reactor Safeguards; Procedures for Meetings

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-08

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Procedures for Meetings.... Nuclear Regulatory Commission's (NRC's) Advisory Committee on Reactor Safeguards (ACRS) pursuant to the... specified in the Federal Register Notice, care of the Advisory Committee on Reactor Safeguards, U.S. Nuclear...

  18. Global Survey of the Concepts and Understanding of the Interfaces Between Nuclear Safety, Security, and Safeguards

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kovacic, Don N.; Stewart, Scott; Erickson, Alexa R.

    There is increasing global discourse on how the elements of nuclear safety, security, and safeguards can be most effectively implemented in nuclear power programs. While each element is separate and unique, they must nevertheless all be addressed in a country’s laws and implemented via regulations and in facility operations. This topic is of particular interest to countries that are currently developing the infrastructure to support nuclear power programs. These countries want to better understand what is required by these elements and how they can manage the interfaces between them and take advantages of any synergies that may exist. They needmore » practical examples and guidance in this area in order to develop better organizational strategies and technical capacities. This could simplify their legal, regulatory, and management structures and avoid inefficient approaches and costly mistakes that may not be apparent to them at this early stage of development. From the perspective of IAEA International Safeguards, supporting Member States in exploring such interfaces and synergies provides a benefit to them because it acknowledges that domestic safeguards in a country do not exist in a vacuum. Instead, it relies on a strong State System of Accounting and Control that is in turn dependent on a capable and independent regulatory body as well as a competent operator and technical staff. These organizations must account for and control nuclear material, communicate effectively, and manage and transmit complete and correct information to the IAEA in a timely manner. This, while in most cases also being responsible for the safety and security of their facilities. Seeking efficiencies in this process benefits international safeguards and nonproliferation. This paper will present the results of a global survey of current and anticipated approaches and practices by countries and organizations with current or future nuclear power programs on how they are implementing

  19. DOE/DHS INDUSTRIAL CONTROL SYSTEM CYBER SECURITY PROGRAMS: A MODEL FOR USE IN NUCLEAR FACILITY SAFEGUARDS AND SECURITY

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Robert S. Anderson; Mark Schanfein; Trond Bjornard

    2011-07-01

    Many critical infrastructure sectors have been investigating cyber security issues for several years especially with the help of two primary government programs. The U.S. Department of Energy (DOE) National SCADA Test Bed and the U.S. Department of Homeland Security (DHS) Control Systems Security Program have both implemented activities aimed at securing the industrial control systems that operate the North American electric grid along with several other critical infrastructure sectors (ICS). These programs have spent the last seven years working with industry including asset owners, educational institutions, standards and regulating bodies, and control system vendors. The programs common mission is tomore » provide outreach, identification of cyber vulnerabilities to ICS and mitigation strategies to enhance security postures. The success of these programs indicates that a similar approach can be successfully translated into other sectors including nuclear operations, safeguards, and security. The industry regulating bodies have included cyber security requirements and in some cases, have incorporated sets of standards with penalties for non-compliance such as the North American Electric Reliability Corporation Critical Infrastructure Protection standards. These DOE and DHS programs that address security improvements by both suppliers and end users provide an excellent model for nuclear facility personnel concerned with safeguards and security cyber vulnerabilities and countermeasures. It is not a stretch to imagine complete surreptitious collapse of protection against the removal of nuclear material or even initiation of a criticality event as witnessed at Three Mile Island or Chernobyl in a nuclear ICS inadequately protected against the cyber threat.« less

  20. University of Texas Safeguards by Design Problem Statement

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rauch, Eric Benton; Scherer, Carolynn P.; Ruggiero, Christy E.

    This document describes the problem statement that students at the University of Texas will use for their senior level capstone design class. The purpose of this project is to introduce students to Safeguards by Design concepts as part of their capstone design course at the culmination of their degree program. This work is supported by Los Alamos National Laboratory with FY17 and FY18 programmatic funding from the U. S. Department of Energy’s (DOE) National Nuclear Security Administration (NNSA), through the Office of Defense Nuclear Nonproliferation (DNN), Office of International Nuclear Safeguards (INS), Next Generation Safeguards Initiative (NGSI), Human Resource Developmentmore » Program, Safeguards by Design Project.« less

  1. The evolution of information-driven safeguards

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Budlong-sylvester, Kory W; Pilat, Joseph F

    2010-10-14

    From the adoption of the Model Additional Protocol and integrated safeguards in the 1990s, to current International Atomic Energy Agency (IAEA) efforts to deal with cases of noncompliance, the question of how the Agency can best utilize all the information available to it remains of great interest and increasing importance. How might the concept of 'information-driven' safeguards (IDS) evolve in the future? The ability of the Agency to identify and resolve anomalies has always been important and has emerged as a core Agency function in recent years as the IAEA has had to deal with noncompliance in Iran and themore » Democratic People's Republic of Korea (DPRK). Future IAEA safeguards implementation should be designed with the goal of facilitating and enhancing this vital capability. In addition, the Agency should utilize all the information it possesses, including its in-house assessments and expertise, to direct its safeguards activities. At the State level, knowledge of proliferation possibilities is currently being used to guide the analytical activities of the Agency and to develop inspection plans. How far can this approach be extended? Does it apply across State boundaries? Should it dictate a larger fraction of safeguards activities? Future developments in IDS should utilize the knowledge resident within the Agency to ensure that safeguards resources flow to where they are most needed in order to address anomalies first and foremost, but also to provide greater confidence in conclusions regarding the absence of undeclared nuclear activities. The elements of such a system and related implementation issues are assessed in this paper.« less

  2. Hybrid statistical testing for nuclear material accounting data and/or process monitoring data in nuclear safeguards

    DOE PAGES

    Burr, Tom; Hamada, Michael S.; Ticknor, Larry; ...

    2015-01-01

    The aim of nuclear safeguards is to ensure that special nuclear material is used for peaceful purposes. Historically, nuclear material accounting (NMA) has provided the quantitative basis for monitoring for nuclear material loss or diversion, and process monitoring (PM) data is collected by the operator to monitor the process. PM data typically support NMA in various ways, often by providing a basis to estimate some of the in-process nuclear material inventory. We develop options for combining PM residuals and NMA residuals (residual = measurement - prediction), using a hybrid of period-driven and data-driven hypothesis testing. The modified statistical tests canmore » be used on time series of NMA residuals (the NMA residual is the familiar material balance), or on a combination of PM and NMA residuals. The PM residuals can be generated on a fixed time schedule or as events occur.« less

  3. Exploring Operational Safeguards, Safety, and Security by Design to Address Real Time Threats in Nuclear Facilities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Schanfein, Mark J.; Mladineo, Stephen V.

    2015-07-07

    Over the last few years, significant attention has been paid to both encourage application and provide domestic and international guidance for designing in safeguards and security in new facilities.1,2,3 However, once a facility is operational, safeguards, security, and safety often operate as separate entities that support facility operations. This separation is potentially a serious weakness should insider or outsider threats become a reality.Situations may arise where safeguards detects a possible loss of material in a facility. Will they notify security so they can, for example, check perimeter doors for tampering? Not doing so might give the advantage to an insidermore » who has already, or is about to, move nuclear material outside the facility building. If outsiders break into a facility, the availability of any information to coordinate the facility’s response through segregated alarm stations or a failure to include all available radiation sensors, such as safety’s criticality monitors can give the advantage to the adversary who might know to disable camera systems, but would most likely be unaware of other highly relevant sensors in a nuclear facility.This paper will briefly explore operational safeguards, safety, and security by design (3S) at a high level for domestic and State facilities, identify possible weaknesses, and propose future administrative and technical methods, to strengthen the facility system’s response to threats.« less

  4. National and International Security Applications of Cryogenic Detectors—Mostly Nuclear Safeguards

    NASA Astrophysics Data System (ADS)

    Rabin, Michael W.

    2009-12-01

    As with science, so with security—in both arenas, the extraordinary sensitivity of cryogenic sensors enables high-confidence detection and high-precision measurement even of the faintest signals. Science applications are more mature, but several national and international security applications have been identified where cryogenic detectors have high potential payoff. International safeguards and nuclear forensics are areas needing new technology and methods to boost speed, sensitivity, precision and accuracy. Successfully applied, improved nuclear materials analysis will help constrain nuclear materials diversion pathways and contribute to treaty verification. Cryogenic microcalorimeter detectors for X-ray, gamma-ray, neutron, and alpha-particle spectrometry are under development with these aims in mind. In each case the unsurpassed energy resolution of microcalorimeters reveals previously invisible spectral features of nuclear materials. Preliminary results of quantitative analysis indicate substantial improvements are still possible, but significant work will be required to fully understand the ultimate performance limits.

  5. Evolution of Safeguards over Time: Past, Present, and Projected Facilities, Material, and Budget

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kollar, Lenka; Mathews, Caroline E.

    This study examines the past trends and evolution of safeguards over time and projects growth through 2030. The report documents the amount of nuclear material and facilities under safeguards from 1970 until present, along with the corresponding budget. Estimates for the future amount of facilities and material under safeguards are made according to non-nuclear-weapons states’ (NNWS) plans to build more nuclear capacity and sustain current nuclear infrastructure. Since nuclear energy is seen as a clean and economic option for base load electric power, many countries are seeking to either expand their current nuclear infrastructure, or introduce nuclear power. In ordermore » to feed new nuclear power plants and sustain existing ones, more nuclear facilities will need to be built, and thus more nuclear material will be introduced into the safeguards system. The projections in this study conclude that a zero real growth scenario for the IAEA safeguards budget will result in large resource gaps in the near future.« less

  6. Documentation and Analysis of IAEA (International Atomic Energy Agency) Safeguards Implementation at the Exxon Nuclear Fuel Fabrication Plant.

    DTIC Science & Technology

    1984-10-01

    SAFEGUARDS AT SIMILAR FACILTTIES ASEA -ATOM LEU FUEL FABRICATION PLANT IN VASTERAS, SWEDEN..................B-1 APPENDIX C - EFFECTS OF NONMEASUREMENT ERRORS...second visit was to the ASEA -ATOM’s fuel fabrication plant in Vasteras, Sweden. The safeguards specialists for those plants were interviewed by R...Facilities, ASEA -ATOM LEU Fuel Fabrication Plant in Vasteras, Sweden, by V. Andersson of ASEA -ATOM, Vasteras, Sweden and R. Nilson of Exxon Nuclear

  7. Strengthening IAEA Safeguards for Research Reactors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Reid, Bruce D.; Anzelon, George A.; Budlong-Sylvester, Kory

    During their December 10-11, 2013, workshop in Grenoble France, which focused on the history and future of safeguarding research reactors, the United States, France and the United Kingdom (UK) agreed to conduct a joint study exploring ways to strengthen the IAEA’s safeguards approach for declared research reactors. This decision was prompted by concerns about: 1) historical cases of non-compliance involving misuse (including the use of non-nuclear materials for production of neutron generators for weapons) and diversion that were discovered, in many cases, long after the violations took place and as part of broader pattern of undeclared activities in half amore » dozen countries; 2) the fact that, under the Safeguards Criteria, the IAEA inspects some reactors (e.g., those with power levels under 25 MWt) less than once per year; 3) the long-standing precedent of States using heavy water research reactors (HWRR) to produce plutonium for weapons programs; 4) the use of HEU fuel in some research reactors; and 5) various technical characteristics common to some types of research reactors that could provide an opportunity for potential proliferators to misuse the facility or divert material with low probability of detection by the IAEA. In some research reactors it is difficult to detect diversion or undeclared irradiation. In addition, infrastructure associated with research reactors could pose a safeguards challenge. To strengthen the effectiveness of safeguards at the State level, this paper advocates that the IAEA consider ways to focus additional attention and broaden its safeguards toolbox for research reactors. This increase in focus on the research reactors could begin with the recognition that the research reactor (of any size) could be a common path element on a large number of technically plausible pathways that must be considered when performing acquisition pathway analysis (APA) for developing a State Level Approach (SLA) and Annual Implementation Plan

  8. Comprehensive Nuclear-Test-Ban Treaty: Updated ’Safeguards’ and Net Assessments

    DTIC Science & Technology

    2009-06-03

    measures that this nation can take unilaterally within the treaty to protect its nuclear security. To compensate for “disadvantages and risk” they...and strategic forces, and could be augmented with implementation measures . While Safeguards may be part of a future CTBT debate, both supporters and...A second path involves efforts to alter the net assessment through measures intended to mitigate perceived risks of the treaty. This path has been

  9. International Safeguards and the Pacific Northwest National Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Olsen, Khris B.; Smith, Leon E.; Frazar, Sarah L.

    Established in 1965, Pacific Northwest National Laboratory’s (PNNL) strong technical ties and shared heritage with the nearby U.S. Department of Energy Hanford Site were central to the early development of expertise in nuclear fuel cycle signatures, separations chemistry, plutonium chemistry, environmental monitoring, modeling and analysis of reactor systems, and nuclear material safeguards and security. From these Hanford origins, PNNL has grown into a multi-program science and engineering enterprise that utilizes this diversity to strengthen the international safeguards regime. Today, PNNL supports the International Atomic Energy Agency (IAEA) in its mission to provide assurances to the international community that nations domore » not use nuclear materials and equipment outside of peaceful uses. PNNL also serves in the IAEA’s Network of Analytical Laboratories (NWAL) by providing analysis of environmental samples gathered around the world. PNNL is involved in safeguards research and development activities in support of many U.S. Government programs such as the National Nuclear Security Administration’s (NNSA) Office of Research and Development, NNSA Office of Nonproliferation and Arms Control, and the U.S. Support Program to IAEA Safeguards. In addition to these programs, PNNL invests internal resources including safeguards-specific training opportunities for staff, and laboratory-directed research and development funding to further ideas that may grow into new capabilities. This paper and accompanying presentation highlight some of PNNL’s contributions in technology development, implementation concepts and approaches, policy, capacity building, and human capital development, in the field of international safeguards.« less

  10. Potential application of LIBS to NNSA next generation safeguards initiative (NGSI)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Barefield Ii, James E; Clegg, Samuel M; Veirs, Douglas K

    2009-01-01

    In a climate in which states and nations have been and perhaps currently are involved in the prol iferation of nuclear materials and technologies, advanced methodologies and improvements in current measurement techniques are needed to combat new threats and increased levels of sophistication. The Department of Energy through the National Nuclear Security Administration (NNSA) has undertaken a broad review of International Safeguards. The conclusion from that review was that a comprehensive initiative to revitalize international safeguards technology and the human resource base was urgently needed to keep pace with demands and increasingly sophisticated emerging safeguards challenges. To address these challenges,more » NNSA launched the Next Generation Safeguards Initiative (NGSI) to develop policies, concepts, technologies, expertise, and infrastructure necessary to sustain the international safeguards system as its mission evolves for the next 25 years. NGSI is designed to revitalize and strengthen the U.S. safeguards technical base, recognizing that without a robust program the United States of America will not be in a position to exercise leadership or provide the necessary support to the IAEA (International Atomic Energy Agency). International safeguards as administrated by the IAEA are the primary vehicle for verifying compliance with the peaceful use and nonproliferation of nuclear materials and technologies. Laser Induced Breakdown Spectroscopy or LIBS has the potential to support the goals of NGSI as follows: by providing (1) automated analysis in complex nuclear processing or reprocessing facilities in real-time or near real-time without sample preparation or removal, (2) isotopic and important elemental ratio (Cm/Pu, Cm/U, ... etc) analysis, and (3) centralized remote control, process monitoring, and analysis of nuclear materials in nuclear facilities at multiple locations within the facility. Potential application of LIBS to international safeguards as

  11. Safeguards-by-Design: Guidance for Independent Spent Fuel Dry Storage Installations (ISFSI)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Trond Bjornard; Philip C. Durst

    2012-05-01

    This document summarizes the requirements and best practices for implementing international nuclear safeguards at independent spent fuel storage installations (ISFSIs), also known as Away-from- Reactor (AFR) storage facilities. These installations may provide wet or dry storage of spent fuel, although the safeguards guidance herein focuses on dry storage facilities. In principle, the safeguards guidance applies to both wet and dry storage. The reason for focusing on dry independent spent fuel storage installations is that this is one of the fastest growing nuclear installations worldwide. Independent spent fuel storage installations are typically outside of the safeguards nuclear material balance area (MBA)more » of the reactor. They may be located on the reactor site, but are generally considered by the International Atomic Energy Agency (IAEA) and the State Regulator/SSAC to be a separate facility. The need for this guidance is becoming increasingly urgent as more and more nuclear power plants move their spent fuel from resident spent fuel ponds to independent spent fuel storage installations. The safeguards requirements and best practices described herein are also relevant to the design and construction of regional independent spent fuel storage installations that nuclear power plant operators are starting to consider in the absence of a national long-term geological spent fuel repository. The following document has been prepared in support of two of the three foundational pillars for implementing Safeguards-by-Design (SBD). These are: i) defining the relevant safeguards requirements, and ii) defining the best practices for meeting the requirements. This document was prepared with the design of the latest independent dry spent fuel storage installations in mind and was prepared specifically as an aid for designers of commercial nuclear facilities to help them understand the relevant international requirements that follow from a country’s safeguards agreement

  12. Reactor safeguards system assessment and design. Volume I

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Varnado, G.B.; Ericson, D.M. Jr.; Daniel, S.L.

    1978-06-01

    This report describes the development and application of a methodology for evaluating the effectiveness of nuclear power reactor safeguards systems. Analytic techniques are used to identify the sabotage acts which could lead to release of radioactive material from a nuclear power plant, to determine the areas of a plant which must be protected to assure that significant release does not occur, to model the physical plant layout, and to evaluate the effectiveness of various safeguards systems. The methodology was used to identify those aspects of reactor safeguards systems which have the greatest effect on overall system performance and which, therefore,more » should be emphasized in the licensing process. With further refinements, the methodology can be used by the licensing reviewer to aid in assessing proposed or existing safeguards systems.« less

  13. THE NEXT GENERATION SAFEGUARDS PROFESSIONAL NETWORK: PROGRESS AND NEXT STEPS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Zhernosek, Alena V; Lynch, Patrick D; Scholz, Melissa A

    2011-01-01

    President Obama has repeatedly stated that the United States must ensure that the international safeguards regime, as embodied by the International Atomic Energy Agency (IAEA), has 'the authority, information, people, and technology it needs to do its job.' The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA) works to implement the President's vision through the Next Generation Safeguards Initiative (NGSI), a program to revitalize the U.S. DOE national laboratories safeguards technology and human capital base so that the United States can more effectively support the IAEA and ensure that it meets current and emerging challenges to the internationalmore » safeguards system. In 2009, in response to the human capital development goals of NGSI, young safeguards professionals within the Global Nuclear Security Technology Division at Oak Ridge National Laboratory launched the Next Generation Safeguards Professional Network (NGSPN). The purpose of this initiative is to establish working relationships and to foster collaboration and communication among the next generation of safeguards leaders. The NGSPN is an organization for, and of, young professionals pursuing careers in nuclear safeguards and nonproliferation - as well as mid-career professionals new to the field - whether working within the U.S. DOE national laboratory complex, U.S. government agencies, academia, or industry or at the IAEA. The NGSPN is actively supported by the NNSA, boasts more than 70 members, maintains a website and newsletter, and has held two national meetings as well as an NGSPN session and panel at the July 2010 Institute of Nuclear Material Management Annual Meeting. This paper discusses the network; its significance, goals and objectives; developments and progress to date; and future plans.« less

  14. Oak Ridge National Laboratory Office of International Nuclear Safeguards: Human Capital Development Activity in FY16

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gilligan, Kimberly V.; Gaudet, Rachel N.

    In 2007, the U.S. Department of Energy National Nuclear Security Administration (DOE NNSA) Office of Nonproliferation and Arms Control (NPAC) completed a comprehensive review of the current and potential future challenges facing the international safeguards system. One of the report’s key recommendations was for DOE NNSA to launch a major new program to revitalize the international safeguards technology and human resource base. In 2007, at the International Atomic Energy Agency (IAEA) General Conference, then Secretary of Energy Samuel W. Bodman announced the newly created Next Generation Safeguards Initiative (NGSI). NGSI consists of five program elements: policy development and outreach, conceptsmore » and approaches, technology and analytical methodologies, human capital development (HCD), and infrastructure development. This report addresses the HCD component of NGSI. The goal of the HCD component as defined in the NNSA Program Plan is “to revitalize and expand the international safeguards human capital base by attracting and training a new generation of talent.” The major objectives listed in the HCD goal include education and training, outreach to universities and professional societies, postdoctoral appointments, and summer internships at national laboratories.« less

  15. 77 FR 45700 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-01

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on August... Fukushima Near Term Task Force (NTTF) Recommendation 1: Enhanced Regulatory Framework. The Subcommittee will...

  16. International Internships in Nuclear Safeguards and Security: Challenges and Successes

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Duncan, Cristen L.; Heinberg, Cynthia L.; Killinger, Mark H.

    2010-04-20

    All students in the Russian safeguards and security degree programs at the National Research Nuclear University MEPhI and Tomsk Polytechnic University, sponsored by the Material Protection, Control and Accounting (MPC&A) Education Project, take part in a domestic internship at a Russian enterprise or facility. In addition, a select few students are placed in an international internship. These internships provide students with a better view of how MPC&A and nonproliferation in general are addressed outside of Russia. The possibility of an international internship is a significant incentive for students to enroll in the safeguards and security degree programs. The U.S. membersmore » of the MPC&A Education Project team interview students who have been nominated by their professors. These students must have initiative and reasonable English skills. The project team and professors then select students to be tentatively placed in various international internships during the summer or fall of their final year of study. Final arrangements are then made with the host organizations. This paper describes the benefits of the joint United States/Russia cooperation for next-generation workforce development, some of the international internships that have been carried out, the benefits of these international internships, and lessons learned in implementing them.« less

  17. Safeguards-by-Design:Guidance for High Temperature Gas Reactors (HTGRs) With Prismatic Fuel

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mark Schanfein; Casey Durst

    2012-11-01

    Introduction and Purpose The following is a guidance document from a series prepared for the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), under the Next Generation Safeguards Initiative (NGSI), to assist facility designers and operators in implementing international Safeguards-by-Design (SBD). SBD has two main objectives: (1) to avoid costly and time consuming redesign work or retrofits of new nuclear fuel cycle facilities and (2) to make the implementation of international safeguards more effective and efficient at such facilities. In the long term, the attainment of these goals would save industry and the International Atomic Energy Agency (IAEA)more » time, money, and resources and be mutually beneficial. This particular safeguards guidance document focuses on prismatic fuel high temperature gas reactors (HTGR). The purpose of the IAEA safeguards system is to provide credible assurance to the international community that nuclear material and other specified items are not diverted from peaceful nuclear uses. The safeguards system consists of the IAEA’s statutory authority to establish safeguards; safeguards rights and obligations in safeguards agreements and additional protocols; and technical measures implemented pursuant to those agreements. Of foremost importance is the international safeguards agreement between the country and the IAEA, concluded pursuant to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). According to a 1992 IAEA Board of Governors decision, countries must: notify the IAEA of a decision to construct a new nuclear facility as soon as such decision is taken; provide design information on such facilities as the designs develop; and provide detailed design information based on construction plans at least 180 days prior to the start of construction, and on "as-built" designs at least 180 days before the first receipt of nuclear material. Ultimately, the design information will be captured in an

  18. 76 FR 79229 - Advisory Committee on Reactor Safeguards; Notice of Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-21

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Notice of Meeting In... Advisory Committee on Reactor Safeguards (ACRS) will hold a meeting on January 19-20, 2012, 11545 Rockville... Cooling Systems for Light- Water Nuclear Power Reactors'' (Open)--The Committee will hear presentations by...

  19. Long-term proliferation and safeguards issues in future technologies

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Keisch, B.; Auerbach, C.; Fainberg, A.

    1986-02-01

    The purpose of the task was to assess the effect of potential new technologies, nuclear and non-nuclear, on safeguards needs and non-proliferation policies, and to explore possible solutions to some of the problems envisaged. Eight subdivisions were considered: New Enrichment Technologies; Non-Aqueous Reprocessing Technologies; Fusion; Accelerator-Driven Reactor Systems; New Reactor Types; Heavy Water and Deuterium; Long-Term Storage of Spent Fuel; and Other Future Technologies (Non-Nuclear). For each of these subdivisions, a careful review of the current world-wide effort in the field provided a means of subjectively estimating the viability and qualitative probability of fruition of promising technologies. Technologies for whichmore » safeguards and non-proliferation requirements have been thoroughly considered by others were not restudied here (e.g., the Fast Breeder Reactor). The time scale considered was 5 to 40 years for possible initial demonstration although, in some cases, a somewhat optimistic viewpoint was embraced. Conventional nuclear-material safeguards are only part of the overall non-proliferation regime. Other aspects are international agreements, export controls on sensitive technologies, classification of information, intelligence gathering, and diplomatic initiatives. The focus here is on safeguards, export controls, and classification.« less

  20. Development of Metallic Magnetic Calorimeters for Nuclear Safeguards Applications

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bates, Cameron Russell

    2015-03-11

    Many nuclear safeguards applications could benefit from high-resolution gamma-ray spectroscopy achievable with metallic magnetic calorimeters. This dissertation covers the development of a system for these applications based on gamma-ray detectors developed at the University of Heidelberg. It demonstrates new calorimeters of this type, which achieved an energy resolution of 45.5 eV full-width at half-maximum at 59.54 keV, roughly ten times better than current state of the art high purity germanium detectors. This is the best energy resolution achieved with a gamma-ray metallic magnetic calorimeter at this energy to date. In addition to demonstrating a new benchmark in energy resolution, anmore » experimental system for measuring samples with metallic magnetic calorimeters was constructed at Lawrence Livermore National Laboratory. This system achieved an energy resolution of 91.3 eV full-width at half-maximum at 59.54 keV under optimal conditions. Using this system it was possible to characterize the linearity of the response, the count-rate limitations, and the energy resolution as a function of temperature of the new calorimeter. With this characterization it was determined that it would be feasible to measure 242Pu in a mixed isotope plutonium sample. A measurement of a mixed isotope plutonium sample was performed over the course of 12 days with a single two-pixel metallic magnetic calorimeter. The relative concentration of 242Pu in comparison to other plutonium isotopes was determined by direct measurement to less than half a percent accuracy. This is comparable with the accuracy of the best-case scenario using traditional indirect methods. The ability to directly measure the relative concentration of 242Pu in a sample could enable more accurate accounting and detection of indications of undeclared activities in nuclear safeguards, a better constraint on source material in forensic samples containing plutonium, and improvements in verification in a future

  1. SARS: Safeguards Accounting and Reporting Software

    NASA Astrophysics Data System (ADS)

    Mohammedi, B.; Saadi, S.; Ait-Mohamed, S.

    In order to satisfy the requirements of the SSAC (State System for Accounting and Control of nuclear materials), for recording and reporting objectives; this computer program comes to bridge the gape between nuclear facilities operators and national inspection verifying records and delivering reports. The SARS maintains and generates at-facility safeguards accounting records and generates International Atomic Energy Agency (IAEA) safeguards reports based on accounting data input by the user at any nuclear facility. A database structure is built and BORLAND DELPHI programming language has been used. The software is designed to be user-friendly, to make extensive and flexible management of menus and graphs. SARS functions include basic physical inventory tacking, transaction histories and reporting. Access controls are made by different passwords.

  2. 75 FR 21046 - Advisory Committee on Reactor Safeguards

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-22

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards In accordance with the... on Reactor Safeguards (ACRS) will hold a meeting on May 6-8, 2010, 11545 Rockville Pike, Rockville....: Boiling Water Reactor (BWR) Owners Group (BWROG) Topical Report NEDC-33347P, ``Containment Overpressure...

  3. A 3S Risk ?3SR? Assessment Approach for Nuclear Power: Safety Security and Safeguards.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Forrest, Robert; Reinhardt, Jason Christian; Wheeler, Timothy A.

    Safety-focused risk analysis and assessment approaches struggle to adequately include malicious, deliberate acts against the nuclear power industry's fissile and waste material, infrastructure, and facilities. Further, existing methods do not adequately address non- proliferation issues. Treating safety, security, and safeguards concerns independently is inefficient because, at best, it may not take explicit advantage of measures that provide benefits against multiple risk domains, and, at worst, it may lead to implementations that increase overall risk due to incompatibilities. What is needed is an integrated safety, security and safeguards risk (or "3SR") framework for describing and assessing nuclear power risks that canmore » enable direct trade-offs and interactions in order to inform risk management processes -- a potential paradigm shift in risk analysis and management. These proceedings of the Sandia ePRA Workshop (held August 22-23, 2017) are an attempt to begin the discussions and deliberations to extend and augment safety focused risk assessment approaches to include security concerns and begin moving towards a 3S Risk approach. Safeguards concerns were not included in this initial workshop and are left to future efforts. This workshop focused on four themes in order to begin building out a the safety and security portions of the 3S Risk toolkit: 1. Historical Approaches and Tools 2. Current Challenges 3. Modern Approaches 4. Paths Forward and Next Steps This report is organized along the four areas described above, and concludes with a summary of key points. 2 Contact: rforres@sandia.gov; +1 (925) 294-2728« less

  4. Assessing the effectiveness of safeguards at a medium-sized spent-fuel reprocessing facility

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Higinbotham, W.; Fishbone, L.G.; Suda, S.

    1983-01-01

    In order to evaluate carefully and systematically the effectiveness of safeguards at nuclear-fuel-cycle facilities, the International Atomic Energy Agency has adopted a safeguards effectiveness assessment methodology. The methodology has been applied to a well-characterized, medium-sized, spent-fuel reprocessing plant to understand how explicit safeguards inspection procedures would serve to expose conceivable nuclear materials diversion schemes, should such diversion occur.

  5. 75 FR 8154 - Advisory Committee on Reactor Safeguards

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-23

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards In accordance with the... on Reactor Safeguards (ACRS) will hold a meeting on March 4-6, 2010, 11545 Rockville Pike, Rockville....-12 p.m.: New Advanced Reactor Designs (Open)--The Committee will hear presentations by and hold...

  6. Incorporating delayed neutrons into the point-model equations routinely used for neutron coincidence counting in nuclear safeguards

    DOE PAGES

    Croft, Stephen; Favalli, Andrea

    2016-09-21

    Here, we extend the familiar Bӧhnel point-model equations, which are routinely used to interpret neutron coincidence counting rates, by including the contribution of delayed neutrons. After developing the necessary equations we use them to show, by providing some numerical results, what the quantitative impact of neglecting delayed neutrons is across the full range of practical nuclear safeguards applications. The influence of delayed neutrons is predicted to be small for the types of deeply sub-critical assay problems which concern the nuclear safeguards community, smaller than uncertainties arising from other factors. This is most clearly demonstrated by considering the change in themore » effective (α,n)-to-spontaneous fission prompt-neutron ratio that the inclusion of delayed neutrons gives rise to. That the influence of delayed neutrons is small is fortunate, and our results justify the long standing practice of simply neglecting them in the analysis of field measurements.« less

  7. Regional Cooperation to Strengthen Safeguards

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Minnini, Margot; Elkhamri, Oksana O.

    2016-06-06

    President Obama’s decision over four years ago to ”pivot” toward Asia represented an important strategic shift in American foreign policy and a rebalancing of U.S. economic and security engagement in the Asia-Pacific countries. The United States has since supported a variety of regional initiatives aimed at promoting nuclear security and safeguards. When a new regional organization, the Asia-Pacific Safeguards Network (APSN) was established in 2010, DOE/NNSA became an early member and enthusiastic advocate. Launched on the initiative of Australia, Japan, Republic of Korea, and Indonesia, the APSN aims to strengthen the quality and effectiveness of safeguards implementation in the Asia-Pacificmore » region.« less

  8. FY 2008 Next Generation Safeguards Initiative International Safeguards Education and Training Pilot Progerams Summary Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dreicer, M; Anzelon, G; Essner, J

    2008-10-17

    Key component of the Next Generation Safeguards Initiative (NGSI) launched by the National Nuclear Security Administration is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. Two pilot programs at university level, involving 44 students, were initiated and implemented in spring-summer 2008 and linked to hands-on internships at LANL or LLNL. During the internships, students worked on specific safeguards-related projects with a designated Laboratory Mentor to provide broader exposure tomore » nuclear materials management and information analytical techniques. The Safeguards and Nuclear Material Management pilot program was a collaboration between the Texas A&M University (TAMU), Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). It included a 16-lecture course held during a summer internship program. The instructors for the course were from LANL together with TAMU faculty and LLNL experts. The LANL-based course was shared with the students spending their internship at LLNL via video conference. A week-long table-top (or hands-on) exercise on was also conducted at LANL. The student population was a mix of 28 students from a 12 universities participating in a variety of summer internship programs held at LANL and LLNL. A large portion of the students were TAMU students participating in the NGSI pilot. The International Nuclear Safeguards Policy and Information Analysis pilot program was implemented at the Monterey Institute for International Studies (MIIS) in cooperation with LLNL. It included a two-week intensive course consisting of 20 lectures and two exercises. MIIS, LLNL, and speakers from other U.S. national laboratories (LANL, BNL) delivered lectures for the audience of 16 students. The majority of

  9. Developing a Signature Based Safeguards Approach for the Electrorefiner and Salt Cleanup Unit Operations in Pyroprocessing Facilities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Murphy, Chantell Lynne-Marie

    Traditional nuclear materials accounting does not work well for safeguards when applied to pyroprocessing. Alternate methods such as Signature Based Safeguards (SBS) are being investigated. The goal of SBS is real-time/near-real-time detection of anomalous events in the pyroprocessing facility as they could indicate loss of special nuclear material. In high-throughput reprocessing facilities, metric tons of separated material are processed that must be accounted for. Even with very low uncertainties of accountancy measurements (<0.1%) the uncertainty of the material balances is still greater than the desired level. Novel contributions of this work are as follows: (1) significant enhancement of SBS developmentmore » for the salt cleanup process by creating a new gas sparging process model, selecting sensors to monitor normal operation, identifying safeguards-significant off-normal scenarios, and simulating those off-normal events and generating sensor output; (2) further enhancement of SBS development for the electrorefiner by simulating off-normal events caused by changes in salt concentration and identifying which conditions lead to Pu and Cm not tracking throughout the rest of the system; and (3) new contribution in applying statistical techniques to analyze the signatures gained from these two models to help draw real-time conclusions on anomalous events.« less

  10. Field trial of the enhanced data authentication system (EDAS)

    DOE PAGES

    Thomas, Maikael A.; Hymel, Ross W.; Baldwin, George; ...

    2016-11-01

    The Enhanced Data Authentication System (EDAS) is means to securely branch information from an existing measurement system or data stream to a secondary observer. In an international nuclear safeguards context, the EDAS connects to operator instrumentation, and provides a cryptographically secure copy of the information for a safeguards inspectorate. However, this novel capability could be a valuable complement to inspector-owned safeguards instrumentation, offering context that is valuable for anomaly resolution and contingency.

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kryuchkov, Eduard F.; Geraskin, Nikolay I.; Killinger, Mark H.

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

  12. International Atomic Energy Agency Safeguards: Challenge and response

    NASA Astrophysics Data System (ADS)

    Spector, Leonard S.

    2017-11-01

    This article provides a critical review of the nuclear accounting and inspection system of the International Atomic Energy Agency (IAEA), known as "IAEA safeguards." The article focuses on the multiple challenges the Agency confronts in verifying that all nuclear activities in the countries under its safeguards system are being pursued for exclusively peaceful purposes. The principal challenges noted are those posed by: undeclared facilities, the development of enrichment and reprocessing capabilities, illicit procurement activities, denial of inspector access, difficulties in verifying absence of weaponization activities, and difficulties in establishing that all nuclear-relevant activities in a state are peaceful. The article is in the form of annotated PowerPoint briefing slides.

  13. 75 FR 3501 - Advisory Committee on Reactor Safeguards

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-21

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards In accordance with the purposes of Sections 29 and 182b of the Atomic Energy Act (42 U.S.C. 2039, 2232b), the Advisory Committee on Reactor Safeguards (ACRS) will hold a meeting on February 4-6, 2010, 11545 Rockville Pike...

  14. Implementation of IT-based applications in the safeguards field

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ekenstam, G.C. af; Sallstrom, M.

    1995-12-31

    For many years the Swedish Nuclear Power Inspectorate, SKI, has used computers as a tool within nuclear material control and accountancy. Over the last five years a lot of effort has been put into projects related to the increasing possibilities of fast and reliable data transfer over large distances. The paper discusses related administrative and technical issues and presents experience gained in tasks of the Swedish Support Program to IAEA Safeguards and during the alternative Safeguards trials carried out by SKI. The following topics will be presented: (1) Main Safeguards purposes and data transfer; (2) Administrative systems and requirements; (3)more » Technical possibilities and experiences; and (4) The cost aspect.« less

  15. Pebble bed modular reactor safeguards: developing new approaches and implementing safeguards by design

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Beyer, Brian David; Beddingfield, David H; Durst, Philip

    2010-01-01

    The design of the Pebble Bed Modular Reactor (PBMR) does not fit or seem appropriate to the IAEA safeguards approach under the categories of light water reactor (LWR), on-load refueled reactor (OLR, i.e. CANDU), or Other (prismatic HTGR) because the fuel is in a bulk form, rather than discrete items. Because the nuclear fuel is a collection of nuclear material inserted in tennis-ball sized spheres containing structural and moderating material and a PBMR core will contain a bulk load on the order of 500,000 spheres, it could be classified as a 'Bulk-Fuel Reactor.' Hence, the IAEA should develop unique safeguardsmore » criteria. In a multi-lab DOE study, it was found that an optimized blend of: (i) developing techniques to verify the plutonium content in spent fuel pebbles, (ii) improving burn-up computer codes for PBMR spent fuel to provide better understanding of the core and spent fuel makeup, and (iii) utilizing bulk verification techniques for PBMR spent fuel storage bins should be combined with the historic IAEA and South African approaches of containment and surveillance to verify and maintain continuity of knowledge of PBMR fuel. For all of these techniques to work the design of the reactor will need to accommodate safeguards and material accountancy measures to a far greater extent than has thus far been the case. The implementation of Safeguards-by-Design as the PBMR design progresses provides an approach to meets these safeguards and accountancy needs.« less

  16. 3 CFR - Certifications Pursuant to Section 104 of the United States-India Nuclear Cooperation Approval...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... States-India Nuclear Cooperation Approval and Nonproliferation Enhancement Act Regarding the Safeguards Agreement Between India and the International Atomic Energy Agency Presidential Documents Other Presidential... of the United States-India Nuclear Cooperation Approval and Nonproliferation Enhancement Act...

  17. 3S (Safeguards, Security, Safety) based pyroprocessing facility safety evaluation plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ku, J.H.; Choung, W.M.; You, G.S.

    The big advantage of pyroprocessing for the management of spent fuels against the conventional reprocessing technologies lies in its proliferation resistance since the pure plutonium cannot be separated from the spent fuel. The extracted materials can be directly used as metal fuel in a fast reactor, and pyroprocessing reduces drastically the volume and heat load of the spent fuel. KAERI has implemented the SBD (Safeguards-By-Design) concept in nuclear fuel cycle facilities. The goal of SBD is to integrate international safeguards into the entire facility design process since the very beginning of the design phase. This paper presents a safety evaluationmore » plan using a conceptual design of a reference pyroprocessing facility, in which 3S (Safeguards, Security, Safety)-By-Design (3SBD) concept is integrated from early conceptual design phase. The purpose of this paper is to establish an advanced pyroprocessing hot cell facility design concept based on 3SBD for the successful realization of pyroprocessing technology with enhanced safety and proliferation resistance.« less

  18. 10 CFR 1304.114 - Responsibility for maintaining adequate safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 4 2011-01-01 2011-01-01 false Responsibility for maintaining adequate safeguards. 1304.114 Section 1304.114 Energy NUCLEAR WASTE TECHNICAL REVIEW BOARD PRIVACY ACT OF 1974 § 1304.114 Responsibility for maintaining adequate safeguards. The Board has the responsibility for maintaining adequate...

  19. 10 CFR 1304.114 - Responsibility for maintaining adequate safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 4 2014-01-01 2014-01-01 false Responsibility for maintaining adequate safeguards. 1304.114 Section 1304.114 Energy NUCLEAR WASTE TECHNICAL REVIEW BOARD PRIVACY ACT OF 1974 § 1304.114 Responsibility for maintaining adequate safeguards. The Board has the responsibility for maintaining adequate...

  20. 10 CFR 1304.114 - Responsibility for maintaining adequate safeguards.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 4 2012-01-01 2012-01-01 false Responsibility for maintaining adequate safeguards. 1304.114 Section 1304.114 Energy NUCLEAR WASTE TECHNICAL REVIEW BOARD PRIVACY ACT OF 1974 § 1304.114 Responsibility for maintaining adequate safeguards. The Board has the responsibility for maintaining adequate...

  1. 10 CFR 1304.114 - Responsibility for maintaining adequate safeguards.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 4 2013-01-01 2013-01-01 false Responsibility for maintaining adequate safeguards. 1304.114 Section 1304.114 Energy NUCLEAR WASTE TECHNICAL REVIEW BOARD PRIVACY ACT OF 1974 § 1304.114 Responsibility for maintaining adequate safeguards. The Board has the responsibility for maintaining adequate...

  2. Safeguards Considerations for Thorium Fuel Cycles

    DOE PAGES

    Worrall, Louise G.; Worrall, Andrew; Flanagan, George F.; ...

    2016-04-21

    We report that by around 2025, thorium-based fuel cycles are likely to be deployed internationally. States such as China and India are pursuing research, development, and deployment pathways toward a number of commercial-scale thorium fuel cycles, and they are already building test reactors and the associated fuel cycle infrastructure. In the future, the potential exists for these emerging programs to sell, export, and deploy thorium fuel cycle technology in other states. Without technically adequate international safeguards protocols and measures in place, any future potential clandestine misuse of these fuel cycles could go undetected, compromising the deterrent value of these protocolsmore » and measures. The development of safeguards approaches for thorium-based fuel cycles is therefore a matter of some urgency. Yet, the focus of the international safeguards community remains mainly on safeguarding conventional 235U- and 239Pu-based fuel cycles while the safeguards challenges of thorium-uranium fuel cycles remain largely uninvestigated. This raises the following question: Is the International Atomic Energy Agency and international safeguards system ready for thorium fuel cycles? Furthermore, is the safeguards technology of today sufficiently mature to meet the verification challenges posed by thorium-based fuel cycles? In defining these and other related research questions, the objectives of this paper are to identify key safeguards considerations for thorium-based fuel cycles and to call for an early dialogue between the international safeguards and the nuclear fuel cycle communities to prepare for the potential safeguards challenges associated with these fuel cycles. In this paper, it is concluded that directed research and development programs are required to meet the identified safeguards challenges and to take timely action in preparation for the international deployment of thorium fuel cycles.« less

  3. Russian University Education in Nuclear Safeguards and Security

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Duncan, Cristen L.; Kryuchkov, Eduard F.; Geraskin, Nikolay I.

    2009-03-15

    As safeguards and security (S&S) systems are installed and upgraded in nuclear facilities throughout Russia, it becomes increasingly important to develop mechanisms for educating future Russian nuclear scientists and engineers in the technologies and methodologies of physical protection (PP) and nuclear material control and accounting (MC&A). As part of the U.S. Department of Energy’s (DOE) program to secure nuclear materials in Russia, the Education Project supports technical S&S degree programs at key Russian universities and nonproliferation education initiatives throughout the Russian Federation that are necessary to achieve the overall objective of fostering qualified and vigilant Russian S&S personnel. The Educationmore » Project supports major educational degree programs at the Moscow Engineering Physics Institute (MEPhI) and Tomsk Polytechnic University (TPU). The S&S Graduate Program is available only at MEPhI and is the world’s first S&S degree program. Ten classes of students have graduated with a total of 79 Masters Degrees as of early 2009. At least 84% of the graduates over the ten years are still working in the S&S field. Most work at government agencies or research organizations, and some are pursuing their PhD. A 5½ year Engineering Degree Program (EDP) in S&S is currently under development at MEPhI and TPU. The EDP is more tailored to the needs of nuclear facilities. The program’s first students (14) graduated from MEPhI in February 2007. Similar-sized classes are graduating from MEPhI each February. All of the EDP graduates are working in the S&S field, many at nuclear facilities. TPU also established an EDP and graduated its first class of approximately 18 students in February 2009. For each of these degree programs, the American project team works with MEPhI and TPU to develop appropriate curriculum, identify and acquire various training aids, develop and publish textbooks, and strengthen instructor skills. The project has also

  4. Exploratory study on potential safeguards applications for shared ledger technology

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Frazar, Sarah L.; Jarman, Kenneth D.; Joslyn, Cliff A.

    The International Atomic Energy Agency (IAEA) is responsible for providing credible assurance that countries are meeting their obligations not to divert or misuse nuclear materials and facilities for non-peaceful purposes. To this end, the IAEA integrates information about States’ nuclear material inventories and transactions with other types of data to draw its safeguards conclusions. As the amount and variety of data and information has increased, the IAEA’s data acquisition, management, and analysis processes have greatly benefited from advancements in computer science, data management, and cybersecurity during the last 20 years. Despite these advancements, inconsistent use of advanced computer technologies asmore » well as political concerns among certain IAEA Member States centered on trust, transparency, and IAEA authorities limit the overall effectiveness and efficiency of IAEA safeguards. As a result, there is an ongoing need to strengthen the effectiveness and efficiency of IAEA safeguards while improving Member State cooperation and trust in the safeguards system. These chronic safeguards needs could be met with some emerging technologies, specifically those associated with the digital currency bitcoin.« less

  5. Safeguards and Security by Design (SSBD) for Small Modular Reactors (SMRs) through a Common Global Approach

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Badwan, Faris M.; Demuth, Scott Francis; Miller, Michael Conrad

    Small Modular Reactors (SMR) with power levels significantly less than the currently standard 1000 to 1600-MWe reactors have been proposed as a potential game changer for future nuclear power. SMRs may offer a simpler, more standardized, and safer modular design by using factory built and easily transportable components. Additionally, SMRs may be more easily built and operated in isolated locations, and may require smaller initial capital investment and shorter construction times. Because many SMRs designs are still conceptual and consequently not yet fixed, designers have a unique opportunity to incorporate updated design basis threats, emergency preparedness requirements, and then fullymore » integrate safety, physical security, and safeguards/material control and accounting (MC&A) designs. Integrating safety, physical security, and safeguards is often referred to as integrating the 3Ss, and early consideration of safeguards and security in the design is often referred to as safeguards and security by design (SSBD). This paper describes U.S./Russian collaborative efforts toward developing an internationally accepted common approach for implementing SSBD/3Ss for SMRs based upon domestic requirements, and international guidance and requirements. These collaborative efforts originated with the Nuclear Energy and Nuclear Security working group established under the U.S.-Russia Bilateral Presidential Commission during the 2009 Presidential Summit. Initial efforts have focused on review of U.S. and Russian domestic requirements for Security and MC&A, IAEA guidance for security and MC&A, and IAEA requirements for international safeguards. Additionally, example SMR design features that can enhance proliferation resistance and physical security have been collected from past work and reported here. The development of a U.S./Russian common approach for SSBD/3Ss should aid the designer of SMRs located anywhere in the world. More specifically, the application of this

  6. Safeguards Options for Natural Uranium Conversion Facilities ? A Collaborative Effort between the U.S. Department of Energy (DOE) and the National Nuclear Energy Commission of Brazil (CNEN)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Raffo-Caiado, Ana Claudia; Begovich, John M; Ferrada, Juan J

    2008-01-01

    In 2005, the National Nuclear Energy Commission of Brazil (CNEN) and the U.S. Department of Energy (DOE) agreed on a collaborative effort to evaluate measures that can strengthen the effectiveness of international safeguards at a natural uranium conversion plant (NUCP). The work was performed by DOE's Oak Ridge National Laboratory and CNEN. A generic model of an NUCP was developed and typical processing steps were defined. The study, completed in early 2007, identified potential safeguards measures and evaluated their effectiveness and impacts on operations. In addition, advanced instrumentation and techniques for verification purposes were identified and investigated. The scope ofmore » the work was framed by the International Atomic Energy Agency's (IAEA's) 2003 revised policy concerning the starting point of safeguards at uranium conversion facilities. Before this policy, only the final products of the uranium conversion plant were considered to be of composition and purity suitable for use in the nuclear fuel cycle and, therefore, subject to AEA safeguards control. DOE and CNEN have explored options for implementing the IAEA policy, although Brazil understands that the new policy established by the IAEA is beyond the framework of the Quadripartite Agreement of which it is one of the parties, together with Argentina, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, and the IAEA. This paper highlights the findings of this joint collaborative effort and identifies technical measures to strengthen international safeguards in NUCPs.« less

  7. Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Zhang, Jinsuo

    Pyroprocessing is an electrochemical method based on the molten salt electrolyte, mainly the LiCl-KCl eutectic molten salt, to recycle the used nuclear fuel. For a conceptual design of commercial pyroprocessing facility, tons of special nuclear materials, namely U and Pu, may be involved, which could be used for non-peaceful purposes if they are diverted. Effective safeguards approaches have to be developed prior to the development and construction of a pyroprocessing facility. Present research focused on two main objectives, namely calculating the properties of nuclear species in LiCl-KCl molten salt and developing integrated model to safeguard a pyroprocessing facility. Understanding themore » characteristics of special nuclear materials in LiCl-KCl eutectic salt is extremely important to understand their behaviors in an electrorefiner. The model development for the separation processes in the pyroprocessing, including electrorefining, actinide drawdown, and rare earth drawdown benefits the understanding of material transport and separation performance of these processes under various conditions. The output signals, such as potential, current, and species concentration contribute to the material balance closure and provide safeguards signatures to detect the scenarios of diversion. U and Pu are the two main elements concerned in this study due to our interest in safeguards.« less

  8. Simulation Enabled Safeguards Assessment Methodology

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Robert Bean; Trond Bjornard; Thomas Larson

    2007-09-01

    It is expected that nuclear energy will be a significant component of future supplies. New facilities, operating under a strengthened international nonproliferation regime will be needed. There is good reason to believe virtual engineering applied to the facility design, as well as to the safeguards system design will reduce total project cost and improve efficiency in the design cycle. Simulation Enabled Safeguards Assessment MEthodology (SESAME) has been developed as a software package to provide this capability for nuclear reprocessing facilities. The software architecture is specifically designed for distributed computing, collaborative design efforts, and modular construction to allow step improvements inmore » functionality. Drag and drop wireframe construction allows the user to select the desired components from a component warehouse, render the system for 3D visualization, and, linked to a set of physics libraries and/or computational codes, conduct process evaluations of the system they have designed.« less

  9. Gas centrifuge enrichment plants inspection frequency and remote monitoring issues for advanced safeguards implementation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Boyer, Brian David; Erpenbeck, Heather H; Miller, Karen A

    2010-09-13

    Current safeguards approaches used by the IAEA at gas centrifuge enrichment plants (GCEPs) need enhancement in order to verify declared low enriched uranium (LEU) production, detect undeclared LEU production and detect high enriched uranium (BEU) production with adequate probability using non destructive assay (NDA) techniques. At present inspectors use attended systems, systems needing the presence of an inspector for operation, during inspections to verify the mass and {sup 235}U enrichment of declared cylinders of uranium hexafluoride that are used in the process of enrichment at GCEPs. This paper contains an analysis of how possible improvements in unattended and attended NDAmore » systems including process monitoring and possible on-site destructive analysis (DA) of samples could reduce the uncertainty of the inspector's measurements providing more effective and efficient IAEA GCEPs safeguards. We have also studied a few advanced safeguards systems that could be assembled for unattended operation and the level of performance needed from these systems to provide more effective safeguards. The analysis also considers how short notice random inspections, unannounced inspections (UIs), and the concept of information-driven inspections can affect probability of detection of the diversion of nuclear material when coupled to new GCEPs safeguards regimes augmented with unattended systems. We also explore the effects of system failures and operator tampering on meeting safeguards goals for quantity and timeliness and the measures needed to recover from such failures and anomalies.« less

  10. 77 FR 64563 - Advisory Committee on Reactor Safeguards; Notice of Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-22

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Notice of Meeting In... Advisory Committee on Reactor Safeguards (ACRS) will hold a meeting on November 1-3, 2012, 11545 Rockville...-Term Core Cooling Approach for the Advanced Boiling Water Reactor (ABWR) Design for South Texas Project...

  11. USSP-IAEA WORKSHOP ON ADVANCED SENSORS FOR SAFEGUARDS.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    PEPPER,S.; QUEIROLO, A.; ZENDEL, M.

    2007-11-13

    The IAEA Medium Term Strategy (2006-2011) defines a number of specific goals in respect to the IAEA's ability to provide assurances to the international community regarding the peaceful use of nuclear energy through States adherences to their respective non-proliferation treaty commitments. The IAEA has long used and still needs the best possible sensors to detect and measure nuclear material. The Department of Safeguards, recognizing the importance of safeguards-oriented R&D, especially targeting improved detection capabilities for undeclared facilities, materials and activities, initiated a number of activities in early 2005. The initiatives included letters to Member State Support Programs (MSSPs), personal contactsmore » with known technology holders, topical meetings, consultant reviews of safeguards technology, and special workshops to identify new and novel technologies and methodologies. In support of this objective, the United States Support Program to IAEA Safeguards hosted a workshop on ''Advanced Sensors for Safeguards'' in Santa Fe, New Mexico, from April 23-27, 2007. The Organizational Analysis Corporation, a U.S.-based management consulting firm, organized and facilitated the workshop. The workshop's goal was to help the IAEA identify and plan for new sensors for safeguards implementation. The workshop, which was attended by representatives of seven member states and international organizations, included presentations by technology holders and developers on new technologies thought to have relevance to international safeguards, but not yet in use by the IAEA. The presentations were followed by facilitated breakout sessions where the participants considered two scenarios typical of what IAEA inspectors might face in the field. One scenario focused on an enrichment plant; the other scenario focused on a research reactor. The participants brainstormed using the technologies presented by the participants and other technologies known to them to propose

  12. OR14-V-Uncertainty-PD2La Uncertainty Quantification for Nuclear Safeguards and Nondestructive Assay Final Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nicholson, Andrew D.; Croft, Stephen; McElroy, Robert Dennis

    2017-08-01

    The various methods of nondestructive assay (NDA) of special nuclear material (SNM) have applications in nuclear nonproliferation, including detection and identification of illicit SNM at border crossings and quantifying SNM at nuclear facilities for safeguards. No assay method is complete without “error bars,” which provide one way of expressing confidence in the assay result. Consequently, NDA specialists typically provide error bars and also partition total uncertainty into “random” and “systematic” components so that, for example, an error bar can be developed for the total mass estimate in multiple items. Uncertainty Quantification (UQ) for NDA has always been important, but itmore » is recognized that greater rigor is needed and achievable using modern statistical methods.« less

  13. Improving the Transparency of IAEA Safeguards Reporting

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Toomey, Christopher; Hayman, Aaron M.; Wyse, Evan T.

    2011-07-17

    In 2008, the Standing Advisory Group on Safeguards Implementation (SAGSI) indicated that the International Atomic Energy Agency's (IAEA) Safeguards Implementation Report (SIR) has not kept pace with the evolution of safeguards and provided the IAEA with a set of recommendations for improvement. The SIR is the primary mechanism for providing an overview of safeguards implementation in a given year and reporting on the annual safeguards findings and conclusions drawn by the Secretariat. As the IAEA transitions to State-level safeguards approaches, SIR reporting must adapt to reflect these evolutionary changes. This evolved report will better reflect the IAEA's transition to amore » more qualitative and information-driven approach, based upon State-as-a-whole considerations. This paper applies SAGSI's recommendations to the development of multiple models for an evolved SIR and finds that an SIR repurposed as a 'safeguards portal' could significantly enhance information delivery, clarity, and transparency. In addition, this paper finds that the 'portal concept' also appears to have value as a standardized information presentation and analysis platform for use by Country Officers, for continuity of knowledge purposes, and the IAEA Secretariat in the safeguards conclusion process. Accompanying this paper is a fully functional prototype of the 'portal' concept, built using commercial software and IAEA Annual Report data.« less

  14. 77 FR 69900 - Advisory Committee on Reactor Safeguards; Notice of Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-21

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Notice of Meeting In... Advisory Committee on Reactor Safeguards (ACRS) will hold a meeting on December 6-8, 2012, 11545 Rockville... Recommendations (SECY-12-0064), (3) Venting Systems for Boiling Water Reactors (BWRs) with Mark I and Mark II...

  15. FY2017 Final Report: Power of the People: A technical ethical and experimental examination of the use of crowdsourcing to support international nuclear safeguards verification.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gastelum, Zoe Nellie; Sentz, Kari; Swanson, Meili Claire

    Recent advances in information technology have led to an expansion of crowdsourcing activities that utilize the “power of the people” harnessed via online games, communities of interest, and other platforms to collect, analyze, verify, and provide technological solutions for challenges from a multitude of domains. To related this surge in popularity, the research team developed a taxonomy of crowdsourcing activities as they relate to international nuclear safeguards, evaluated the potential legal and ethical issues surrounding the use of crowdsourcing to support safeguards, and proposed experimental designs to test the capabilities and prospect for the use of crowdsourcing to support nuclearmore » safeguards verification.« less

  16. International Safeguards Technology and Policy Education and Training Pilot Programs

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dreicer, M; Anzelon, G A; Essner, J T

    2009-06-16

    A major focus of the National Nuclear Security Administration-led Next Generation Safeguards Initiative (NGSI) is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. NNSA launched two pilot programs in 2008 to develop university level courses and internships in association with James, Martin Center for Nonproliferation Studies (CNS) at the Monterey Institute of International Studies (MIIS) and Texas A&M University (TAMU). These pilot efforts involved 44 students in total andmore » were closely linked to hands-on internships at Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). The Safeguards and Nuclear Material Management pilot program was a collaboration between TAMU, LANL, and LLNL. The LANL-based coursework was shared with the students undertaking internships at LLNL via video teleconferencing. A weeklong hands-on exercise was also conducted at LANL. A second pilot effort, the International Nuclear Safeguards Policy and Information Analysis pilot program was implemented at MIIS in cooperation with LLNL. Speakers from MIIS, LLNL, and other U.S. national laboratories (LANL, BNL) delivered lectures for the audience of 16 students. The majority of students were senior classmen or new master's degree graduates from MIIS specializing in nonproliferation policy studies. The two pilots programs concluded with an NGSI Summer Student Symposium, held at LLNL, where 20 students participated in LLNL facility tours and poster sessions. The value of bringing together the students from the technical and policy pilots was notable and will factor into the planning for the continued refinement of the two programs in the coming years.« less

  17. Exploring the Application of Shared Ledger Technology to Safeguards and other National Security Topics

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Frazar, Sarah L.; Winters, Samuel T.; Kreyling, Sean J.

    In 2016, the Office of International Nuclear Safeguards at the National Nuclear Security Administration (NNSA) within the Department of Energy (DOE) commissioned the Pacific Northwest National Laboratory (PNNL) to explore the potential implications of the digital currency bitcoin and its underlying technologies on the safeguards system. The authors found that one category of technologies referred to as Shared Ledger Technology (SLT) offers a spectrum of benefits to the safeguards system. While further research is needed to validate assumptions and findings in the paper, preliminary analysis suggests that both the International Atomic Energy Agency (IAEA) and Member States can use SLTmore » to promote efficient, effective, accurate, and timely reporting, and increase transparency in the safeguards system without sacrificing confidentiality of safeguards data. This increased transparency and involvement of Member States in certain safeguards transactions could lead to increased trust and cooperation among States and the public, which generates a number of benefits. This paper describes these benefits and the analytical framework for assessing SLT applications for specific safeguards problems. The paper will also describe other national security areas where SLT could provide benefits.« less

  18. Fiscal Year 2014 Annual Report on BNLs Next Generation Safeguards Initiative Human Capital Development Activities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pepper, Susan E.

    2014-10-10

    Brookhaven National Laboratory’s (BNL’s) Nonproliferation and National Security Department contributes to the National Nuclear Security Administration Office of Nonproliferation and International Security Next Generation Safeguards Initiative (NGSI) through university engagement, safeguards internships, safeguards courses, professional development, recruitment, and other activities aimed at ensuring the next generation of international safeguards professionals is adequately prepared to support the U.S. safeguards mission. This report is a summary of BNL s work under the NGSI program in Fiscal Year 2014.

  19. 78 FR 32279 - Advisory Committee On Reactor Safeguards; Notice of Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-29

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards; Notice of Meeting In accordance with the purposes of Sections 29 and 182b of the Atomic Energy Act (42 U.S.C. 2039, 2232b), the Advisory Committee on Reactor Safeguards (ACRS) will hold a meeting on June 5-7, 2013, 11545 Rockville Pike...

  20. 10 CFR 54.25 - Report of the Advisory Committee on Reactor Safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Report of the Advisory Committee on Reactor Safeguards. 54.25 Section 54.25 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) REQUIREMENTS FOR RENEWAL OF... Reactor Safeguards. Each renewal application will be referred to the Advisory Committee on Reactor...

  1. 10 CFR 54.25 - Report of the Advisory Committee on Reactor Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Report of the Advisory Committee on Reactor Safeguards. 54.25 Section 54.25 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) REQUIREMENTS FOR RENEWAL OF... Reactor Safeguards. Each renewal application will be referred to the Advisory Committee on Reactor...

  2. Recommended observational skills training for IAEA safeguards inspections. Final report: Recommended observational skills training for IAEA safeguards inspections

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Toquam, J.L.; Morris, F.A.

    This is the second of two reports prepared to assist the International Atomic Energy Agency (IAEA or Agency) in enhancing the effectiveness of its international safeguards inspections through inspector training in {open_quotes}Observational Skills{close_quotes}. The first (Phase 1) report was essentially exploratory. It defined Observational Skills broadly to include all appropriate cognitive, communications, and interpersonal techniques that have the potential to help IAEA safeguards inspectors function more effectively. It identified 10 specific Observational Skills components, analyzed their relevance to IAEA safeguards inspections, and reviewed a variety of inspection programs in the public and private sectors that provide training in one ormore » more of these components. The report concluded that while it should be possible to draw upon these other programs in developing Observational Skills training for IAEA inspectors, the approaches utilized in these programs will likely require significant adaption to support the specific job requirements, policies, and practices that define the IAEA inspector`s job. The overall objective of this second (Phase 2) report is to provide a basis for the actual design and delivery of Observational Skills training to IAEA inspectors. The more specific purposes of this report are to convey a fuller understanding of the potential application of Observational Skills to the inspector`s job, describe inspector perspectives on the relevance and importance of particular Observational Skills, identify the specific Observational Skill components that are most important and relevant to enhancing safeguards inspections, and make recommendations as to Observational Skills training for the IAEA`s consideration in further developing its Safeguards training program.« less

  3. State Regulatory Authority (SRA) Coordination of Safety, Security, and Safeguards of Nuclear Facilities: A Framework for Analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mladineo, Stephen V.; Frazar, Sarah L.; Kurzrok, Andrew J.

    This paper will explore the development of a framework for conducting an assessment of safety-security-safeguards integration within a State. The goal is to examine State regulatory structures to identify conflicts and gaps that hinder management of the three disciplines at nuclear facilities. Such an analysis could be performed by a State Regulatory Authority (SRA) to provide a self-assessment or as part of technical cooperation with either a newcomer State, or to a State with a fully developed SRA.

  4. Detection for Nuclear Nonproliferation

    DOE PAGES

    Pozzi, Sara A.; Hamel, Michael C.; Polack, J. Kyle; ...

    2016-11-13

    The detection and characterization of special nuclear materials is a high priority area for applications in nuclear safeguards and nonproliferation. We are developing new instruments based on organic scintillators to detect and characterize the emissions from special nuclear materials. This paper describes some of the gaps and challenges in nuclear safeguards and proposed approaches.

  5. 10 CFR 52.141 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.141 Section 52.141 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  6. 10 CFR 52.87 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.87 Section 52.87 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS. The ACRS...

  7. 10 CFR 52.53 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.53 Section 52.53 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  8. 10 CFR 52.165 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.165 Section 52.165 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  9. 10 CFR 52.23 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.23 Section 52.23 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application for an early site...

  10. 10 CFR 52.165 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.165 Section 52.165 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  11. 10 CFR 52.23 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.23 Section 52.23 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application for an early site...

  12. 10 CFR 52.87 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.87 Section 52.87 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS. The ACRS...

  13. 10 CFR 52.141 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.141 Section 52.141 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  14. 10 CFR 52.53 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.53 Section 52.53 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  15. A Comparison Framework for Reactor Anti-Neutrino Detectors in Near-Field Nuclear Safeguards Applications

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mendenhall, M.; Bowden, N.; Brodsky, J.

    Electron anti-neutrino ( e) detectors can support nuclear safeguards, from reactor monitoring to spent fuel characterization. In recent years, the scientific community has developed multiple detector concepts, many of which have been prototyped or deployed for specific measurements by their respective collaborations. However, the diversity of technical approaches, deployment conditions, and analysis techniques complicates direct performance comparison between designs. We have begun development of a simulation framework to compare and evaluate existing and proposed detector designs for nonproliferation applications in a uniform manner. This report demonstrates the intent and capabilities of the framework by evaluating four detector design concepts, calculatingmore » generic reactor antineutrino counting sensitivity, and capabilities in a plutonium disposition application example.« less

  16. 10 CFR 73.21 - Protection of Safeguards Information: Performance requirements.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... maintain an information protection system that includes the applicable measures for Safeguards Information specified in § 73.22 related to: Power reactors; a formula quantity of strategic special nuclear material; transportation of or delivery to a carrier for transportation of a formula quantity of strategic special nuclear...

  17. Preliminary Safeguards Assessment for the Pebble-Bed Fluoride High-Temperature Reactor (PB-FHR) Concept

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Disser, Jay; Arthur, Edward; Lambert, Janine

    2016-09-01

    This report examines a preliminary design for a pebble bed fluoride salt-cooled high temperature reactor (PB-FHR) concept, assessing it from an international safeguards perspective. Safeguards features are defined, in a preliminary fashion, and suggestions are made for addressing further nuclear materials accountancy needs.

  18. A comparison of the additional protocols of the five nuclear weapon states and the ensuing safeguards benefits to international nonproliferation efforts

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Uribe, Eva C; Sandoval, M Analisa; Sandoval, Marisa N

    2009-01-01

    With the 6 January 2009 entry into force of the Additional Protocol by the United States of America, all five declared Nuclear Weapon States that are part of the Nonproliferation Treaty have signed, ratified, and put into force the Additional Protocol. This paper makes a comparison of the strengths and weaknesses of the five Additional Protocols in force by the five Nuclear Weapon States with respect to the benefits to international nonproliferation aims. This paper also documents the added safeguards burden to the five declared Nuclear Weapon States that these Additional Protocols put on the states with respect to accessmore » to their civilian nuclear programs and the hosting of complementary access activities as part of the Additional Protocol.« less

  19. Safeguards and security research and development: Progress report, October 1994--September 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rutherford, D.R.; Henriksen, P.W.

    The primary goal of the Los Alamos Safeguards and Security Technology Development Program, International Safeguards, and other Safeguards and Security Programs is to continue to be the center of excellence in the field of Safeguards and Security. This annual report for 1995 describes those scientific and engineering projects that contribute to all of the aforementioned programs. The authors have presented the information in a different format from previous annual reports. Part I is devoted to Nuclear Material Measurement Systems. Part II contains projects that are specific to Integrated Safeguards Systems. Part III highlights Safeguards Systems Effectiveness Evaluations and Part IVmore » is a compilation of highlights from Information Assurance projects. Finally Part V highlights work on the projects at Los Alamos for International Safeguards. The final part of this annual report lists titles and abstracts of Los Alamos Safeguards and Security Technology Development reports, technical journal articles, and conference papers that were presented and published in 1995. This is the last annual report in this format. The authors wish to thank all of the individuals who have contributed to this annual report and made it so successful over the years.« less

  20. A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment and Processing Plants

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Krichinsky, Alan M; Bates, Bruce E; Chesser, Joel B

    2009-12-01

    This report describes an engineering-scale, mock UF6 feed and withdrawal (F&W) system, its operation, and its intended uses. This system has been assembled to provide a test bed for evaluating and demonstrating new methodologies that can be used in remote, unattended, continuous monitoring of nuclear material process operations. These measures are being investigated to provide independent inspectors improved assurance that operations are being conducted within declared parameters, and to increase the overall effectiveness of safeguarding nuclear material. Testing applicable technologies on a mock F&W system, which uses water as a surrogate for UF6, enables thorough and cost-effective investigation of hardware,more » software, and operational strategies before their direct installation in an industrial nuclear material processing environment. Electronic scales used for continuous load-cell monitoring also are described as part of the basic mock F&W system description. Continuous monitoring components on the mock F&W system are linked to a data aggregation computer by a local network, which also is depicted. Data collection and storage systems are described only briefly in this report. The mock UF{sub 6} F&W system is economical to operate. It uses a simple process involving only a surge tank between feed tanks and product and withdrawal (or waste) tanks. The system uses water as the transfer fluid, thereby avoiding the use of hazardous UF{sub 6}. The system is not tethered to an operating industrial process involving nuclear materials, thereby allowing scenarios (e.g., material diversion) that cannot be conducted otherwise. These features facilitate conducting experiments that yield meaningful results with a minimum of expenditure and quick turnaround time. Technologies demonstrated on the engineering-scale system lead to field trials (described briefly in this report) for determining implementation issues and performance of the monitoring technologies under plant

  1. 78 FR 79020 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Reliability...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-27

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Reliability & PRA; Notice of Meeting The ACRS Subcommittee on Reliability & PRA will hold a..., 2013. Cayetano Santos, Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards. [FR...

  2. The Coming Nuclear Renaissance for Next Generation Safeguards Specialists--Maximizing Potential and Minimizing the Risks

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Eipeldauer, Mary D

    2009-01-01

    This document is intended to provide an overview of the workshop entitled 'The Coming Nuclear Renaissance for the Next Generation Safeguards Experts-Maximizing Benefits While Minimizing Proliferation Risks', conducted at Oak Ridge National Laboratory (ORNL) in partnership with the Y-12 National Security Complex (Y-12) and the Savannah River National Laboratory (SRNL). This document presents workshop objectives; lists the numerous participant universities and individuals, the nuclear nonproliferation lecture topics covered, and the facilities tours taken as part of the workshop; and discusses the university partnership sessions and proposed areas for collaboration between the universities and ORNL for 2009. Appendix A contains themore » agenda for the workshop; Appendix B lists the workshop attendees and presenters with contact information; Appendix C contains graphics of the evaluation form results and survey areas; and Appendix D summarizes the responses to the workshop evaluation form. The workshop was an opportunity for ORNL, Y-12, and SRNL staff with more than 30 years combined experience in nuclear nonproliferation to provide a comprehensive overview of their expertise for the university professors and their students. The overall goal of the workshop was to emphasize nonproliferation aspects of the nuclear fuel cycle and to identify specific areas where the universities and experts from operations and national laboratories could collaborate.« less

  3. Pakistans Nuclear Weapons

    DTIC Science & Technology

    2016-02-12

    not be subject to International Atomic Energy Agency ( IAEA ) safeguards have the potential to produce 280...PNRA states that Pakistan follows IAEA physical protection standards. Proliferation A fundamental aspect of nuclear security is ensuring that...related to the design and fabrication of a nuclear explosive device,” according to the IAEA (Implementation of the NPT Safeguards Agreement in the

  4. Update on NRF Measurements on ^237Np for National Security and Safeguards Applications

    NASA Astrophysics Data System (ADS)

    Angell, C. T.; Joshi, T.; Yee, R.; Swanberg, E.; Norman, E. B.; Kulp, W. D.; Warren, G.; Hicks, C. L., Jr.; Korbly, S.; Klimenko, A.; Wilson, C.; Bray, T. H.; Copping, R.; Shuh, D. K.

    2010-11-01

    Nuclear resonance fluorescence (NRF) uses γ rays to excite nuclear levels and measure their properties. This provides a unique isotopic signature, and can be used to identify and assay material. This is particularly important for applications that detect the smuggling of nuclear material or the diversion of fissile material for covert weapon programs, both of which present grave risks to world security. ^237Np presents significant safeguard challenges; it is fissile yet currently has fewer safeguard restrictions potentially making it an attractive material for covert weapon programs. This talk will present the final results of two measurements of NRF on ^237Np using a bremsstrahlung photon source. 15 NRF states have been identified between 1.5 and 2.5 MeV excitation energy.

  5. 10 CFR 76.119 - Security facility approval and safeguarding of National Security Information and Restricted Data.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Security facility approval and safeguarding of National Security Information and Restricted Data. 76.119 Section 76.119 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.119 Security facility...

  6. 10 CFR 76.119 - Security facility approval and safeguarding of National Security Information and Restricted Data.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Security facility approval and safeguarding of National Security Information and Restricted Data. 76.119 Section 76.119 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.119 Security facility...

  7. 10 CFR 76.119 - Security facility approval and safeguarding of National Security Information and Restricted Data.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Security facility approval and safeguarding of National Security Information and Restricted Data. 76.119 Section 76.119 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.119 Security facility...

  8. 10 CFR 76.119 - Security facility approval and safeguarding of National Security Information and Restricted Data.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Security facility approval and safeguarding of National Security Information and Restricted Data. 76.119 Section 76.119 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.119 Security facility...

  9. 10 CFR 76.119 - Security facility approval and safeguarding of National Security Information and Restricted Data.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Security facility approval and safeguarding of National Security Information and Restricted Data. 76.119 Section 76.119 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.119 Security facility...

  10. Nuclear Safeguards and the International Atomic Energy Agency

    DTIC Science & Technology

    1995-04-01

    1993; Export Controls and Nonprolife ration Policy, OTA-ISS-596, May 1994; and Proliferation and the Former Soviet Union, OTA-ISC-605, September 1994...states would likely be much less reprocessing plant such as that being built by sanguine about the effectiveness of safeguards if a Japan at Rokkasho... formulate more intelligent and constructive pro- criminal record or are otherwise not eligible to en- posals for its improvement, which could ultimate- ter

  11. Nuclear Safeguards and the International Atomic Energy Agency

    DTIC Science & Technology

    1995-01-01

    designed to use HEU, the tite safeguards agreement already in place for cen- RERTR (Reduced Enrichment for Research and trifuge facilities (which allows only...notice in- types. Many such reactors have been converted. spections, such as provided for under the Hexa- (See discussion below on the RERTR program...the Schumer amendment to the United States was developing suitable alternate 19Some believe that the suspension of the RERTR program may have been a

  12. 78 FR 20959 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-08

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced Boiling Water Reactor The ACRS Subcommittee on Advanced Boiling Water Reactor (ABWR... Committee on Reactor Safeguards. [FR Doc. 2013-08131 Filed 4-5-13; 8:45 am] BILLING CODE 7590-01-P ...

  13. Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the US Department of Energy quarter ending September 30, 1994

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Davis, G.; Mansur, D.L.; Ruhter, W.D.

    1994-10-01

    This report presents the details of the Lawrence Livermore National Laboratory safeguards and securities program. This program is focused on developing new technology, such as x- and gamma-ray spectrometry, for measurement of special nuclear materials. This program supports the Office of Safeguards and Securities in the following five areas; safeguards technology, safeguards and decision support, computer security, automated physical security, and automated visitor access control systems.

  14. Nuclear Security for Floating Nuclear Power Plants

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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 aremore » 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« less

  15. The U.S./IAEA Workshop on Software Sustainability for Safeguards Instrumentation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pepper S. E.; .; Worrall, L.

    2014-08-08

    The U.S. National Nuclear Security Administration’s Next Generation Safeguards Initiative, the U.S. Department of State, and the International Atomic Energy Agency (IAEA) organized a a workshop on the subject of ”Software Sustainability for Safeguards Instrumentation.” The workshop was held at the Vienna International Centre in Vienna, Austria, May 6-8, 2014. The workshop participants included software and hardware experts from national laboratories, industry, government, and IAEA member states who were specially selected by the workshop organizers based on their experience with software that is developed for the control and operation of safeguards instrumentation. The workshop included presentations, to orient the participantsmore » to the IAEA Department of Safeguards software activities related to instrumentation data collection and processing, and case studies that were designed to inspire discussion of software development, use, maintenance, and upgrades in breakout sessions and to result in recommendations for effective software practices and management. This report summarizes the results of the workshop.« less

  16. Advanced integrated safeguards using front-end-triggering devices

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Howell, J.A.; Whitty, W.J.

    This report addresses potential uses of front-end-triggering devices for enhanced safeguards. Such systems incorporate video surveillance as well as radiation and other sensors. Also covered in the report are integration issues and analysis techniques.

  17. RECRUITMENT OF U.S. CITIZENS FOR VACANCIES IN IAEA SAFEGUARDS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    PEPPER,S.E.; DECARO,D.; WILLIAMS,G.

    The International Atomic Energy Agency (IAEA) relies on its member states to assist with recruiting qualified individuals for positions within the IAEA's secretariat. It is important that persons within and outside the US nuclear and safeguards industries become aware of career opportunities available at the IAEA, and informed about important vacancies. The IAEA has established an impressive web page to advertise opportunities for employment. However, additional effort is necessary to ensure that there is sufficient awareness in the US of these opportunities, and assistance for persons interested in taking positions at the IAEA. In 1998, the Subgroup on Safeguards Technicalmore » Support (SSTS) approved a special task under the US Support Program to IAEA Safeguards (USSP) for improving US efforts to identify qualified candidates for vacancies in IAEA's Department of Safeguards. The International Safeguards Project Office (ISPO) developed a plan that includes increased advertising, development of a web page to support US recruitment efforts, feedback from the US Mission in Vienna, and interaction with other recruitment services provided by US professional organizations. The main purpose of this effort is to educate US citizens about opportunities at the IAEA so that qualified candidates can be identified for the IAEA's consideration.« less

  18. IMPACT OF THE U.S. SUPPORT PROGRAM SAFEGUARDS INTERNSHIP PROGRAM.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    PEPPER, S.; OSIECKI, C.

    2006-07-16

    The U.S. Support Program began funding an internship program in the IAEA Department of Safeguards in 2002. Since that time, 39 U.S. citizens and permanent residents have been placed in one-year, paid internships with the IAEA. The management of the internship program was originally the responsibility of the International Safeguards Project Office but was transferred to the Office of Educational Programs at Brookhaven National Laboratory in 2004. Feedback on the internship program from the U.S. government and the IAEA has been positive. The interns have completed basic yet essential work for the Department of Safeguards and freed IAEA staff membersmore » to perform more complex tasks. The cost of an intern is low relative to other forms of human resources support. After the conclusion of their assignments, many of the interns go on to work for the U.S. government, the national laboratories, or companies in international safeguards and nonproliferation. This paper will discuss the work done by the interns for the IAEA, factors influencing the success of the internship program, and the effects the program has had on the careers of interns, in preparing the next generation to work in the nuclear industry, participation in INMM activities, and recruitment for U.S. citizens for safeguards positions.« less

  19. Improving Transparency in the Reporting of Safeguards Implementation: FY11 Update

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Toomey, Christopher; Odlaug, Christopher S.; Wyse, Evan T.

    2011-09-30

    In 2008, the Standing Advisory Group on Safeguards Implementation (SAGSI) indicated that the International Atomic Energy Agency's (IAEA) Safeguards Implementation Report (SIR) has not kept pace with the evolution of safeguards and provided the IAEA with a set of recommendations for improvement. The SIR is the primary mechanism for providing an overview of safeguards implementation in a given year and reporting on the annual safeguards findings and conclusions drawn by the Secretariat. As the IAEA transitions to State-level safeguards approaches, SIR reporting must adapt to reflect these evolutionary changes. This evolved report will better reflect the IAEA's transition to amore » more qualitative and information-driven approach, based upon State-as-a-whole considerations. This paper applies SAGSI's recommendations to the development of multiple models for an evolved SIR and finds that an SIR repurposed as a 'safeguards portal' could significantly enhance information delivery, clarity, and transparency. In addition, this paper finds that the 'portal concept' also appears to have value as a standardized information presentation and analysis platform for use by Country Officers, for continuity of knowledge purposes, and the IAEA Secretariat in the safeguards conclusion process. Accompanying this paper is a fully functional prototype of the 'portal' concept, built using commercial software and IAEA Annual Report data and available for viewing at http://safeguardsportal.pnnl.gov.« less

  20. 75 FR 62610 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-12

    ...: Draft Regulatory Guide DG-1237, ``Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors,'' Interim Staff Guidance (ISG) NSIR/DPR-ISG-01, ``Emergency Planning for Nuclear Power Plants... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS...

  1. 75 FR 66168 - Seeks Qualified Candidates for the Advisory Committee on Reactor Safeguards

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-27

    ... NUCLEAR REGULATORY COMMISSION Seeks Qualified Candidates for the Advisory Committee on Reactor... Reactor Safeguards (ACRS). Submit r[eacute]sum[eacute]s to Ms. Brandi Hamilton, ACRS, Mail Stop T2E-26, U... of existing and proposed nuclear power plants and on the adequacy of proposed reactor safety...

  2. The Nuclear Power and Nuclear Weapons Connection.

    ERIC Educational Resources Information Center

    Leventhal, Paul

    1990-01-01

    Explains problems enforcing the Nuclear Non-Proliferation Treaty (NPT) of 1968. Provides factual charts and details concerning the production of nuclear energy and arms, the processing and disposal of waste products, and outlines the nuclear fuel cycle. Discusses safeguards, the risk of nuclear terrorism, and ways to deal with these problems. (NL)

  3. 77 FR 68161 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-15

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on December 4, 2012, Room T-2B3, 11545...

  4. 77 FR 31044 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-24

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on June 5, 2012, Room T-2B1, 11545 Rockville...

  5. 77 FR 56240 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-12

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on September 18, 2012, Room T-2B3, 11545...

  6. 76 FR 44964 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-27

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on August 17, 2011, Room T-2B3, 11545...

  7. 78 FR 70597 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-26

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on December 3, 2013, Room T-2B1, 11545...

  8. 78 FR 17944 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-25

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on April 9, 2013, Room T-2B3, 11545 Rockville...

  9. 77 FR 38099 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-26

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on July 10, 2012, Room T-2B1, 11545 Rockville...

  10. 78 FR 66967 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommitte on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-07

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommitte on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on November 19, 2013, Room T-2B1, 11545...

  11. 76 FR 55717 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-08

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on September 23, 2011, Room T-2B3, 11545...

  12. 75 FR 27840 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-18

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on May 18, 2010, Room T-2B1, 11545 Rockville Pike, Rockville...

  13. 75 FR 27841 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-18

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on May 18, 2010, Room T-2B1, 11545 Rockville Pike, Rockville...

  14. 76 FR 27101 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-10

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on May 25, 2011, Room T-2B3, 11545 Rockville...

  15. 76 FR 34779 - Advisory Committee On Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-14

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on June 23, 2011, Room T-2B1, 11545 Rockville...

  16. 75 FR 58447 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-24

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on October 22, 2010, Room T-2B1, 11545 Rockville Pike, Rockville...

  17. 75 FR 16874 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-02

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on April 21, 2010, Room T2-B3, at 11545...

  18. 76 FR 55716 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of The ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-08

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of The ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on September 22, 2011, Room T-2B1, 11545...

  19. 75 FR 82093 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-29

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on January 11, 2011, Room T-2B3, 11545...

  20. 75 FR 4881 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-29

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on February 17, 2010, Room T2-B1, 11545...

  1. 75 FR 82092 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-29

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on January 12, 2011, Room T-2B3, 11545...

  2. 78 FR 79020 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-27

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on January 16, 2014, Room T-2B1, 11545...

  3. 76 FR 61119 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-03

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on October 4, 2011, Room T-2B1, 11545...

  4. Polyatomic interferences on high precision uranium isotope ratio measurements by MC-ICP-MS: Applications to environmental sampling for nuclear safeguards

    DOE PAGES

    Pollington, Anthony D.; Kinman, William S.; Hanson, Susan K.; ...

    2015-09-04

    Modern mass spectrometry and separation techniques have made measurement of major uranium isotope ratios a routine task; however accurate and precise measurement of the minor uranium isotopes remains a challenge as sample size decreases. One particular challenge is the presence of isobaric interferences and their impact on the accuracy of minor isotope 234U and 236U measurements. Furthermore, we present techniques used for routine U isotopic analysis of environmental nuclear safeguards samples and evaluate polyatomic interferences that negatively impact accuracy as well as methods to mitigate their impacts.

  5. 76 FR 36160 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-21

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials Notice of Meeting The ACRS Subcommittee on Radiation Protection and Nuclear Materials will hold a meeting on June 20, 2011, Room T-2B1, 11545 Rockville Pike...

  6. Used fuel extended storage security and safeguards by design roadmap

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Durbin, Samuel G.; Lindgren, Eric Richard; Jones, Robert

    2016-05-01

    In the United States, spent nuclear fuel (SNF) is safely and securely stored in spent fuel pools and dry storage casks. The available capacity in spent fuel pools across the nuclear fleet has nearly reached a steady state value. The excess SNF continues to be loaded in dry storage casks. Fuel is expected to remain in dry storage for periods beyond the initial dry cask certification period of 20 years. Recent licensing renewals have approved an additional 40 years. This report identifies the current requirements and evaluation techniques associated with the safeguards and security of SNF dry cask storage. Amore » set of knowledge gaps is identified in the current approaches. Finally, this roadmap identifies known knowledge gaps and provides a research path to deliver the tools and models needed to close the gaps and allow the optimization of the security and safeguards approaches for an interim spent fuel facility over the lifetime of the storage site.« less

  7. Changes to criminal records checks used to safeguard vulnerable patients.

    PubMed

    Griffith, Richard; Tengnah, Cassam

    2012-07-01

    The Protection of Freedoms Act 2012 is introducing changes to the Criminal Records Bureau (CRB) checks carried out on those people who work with vulnerable groups. The new law is the coalition Government's response to the criticism of the Safeguarding Vulnerable Group Act 2006. It will merge the CRB and Independent Safeguarding Authority into a new Disclosure and Barring Service and will enhance the rights of applicants to challenge the CRB's right to disclose non-conviction information as part of an enhanced criminal records check. In the first of two articles on the Protection of Freedoms Act 2012, Richard Griffith and Cassam Tengnah discuss the current framework for disclosing criminal records and the impact of the changes on district nurses applying for new posts.

  8. Nuclear Wallet Cards

    Science.gov Websites

    Index Nuclear Wallet Cards Contents Current Version Radioactive Nuclides (Homeland Security) Nuclear Materials Management & Safeguards System 8th Edition 2011 Nuclear Wallet Cards Resources Search Nuclear Wallet Cards 8th Edition PDF Format 8thEdition, Android Market Download Nuclear Wallet Cards Nuclear

  9. Annual Report FY2013-- A Kinematically Complete, Interdisciplinary, and Co-Institutional Measurement of the 19F(α,n) Cross-section for Nuclear Safeguards Science

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Peters, William A; Smith, Michael Scott; Clement, Ryan

    2013-10-01

    The goal of this proposal is to enable neutron detection for precision Non-Destructive Assays (NDAs) of actinide-fluoride samples. Neutrons are continuously generated from a UFx matrix in a container or sample as a result of the interaction of alpha particles from uranium-decay α particles with fluorine nuclei in the matrix. Neutrons from 19F(α,n)22Na were once considered a poorly characterized background for assays of UFx samples via 238U spontaneous fission neutron detection [SMI2010B]. However, the yield of decay-α-driven neutrons is critical for 234,235U LEU and HEU assays, as it can used to determine both the total amount of uranium and themore » enrichment [BER2010]. This approach can be extremely valuable in a variety of safeguard applications, such as cylinder monitoring in underground uranium storage facilities, nuclear criticality safety studies, nuclear materials accounting, and other nonproliferation applications. The success of neutron-based assays critically depends on an accurate knowledge of the cross section of the (α,n) reaction that generates the neutrons. The 40% uncertainty in the 19F(α,n)22Na cross section currently limits the precision of such assays, and has been identified as a key factor in preventing accurate enrichment determinations [CRO2003]. The need for higher quality cross section data for (α,n) reactions has been a recurring conclusion in reviews of the nuclear data needs to support safeguards. The overarching goal of this project is to enable neutron detection to be used for precision Non- Destructive Assays (NDAs) of actinide-fluoride samples. This will significantly advance safeguards verification at existing declared facilities, nuclear materials accounting, process control, nuclear criticality safety monitoring, and a variety of other nonproliferation applications. To reach this goal, Idaho National Laboratory (INL), in partnership with Oak Ridge National Laboratory (ORNL), Rutgers University (RU), and the University

  10. EURATOM safeguards efforts in the development of spent fuel verification methods by non-destructive assay

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Matloch, L.; Vaccaro, S.; Couland, M.

    The back end of the nuclear fuel cycle continues to develop. The European Commission, particularly the Nuclear Safeguards Directorate of the Directorate General for Energy, implements Euratom safeguards and needs to adapt to this situation. The verification methods for spent nuclear fuel, which EURATOM inspectors can use, require continuous improvement. Whereas the Euratom on-site laboratories provide accurate verification results for fuel undergoing reprocessing, the situation is different for spent fuel which is destined for final storage. In particular, new needs arise from the increasing number of cask loadings for interim dry storage and the advanced plans for the construction ofmore » encapsulation plants and geological repositories. Various scenarios present verification challenges. In this context, EURATOM Safeguards, often in cooperation with other stakeholders, is committed to further improvement of NDA methods for spent fuel verification. In this effort EURATOM plays various roles, ranging from definition of inspection needs to direct participation in development of measurement systems, including support of research in the framework of international agreements and via the EC Support Program to the IAEA. This paper presents recent progress in selected NDA methods. These methods have been conceived to satisfy different spent fuel verification needs, ranging from attribute testing to pin-level partial defect verification. (authors)« less

  11. 76 FR 52715 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Regulatory...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-23

    ... review Draft Final Regulatory Guide (RG) 1.93, ``Availability of Electric Power Sources,'' Revision 1 and new Draft Final RG 1.218, ``Condition Monitoring Techniques for Electric Cables Used in Nuclear Power... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS...

  12. 75 FR 61227 - Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on Future Plant Designs...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-04

    ... Westinghouse Electric Company, General Electric--Hitachi Nuclear Energy (GEH), and their contractors, pursuant... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on Future Plant Designs; Revision to the September 24, 2010, ACRS Meeting Federal Register Notice...

  13. Model of a Generic Natural Uranium Conversion Plant ? Suggested Measures to Strengthen International Safeguards

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Raffo-Caiado, Ana Claudia; Begovich, John M; Ferrada, Juan J

    This is the final report that closed a joint collaboration effort between DOE and the National Nuclear Energy Commission of Brazil (CNEN). In 2005, DOE and CNEN started a collaborative effort to evaluate measures that can strengthen the effectiveness of international safeguards at a natural uranium conversion plant (NUCP). The work was performed by DOE s Oak Ridge National Laboratory and CNEN. A generic model of a NUCP was developed and typical processing steps were defined. Advanced instrumentation and techniques for verification purposes were identified and investigated. The scope of the work was triggered by the International Atomic Energy Agencymore » s 2003 revised policy concerning the starting point of safeguards at uranium conversion facilities. Prior to this policy only the final products of the uranium conversion plant were considered to be of composition and purity suitable for use in the nuclear fuel cycle and therefore, subject to the IAEA safeguards control. DOE and CNEN have explored options for implementing the IAEA policy, although Brazil understands that the new policy established by the IAEA is beyond the framework of the Quadripartite Agreement of which it is one of the parties, together with Argentina, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) and the IAEA. Two technical papers on this subject were published at the 2005 and 2008 INMM Annual Meetings.« less

  14. 75 FR 4428 - Advisory Committee On Reactor Safeguards; Revised Meeting Notice

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-27

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards; Revised Meeting Notice The Agenda for the 569th ACRS meeting, scheduled to be held on February 4-6, 2010, has been revised as noted below. Notice of this meeting was previously published in the Federal Register on Thursday, January 21...

  15. 75 FR 72844 - Advisory Committee on Reactor Safeguards; Revised Meeting Notice

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-26

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Revised Meeting Notice The Agenda for the 578th ACRS meeting, scheduled to be held on December 2-4, 2010, has been revised as noted below. Notice of this meeting was previously published in the Federal Register on Wednesday, November 17...

  16. DOE/NNSA perspective safeguard by design: GEN III/III+ light water reactors and beyond

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pan, Paul Y

    2010-12-10

    An overview of key issues relevant to safeguards by design (SBD) for GEN III/IV nuclear reactors is provided. Lessons learned from construction of typical GEN III+ water reactors with respect to SBD are highlighted. Details of SBD for safeguards guidance development for GEN III/III+ light water reactors are developed and reported. This paper also identifies technical challenges to extend SBD including proliferation resistance methodologies to other GEN III/III+ reactors (except HWRs) and GEN IV reactors because of their immaturity in designs.

  17. 76 FR 61118 - Advisory Committee on Reactor Safeguards; Revised Meeting Notice

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-03

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Revised Meeting Notice The Agenda for the 587th ACRS meeting, scheduled to be held on October 6-8, 2011, has been revised as noted below. Notice of this meeting was previously published in the Federal Register on September 26, 2011 (76...

  18. 10 CFR 2.809 - Participation by the Advisory Committee on Reactor Safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Participation by the Advisory Committee on Reactor Safeguards. 2.809 Section 2.809 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Rulemaking § 2.809 Participation by the Advisory Committee on Reactor...

  19. Application of laser induced breakdown spectroscopy (LIBS) instrumentation for international safeguards

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Barefield Ii, James E; Clegg, Samuel M; Lopez, Leon N

    2010-01-01

    Advanced methodologies and improvements to current measurements techniques are needed to strengthen the effectiveness and efficiency of international safeguards. This need was recognized and discussed at a Technical Meeting on 'The Application of Laser Spectrometry Techniques in IAEA Safeguards' held at IAEA headquarters (September 2006). One of the principal recommendations from that meeting was the need to pursue the development of novel complementary access instrumentation based on Laser Induced Breakdown Spectroscopy (UBS) for the detection of gaseous and solid signatures and indicators of nuclear fuel cycle processes and associated materials'. Pursuant to this recommendation the Department of Safeguards (SG) undermore » the Division of Technical Support (SGTS) convened the 'Experts and Users Advisory Meeting on Laser Induced Breakdown Spectroscopy (LIBS) for Safeguards Applications' also held at IAEA headquarters (July 2008). This meeting was attended by 12 LlBS experts from the Czech Republic, the European Commission, France, the Republic of South Korea, the United States of America, Germany, the United Kingdom of Great Britain, Canada, and Northern Ireland. Following a presentation of the needs of the IAEA inspectors, the LIBS experts agreed that needs as presented could be partially or fully fulfilled using LIBS instrumentation. Inspectors needs were grouped into the following broad categories: (1) Improvements to in-field measurements/environmental sampling; (2) Monitoring status of activities in Hot Cells; (3) Verify status of activity at a declared facility via process monitoring; and (4) Need for pre-screening of environmental samples before analysis. The primary tool employed by the IAEA to detect undeclared processes and activities at special nuclear material facilities and sites is environmental sampling. One of the objectives of the Next Generation Safeguards Initiative (NGSI) Program Plan calls for the development of advanced tools and

  20. 78 FR 69286 - Facility Security Clearance and Safeguarding of National Security Information and Restricted Data

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-19

    ... Clearance and Safeguarding of National Security Information and Restricted Data AGENCY: Nuclear Regulatory... Executive Order 13526, Classified National Security Information. In addition, this direct final rule allowed... licensees (or their designees) to conduct classified [[Page 69287

  1. 76 FR 55717 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Reliability...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-08

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Reliability and Probabilistic Risk Assessment The ACRS Subcommittee on Reliability and PRA will hold a meeting [[Page 55718

  2. Game Imaging Meets Nuclear Reality

    ScienceCinema

    Michel, Kelly; Watkins, Adam

    2018-01-16

    At Los Alamos National Laboratory, a team of artists and animators, nuclear engineers and computer scientists is teaming to provide 3-D models of nuclear facilities to train IAEA safeguards inspectors and others who need fast familiarity with specific nuclear sites.

  3. 10 CFR Appendix C to Part 73 - Nuclear Power Plant Safeguards Contingency Plans

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    .... Licensee's Organizational Structure for Contingency Responses—A delineation of the organization's chain of.... The following topics must be addressed: a. Organizational Structure. The safeguards contingency plan... individual, group, or organizational entity responsible for each decision and action. The goals of licensee...

  4. Qualification of heavy water based irradiation device in the JSI TRIGA reactor for irradiations of FT-TIMS samples for nuclear safeguards

    NASA Astrophysics Data System (ADS)

    Radulović, Vladimir; Kolšek, Aljaž; Fauré, Anne-Laure; Pottin, Anne-Claire; Pointurier, Fabien; Snoj, Luka

    2018-03-01

    The Fission Track Thermal Ionization Mass Spectrometry (FT-TIMS) method is considered as the reference method for particle analysis in the field of nuclear Safeguards for measurements of isotopic compositions (fissile material enrichment levels) in micrometer-sized uranium particles collected in nuclear facilities. An integral phase in the method is the irradiation of samples in a very well thermalized neutron spectrum. A bilateral collaboration project was carried out between the Jožef Stefan Institute (JSI, Slovenia) and the Commissariat à l'Énergie Atomique et aux Énergies Alternatives (CEA, France) to determine whether the JSI TRIGA reactor could be used for irradiations of samples for the FT-TIMS method. This paper describes Monte Carlo simulations, experimental activation measurements and test irradiations performed in the JSI TRIGA reactor, firstly to determine the feasibility, and secondly to design and qualify a purpose-built heavy water based irradiation device for FT-TIMS samples. The final device design has been shown experimentally to meet all the required performance specifications.

  5. The Nuclear Energy Advanced Modeling and Simulation Safeguards and Separations Reprocessing Plant Toolkit

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    McCaskey, Alex; Billings, Jay Jay; de Almeida, Valmor F

    2011-08-01

    This report details the progress made in the development of the Reprocessing Plant Toolkit (RPTk) for the DOE Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. RPTk is an ongoing development effort intended to provide users with an extensible, integrated, and scalable software framework for the modeling and simulation of spent nuclear fuel reprocessing plants by enabling the insertion and coupling of user-developed physicochemical modules of variable fidelity. The NEAMS Safeguards and Separations IPSC (SafeSeps) and the Enabling Computational Technologies (ECT) supporting program element have partnered to release an initial version of the RPTk with a focus on software usabilitymore » and utility. RPTk implements a data flow architecture that is the source of the system's extensibility and scalability. Data flows through physicochemical modules sequentially, with each module importing data, evolving it, and exporting the updated data to the next downstream module. This is accomplished through various architectural abstractions designed to give RPTk true plug-and-play capabilities. A simple application of this architecture, as well as RPTk data flow and evolution, is demonstrated in Section 6 with an application consisting of two coupled physicochemical modules. The remaining sections describe this ongoing work in full, from system vision and design inception to full implementation. Section 3 describes the relevant software development processes used by the RPTk development team. These processes allow the team to manage system complexity and ensure stakeholder satisfaction. This section also details the work done on the RPTk ``black box'' and ``white box'' models, with a special focus on the separation of concerns between the RPTk user interface and application runtime. Section 4 and 5 discuss that application runtime component in more detail, and describe the dependencies, behavior, and rigorous testing of its constituent components.« less

  6. 76 FR 9835 - Advisory Committee on Reactor Safeguards; Meeting of the ACRS Subcommittee on Digital...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-02-22

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Meeting of the ACRS Subcommittee on Digital Instrumentation & Control (DI&C); Revision to February 23, 2011, ACRS Meeting Federal Register Notice The Federal Register Notice for the ACRS Subcommittee Meeting on Digital Instrumentation...

  7. Going nuclear: The spread of nuclear weapons 1986-1987

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Spector, L.S.

    1987-01-01

    In the third annual report of the Carnegie Endowment for International Peace on the spread of nuclear weapons, Spector provides a critical survey of the status of nuclear proliferation throughout the world and examines the nuclear potential of nations in the Middle East, Asia, Africa, and Latin America. Drawing on both historical documents and up-to-date reports, the author addresses such specific topics as Israel's nuclear arsenal, nuclear terrorism and its global security implications, arms control and nuclear safeguards, international treaties, weapons buildup, and political radicalism and unrest in nuclear-threshold nations.

  8. 10 CFR Appendix C to Part 73 - Nuclear Power Plant Safeguards Contingency Plans

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... command and delegation of authority as these apply to safeguards contingencies. b. Physical Layout—(i..., up to and including the design basis threat of radiological sabotage. The goals of licensee... general description of how the response is organized. a. Perceived Danger—Consistent with the design basis...

  9. Decommissioning the Fuel Process Building, a Shift in Paradigm for Terminating Safeguards on Process Holdup

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ivan R. Thomas

    INMM Abstract 51st Annual Meeting Decommissioning the Fuel Process Building, a Shift in Paradigm for Terminating Safeguards on Process Holdup The Fuel Process Building at the Idaho Nuclear Technology and Engineering Center (INTEC) is being decommissioned after nearly four decades of recovering high enriched uranium from various government owned spent nuclear fuels. The separations process began with fuel dissolution in one of multiple head-ends, followed by three cycles of uranium solvent extraction, and ending with denitration of uranyl nitrate product. The entire process was very complex, and the associated equipment formed an extensive maze of vessels, pumps, piping, and instrumentationmore » within several layers of operating corridors and process cells. Despite formal flushing and cleanout procedures, an accurate accounting for the residual uranium held up in process equipment over extended years of operation, presented a daunting safeguards challenge. Upon cessation of domestic reprocessing, the holdup remained inaccessible and was exempt from measurement during ensuing physical inventories. In decommissioning the Fuel Process Building, the Idaho Cleanup Project, which operates the INTEC, deviated from the established requirements that all nuclear material holdup be measured and credited to the accountability books and that all nuclear materials, except attractiveness level E residual holdup, be transferred to another facility. Instead, the decommissioning involved grouting the process equipment in place, rather than measuring and removing the contained holdup for subsequent transfer. The grouting made the potentially attractiveness level C and D holdup even more inaccessible, thereby effectually converting the holdup to attractiveness level E and allowing for termination of safeguards controls. Prior to grouting the facility, the residual holdup was estimated by limited sampling and destructive analysis of solutions in process lines and by acceptable

  10. 75 FR 55365 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Joint Subcommittee

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-10

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Joint Subcommittee The ACRS Subcommittees on Thermal Hydraulics Phenomena; Advanced Boiling Water Reactor (ABWR); and Materials, Metallurgy, and Reactor Fuels will hold a joint meeting on October 4, 2010...

  11. LANL Safeguards and Security Assurance Program. Revision 6

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1995-04-03

    The Safeguards and Security (S and S) Assurance Program provides a continuous quality improvement approach to ensure effective, compliant S and S program implementation throughout the Los Alamos National Laboratory. Any issues identified through the various internal and external assessments are documented, tracked and closed using the Safeguards and Security Issue Management Program. The Laboratory utilizes an integrated S and S systems approach to protect US Department of Energy (DOE) interests from theft or diversion of special nuclear material (SNM), sabotage, espionage, loss or theft of classified/controlled matter or government property, and other hostile acts that may cause unacceptable impactsmore » on national security, health and safety of employees and the public, and the environment. This document explains the basis, scope, and conduct of the S and S process to include: self-assessments, issue management, risk assessment, and root cause analysis. It also provides a discussion of S and S topical areas, roles and responsibilities, process flow charts, minimum requirements, methodology, terms, and forms.« less

  12. 10 CFR Appendix C to Part 73 - Nuclear Power Plant Safeguards Contingency Plans

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... command and delegation of authority as these apply to safeguards contingencies. b. Physical Layout—(i..., up to and including the design basis threat of radiological sabotage. The goals of licensee.... Perceived Danger—Consistent with the design basis threat specified in § 73.1(a)(1), licensees shall identify...

  13. 76 FR 57082 - Advisory Committee on Reactor Safeguards; Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-15

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels Revision to September 21, 2011, ACRS Meeting; Federal... Reactor Fuels is being revised to correct the meeting date to Wednesday, September 21, 2011. The notice of...

  14. 76 FR 76442 - Advisory Committee On Reactor Safeguards Meeting of The ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-07

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards Meeting of The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels Revision to December 15, 2011, ACRS Meeting Federal... & Reactor Fuels scheduled to be held on December 15, 2011, is being revised to notify the following: The...

  15. 75 FR 58449 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-24

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels The ACRS Subcommittee on Materials, Metallurgy & Reactor... would result in a major inconvenience. Dated: September 17, 2010. Antonio Dias, Chief, Reactor Safety...

  16. 77 FR 9707 - Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on Thermal-Hydraulics...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-17

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on Thermal-Hydraulics Phenomena; Revision to February 22, 2012, ACRS Meeting Federal Register Notice The Federal Register Notice for the ACRS Subcommittee meeting on Thermal-Hydraulics Phenomena...

  17. 76 FR 55718 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-08

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels The ACRS Subcommittee on Materials, Metallurgy & Reactor...'' for reactor coolant system (RCS) components, as mentioned in 10 CFR 50 Appendix A, GDC-4. The...

  18. REVIEW OF THE NEGOTIATION OF THE MODEL PROTOCOL ADDITIONAL TO THE AGREEMENT(S) BETWEEN STATE(S) AND THE INTERNATIONAL ATOMIC ENERGY AGENCY FOR THE APPLICATION OF SAFEGUARDS,INFCIRC/540 (Corrected) VOLUME I/III SETTING THE STAGE: 1991-1996.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rosenthal, M.D.; Saum-Manning, L.; Houck, F.

    Events in Iraq at the beginning of the 1990s demonstrated that the safeguards system of the International Atomic Energy Agency (IAEA) needed to be improved. It had failed, after all, to detect Iraq's clandestine nuclear weapon program even though some of Iraq's's activities had been pursued at inspected facilities in buildings adjacent to ones being inspected by the IAEA. Although there were aspects of the implementation of safeguards where the IAEA needed to improve, the primary limitations were considered to be part of the safeguards system itself. That system was based on the Nuclear Nonproliferation Treaty of 1970, to whichmore » Iraq was a party, and implemented on the basis of a model NPT safeguards agreement, published by the IAEA 1972 as INFCIRC/153 (corrected). The agreement calls for states to accept and for the IAEA to apply safeguards to all nuclear material in the state. Iraq was a party to such an agreement, but it violated the agreement by concealing nuclear material and other nuclear activities from the IAEA. Although the IAEA was inspecting in Iraq, it was hindered by aspects of the agreement that essentially limited its access to points in declared facilities and provided the IAEA with little information about nuclear activities anywhere else in Iraq. As a result, a major review of the NPT safeguards system was initiated by its Director General and Member States with the objective of finding the best means to enable the IAEA to detect both diversions from declared stocks and any undeclared nuclear material or activities in the state. Significant improvements that could be made within existing legal authority were taken quickly, most importantly a change in 1992 in how and when and what design information would be reported to the IAEA. During 1991-1996, the IAEA pursued intensive study, legal and technical analysis, and field trials and held numerous consultations with Member States. The Board of Governors discussed the issue of strengthening

  19. Safeguards and retrievability from waste forms

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Danker, W.

    1996-05-01

    This report describes issues discussed at a session from the PLutonium Stabilization and Immobilization Workshop related to safeguards and retrievability from waste forms. Throughout the discussion, the group probed the goals of disposition efforts, particularly an understanding of the {open_quotes}spent fuel standard{close_quotes}, since the disposition material form derives from these goals. The group felt strongly that not only the disposition goals but safeguards to meet these goals could affect the material form. Accordingly, the Department was encouraged to explore and apply safeguards as early in the implementation process as possible. It was emphasized that this was particularly true for anymore » planned use of existing facilities. It is much easier to build safeguards approaches into the development of new facilities, than to backfit existing facilities. Accordingly, special safeguards challenges are likely to be encountered, given the cost and schedule advantages offered by use of existing facilities.« less

  20. 7 CFR 400.408 - Safeguards and storage.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 7 Agriculture 6 2013-01-01 2013-01-01 false Safeguards and storage. 400.408 Section 400.408... and Storage of Social Security Account Numbers and Employer Identification Numbers § 400.408 Safeguards and storage. Records must be maintained in secured storage with proper safeguards sufficient to...

  1. 7 CFR 400.408 - Safeguards and storage.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 7 Agriculture 6 2011-01-01 2011-01-01 false Safeguards and storage. 400.408 Section 400.408... and Storage of Social Security Account Numbers and Employer Identification Numbers § 400.408 Safeguards and storage. Records must be maintained in secured storage with proper safeguards sufficient to...

  2. 7 CFR 400.408 - Safeguards and storage.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 7 Agriculture 6 2012-01-01 2012-01-01 false Safeguards and storage. 400.408 Section 400.408... and Storage of Social Security Account Numbers and Employer Identification Numbers § 400.408 Safeguards and storage. Records must be maintained in secured storage with proper safeguards sufficient to...

  3. 5 CFR 2500.9 - Safeguarding.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 5 Administrative Personnel 3 2011-01-01 2011-01-01 false Safeguarding. 2500.9 Section 2500.9 Administrative Personnel OFFICE OF ADMINISTRATION, EXECUTIVE OFFICE OF THE PRESIDENT INFORMATION SECURITY REGULATION § 2500.9 Safeguarding. The Office of Administration shall protect information in its custody...

  4. 5 CFR 2500.9 - Safeguarding.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 5 Administrative Personnel 3 2010-01-01 2010-01-01 false Safeguarding. 2500.9 Section 2500.9 Administrative Personnel OFFICE OF ADMINISTRATION, EXECUTIVE OFFICE OF THE PRESIDENT INFORMATION SECURITY REGULATION § 2500.9 Safeguarding. The Office of Administration shall protect information in its custody...

  5. 7 CFR 947.55 - Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 947.55 Section 947.55 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... safeguards to prevent shipments pursuant to § 947.54 from entering channels of trade and other outlets for...

  6. 75 FR 10840 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Subcommittee on Advanced Boiling...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-09

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Subcommittee on Advanced Boiling Water Reactor (ABWR); Notice of Meeting The ACRS Subcommittee on ABWR will... would result in major inconvenience. Dated: March 3, 2010. Antonio F. Dias, Chief, Reactor Safety Branch...

  7. 76 FR 5218 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-28

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced Boiling Water Reactor (ABWR); Notice of Meeting The ACRS Subcommittee on Advanced Boiling Water Reactor (ABWR) will hold a meeting on February 8, 2011, 11545 Rockville Pike, Rockville, MD...

  8. 77 FR 9707 - Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on Power Uprates...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-17

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on Power Uprates; Revision to February 23, 2012, ACRS Meeting Federal Register Notice The Federal Register Notice for the ACRS Subcommittee meeting on Power Uprates, scheduled to be held on February 23...

  9. 76 FR 11525 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Reliability...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-02

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Reliability and Probabilistic Risk Assessment (PRA); Notice of Meeting The ACRS Subcommittee on Reliability and Probabilistic Risk Assessment (PRA), Room T-2B1, 11545 Rockville Pike, Rockville, Maryland...

  10. 75 FR 58447 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-24

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Plant License Renewal The ACRS Subcommittee on Plant License Renewal will hold a meeting on..., ``Generic Aging Lessons Learned (GALL) Report.'' The Subcommittee will hear presentations by and hold...

  11. 77 FR 52371 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-29

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on September 5, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. [[Page 52372

  12. 78 FR 2694 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-14

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Fukushima; Cancellation of the January 18, 2013, ACRS Subcommittee Meeting The ACRS Subcommittee meeting on Fukushima scheduled for January 18, 2013 has been cancelled. The notice of this meeting...

  13. 76 FR 53979 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Thermal...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-30

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Thermal Hydraulics Phenomena; Notice of Meeting The ACRS Subcommittee on Thermal Hydraulics... Revision 4 to Regulatory Guide 1.82, ``Water Sources for Long-Term Recirculation Cooling Following a Loss...

  14. 78 FR 31987 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-28

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on June 4, 2013, Room T-2B1, 11545 Rockville Pike, Rockville...

  15. 76 FR 34778 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-14

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on June 23, 2011, Room T-2B3, 11545 Rockville Pike, Rockville...

  16. 78 FR 3474 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-16

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on February 6, 2013, Room T-2B1, 11545 Rockville Pike...

  17. 76 FR 72451 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-23

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on December 15, 2011, Room T-2B1, 11545 Rockville Pike...

  18. 77 FR 76089 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-26

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced Boiling Water Reactor; Notice of Meeting The ACRS Subcommittee on Advanced Boiling Water Reactor (ABWR) will hold a meeting on January 16, 2013, Room T-2B3, 11545 Rockville Pike...

  19. 78 FR 29159 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-17

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on May 22, 2013, Room T-2B1, 11545 Rockville Pike, Rockville...

  20. 76 FR 68793 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Economic...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-07

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Economic Simplified Boiling Water Reactor; Notice of Meeting The ACRS Subcommittee on Economic Simplified Boiling Water Reactor (ESBWR) will hold a meeting on November 30, 2011, Room T-2B1, 11545...

  1. 78 FR 34677 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the Acrs Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-10

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the Acrs Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on June 17, 2013, Room T-2B1, 11545 Rockville Pike, Rockville...

  2. 75 FR 51499 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Thermal...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-20

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Thermal Hydraulics Phenomena The ACRS Subcommittee on Thermal Hydraulics Phenomena will hold a meeting on September 7, 2010, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting...

  3. 75 FR 57536 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Thermal...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-21

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Thermal Hydraulic Phenomena The ACRS Subcommittee on Thermal Hydraulic Phenomena will hold a meeting on October 18, 2010, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting...

  4. 76 FR 22934 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Reliability...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-25

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Reliability and Probabilistic Risk Assessment; Notice of Meeting The ACRS Subcommittee on Reliability and Probabilistic Risk Assessment (PRA) will hold a meeting on May 11, 2011, Room T-2B3, 11545...

  5. 76 FR 71609 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Reliability...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-18

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Reliability and Probabilistic Risk Assessment; Notice of Meeting The ACRS Subcommittee on Reliability and Probabilistic Risk Assessment (PRA) will hold a meeting on December 14, 2011, Room T-2B3...

  6. 77 FR 74698 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-17

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on January 16, 2013, Room T-2B3, 11545 Rockville Pike...

  7. 78 FR 56756 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-13

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on September 19, 2013, Room T-2B3, 11545 Rockville Pike...

  8. 78 FR 79019 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-27

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on January 14, 2014, Room T-2B1, 11545 Rockville Pike...

  9. 78 FR 70598 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-26

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on December 4, 2013, Room T-2B1, 11545 Rockville Pike...

  10. 76 FR 24540 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-02

    ... Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy & Reactor Fuels will hold a meeting on May 10, 2011, Room T-2B1, 11545 Rockville Pike, Rockville...

  11. 76 FR 27103 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-10

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on May 26....m. The Subcommittee will review recent events at the Fukushima site in Japan. The Subcommittee will...

  12. 77 FR 47680 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittees on Reliability...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-09

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittees on Reliability and PRA and Fukushima; Revision to Notice of Meetings The (ACRS) Subcommittee on Fukushima originally scheduled for the afternoon of August 14, 2012, has been moved to the morning of August...

  13. 76 FR 34778 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-14

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on June 23....m. The Subcommittee will review recent events at the Fukushima site in Japan. The Subcommittee will...

  14. Proliferation resistance assessment of various methods of spent nuclear fuel storage and disposal

    NASA Astrophysics Data System (ADS)

    Kollar, Lenka

    Many countries are planning to build or already are building new nuclear power plants to match their growing energy needs. Since all nuclear power plants handle nuclear materials that could potentially be converted and used for nuclear weapons, they each present a nuclear proliferation risk. Spent nuclear fuel presents the largest build-up of nuclear material at a power plant. This is a proliferation risk because spent fuel contains plutonium that can be chemically separated and used for a nuclear weapon. The International Atomic Energy Agency (IAEA) safeguards spent fuel in all non-nuclear weapons states that are party to the Non-Proliferation Treaty. Various safeguards methods are in use at nuclear power plants and research is underway to develop safeguards methods for spent fuel in centralized storage or underground storage and disposal. Each method of spent fuel storage presents different proliferation risks due to the nature of the storage method and the safeguards techniques that are utilized. Previous proliferation resistance and proliferation risk assessments have mainly compared nuclear material through the whole fuel cycle and not specifically focused on spent fuel storage. This project evaluates the proliferation resistance of the three main types of spent fuel storage: spent fuel pool, dry cask storage, and geological repository. The proliferation resistance assessment methodology that is used in this project is adopted from previous work and altered to be applicable to spent fuel storage. The assessment methodology utilizes various intrinsic and extrinsic proliferation-resistant attributes for each spent fuel storage type. These attributes are used to calculate a total proliferation resistant (PR) value. The maximum PR value is 1.00 and a greater number means that the facility is more proliferation resistant. Current data for spent fuel storage in the United States and around the world was collected. The PR values obtained from this data are 0.49 for

  15. 76 FR 52715 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-23

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital Instrumentation and Control Systems; Notice of Meeting The ACRS Subcommittee on Digital Instrumentation and Control Systems (DI&C) will hold a meeting on September 7, 2011, Room T-2B1, 11545 Rockville...

  16. 77 FR 59678 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Advanced...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-28

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Advanced Boiling Water Reactor; Notice of Meeting The ACRS Subcommittee on Advanced Boiling Water Reactor (ABWR) will hold a meeting on October 2, 2012, Room T-2B1, 11545 Rockville Pike, Rockville...

  17. 76 FR 16016 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of The ACRS Subcommittee on Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-22

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of The ACRS Subcommittee on Materials, Metallurgy And Reactor Fuels; Notice of Meeting The ACRS Subcommittee on Materials, Metallurgy and Reactor Fuels will hold a meeting on April 6, 2011, Room T-2B3, 11545 Rockville Pike...

  18. 76 FR 34276 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Advanced...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-13

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Advanced Boiling Water Reactor; Notice of Meeting The ACRS Subcommittee on Advanced Boiling Water Reactor (ABWR) will hold a meeting on June 21, 2011, Room T-2B1, 11545 Rockville Pike, Rockville...

  19. 76 FR 62866 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Economic...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-11

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Economic Simplified Boiling Water Reactor; Notice of Meeting The ACRS Subcommittee on Economic Simplified Boiling Water Reactor (ESBWR) will hold a meeting on October 21, 2011, Room T-2B1, 11545 Rockville...

  20. 76 FR 27102 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Economic...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-10

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Economic Simplified Boiling Water Reactor; Notice of Meeting The ACRS Subcommittee on Economic Simplified Boiling Water Reactor (ESBWR) will hold a meeting on May 26, 2011, Room T-2B1, 11545 Rockville...

  1. 77 FR 24745 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Thermal...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-25

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Thermal Hydraulic Phenomena; Notice of Meeting The ACRS Subcommittee on Thermal Hydraulic Phenomena will hold a meeting on May 8-9, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The...

  2. 76 FR 18586 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Reliability...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-04

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Reliability and Probabilistic Risk Assessment (PRA); Notice of Meeting The ACRS Subcommittee on Reliability and Probabilistic Risk Assessment (PRA) will hold a meeting on April 20, 2011, Room T-2B1, 11545...

  3. 77 FR 60480 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Digital...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-03

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Digital Instrumentation and Control Systems; Notice of Meeting The ACRS Subcommittee on Digital Instrumentation and Control Systems (DI&C) will hold a meeting on October 30, 2012, Room T-2B1, 11545 Rockville...

  4. 77 FR 45699 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-01

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on August 14, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

  5. 77 FR 68161 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-15

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on December... flooding reevaluations requested in the March 2012 10 CFR 50.54(f) letters to address Fukushima Near-Term...

  6. 78 FR 65008 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-30

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on November 5, 2013, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

  7. 76 FR 44377 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-25

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on August... task force review of the events at the Fukushima Dai-Ichi reactor site in Japan. The Subcommittee will...

  8. 77 FR 68161 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-15

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on December 4, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

  9. 77 FR 74697 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-17

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on January 18, 2013, Room T-2B3, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

  10. 78 FR 50457 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-19

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on September 4, 2013, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

  11. 78 FR 27442 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-10

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on May 23, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public...

  12. 78 FR 51752 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-21

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on September 18, 2013, Room T-2B3, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open...

  13. 77 FR 59676 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-28

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on October 3, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

  14. 77 FR 64147 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-18

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on October 31, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

  15. 75 FR 38564 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Subcommittee on Plant Operations...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-02

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Subcommittee on Plant Operations and Fire Protection The ACRS Subcommittee on Plant Operations and Fire Protection will hold a meeting on July 29, 2010, at the U.S. NRC Region IV, Texas Health Resources Tower, 612...

  16. 76 FR 26775 - Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on EPR; Cancellation to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-09

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on EPR; Cancellation to May 11, 2011, ACRS Meeting-- Federal Register Notice The Federal Register Notice for the ACRS Subcommittee Meeting on the design certification application review of the U.S...

  17. Updated hazard rate equations for dual safeguard systems.

    PubMed

    Rothschild, Marc

    2007-04-11

    A previous paper by this author [M.J. Rothschild, Updated hazard rate equation for single safeguards, J. Hazard. Mater. 130 (1-2) (2006) 15-20] showed that commonly used analytical methods for quantifying failure rates overestimates the risk in some circumstances. This can lead the analyst to mistakenly believe that a given operation presents an unacceptable risk. For a single safeguard system, a formula was presented in that paper that accurately evaluates the risk over a wide range of conditions. This paper expands on that analysis by evaluating the failure rate for dual safeguard systems. The safeguards can be activated at the same time or at staggered times, and the safeguard may provide an indication whether it was successful upon a challenge, or its status may go undetected. These combinations were evaluated using a Monte Carlo simulation. Empirical formulas for evaluating the hazard rate were developed from this analysis. It is shown that having the safeguards activate at the same time while providing positive feedback of their individual actions is the most effective arrangement in reducing the hazard rate. The hazard rate can also be reduced by staggering the testing schedules of the safeguards.

  18. 76 FR 32240 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-03

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital Instrumentation and Control Systems; Notice of Meeting The ACRS Subcommittee on Digital Instrumentation and Control Systems (DI&C) will hold a meeting on June 7, 2011, Room T-2B1, 11545 Rockville Pike...

  19. 75 FR 66803 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Evolutionary...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-29

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Evolutionary Power Reactor (EPR); Notice of Meeting The ACRS Subcommittee on EPR will hold a..., November 30, 2010--8:30 a.m. Until 2 p.m. The Subcommittee will review Selected Chapters of the US EPR...

  20. 75 FR 27841 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on EPR

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-18

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on EPR The ACRS Subcommittee on EPR will hold a meeting on May 21, 2010, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public attendance. The agenda for...

  1. 78 FR 65008 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Evolutionary...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-30

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Evolutionary Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on November 6, 2013, Room T-2B1, 11545 Rockville Pike, Rockville...

  2. 77 FR 28637 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-15

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on May 22- 23, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

  3. 78 FR 17945 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-25

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on April 10... reevaluations requested in the March 2012 10 CFR 50.54(f) letters to address Fukushima Near-Term Task Force...

  4. 77 FR 28903 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-16

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on May 22, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public...

  5. 77 FR 31676 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-29

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on June 20, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public...

  6. 76 FR 32240 - Advisory Committee on Reactor Safeguards (ACRS) Meeting on the ACRS Subcommittee on Power Uprates

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-03

    ... Expanded Operating Domains-Power Distribution Validation and Pin-by-Pin Gamma Scan). The Subcommittee will... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting on the ACRS Subcommittee on Power Uprates Notice of Meeting The ACRS Subcommittee on Power Uprates will hold a meeting on...

  7. 75 FR 58448 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Future Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-24

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Future Plant Designs The ACRS Subcommittee on Future Plant Designs will hold a meeting on..., 2010, 1 p.m. Until 5 p.m. The Subcommittee will review current Design Acceptance Criteria associated...

  8. 75 FR 67783 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Planning and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-03

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Planning and Procedures The ACRS Subcommittee on Planning and Procedures will hold a meeting on... adjusted by the Chairman as necessary to facilitate the conduct of the meeting, persons planning to attend...

  9. 75 FR 51501 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Planning and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-20

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Planning and Procedures The ACRS Subcommittee on Planning and Procedures will hold a meeting on... facilitate the conduct of the meeting, persons planning to attend should check with these references if such...

  10. 10 CFR 71.11 - Protection of Safeguards Information.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... public health and safety or the common defense and security, shall protect Safeguards Information against... 10 Energy 2 2012-01-01 2012-01-01 false Protection of Safeguards Information. 71.11 Section 71.11... General Provisions § 71.11 Protection of Safeguards Information. Each licensee, certificate holder, or...

  11. 10 CFR 71.11 - Protection of Safeguards Information.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... public health and safety or the common defense and security, shall protect Safeguards Information against... 10 Energy 2 2011-01-01 2011-01-01 false Protection of Safeguards Information. 71.11 Section 71.11... General Provisions § 71.11 Protection of Safeguards Information. Each licensee, certificate holder, or...

  12. 10 CFR 71.11 - Protection of Safeguards Information.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... public health and safety or the common defense and security, shall protect Safeguards Information against... 10 Energy 2 2010-01-01 2010-01-01 false Protection of Safeguards Information. 71.11 Section 71.11... General Provisions § 71.11 Protection of Safeguards Information. Each licensee, certificate holder, or...

  13. 10 CFR 71.11 - Protection of Safeguards Information.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... public health and safety or the common defense and security, shall protect Safeguards Information against... 10 Energy 2 2013-01-01 2013-01-01 false Protection of Safeguards Information. 71.11 Section 71.11... General Provisions § 71.11 Protection of Safeguards Information. Each licensee, certificate holder, or...

  14. 1986 Nuclear Science Symposium, 33rd, and 1986 Symposium on Nuclear Power Systems, 18th, Washington, DC, Oct. 29-31, 1986, Proceedings

    NASA Technical Reports Server (NTRS)

    Stubblefield, F. W. (Editor)

    1987-01-01

    Papers are presented on space, low-energy physics, and general nuclear science instrumentations. Topics discussed include data acquisition systems and circuits, nuclear medicine imaging and tomography, and nuclear radiation detectors. Consideration is given to high-energy physics instrumentation, reactor systems and safeguards, health physics instrumentation, and nuclear power systems.

  15. 32 CFR 154.68 - Safeguarding procedures.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 32 National Defense 1 2012-07-01 2012-07-01 false Safeguarding procedures. 154.68 Section 154.68 National Defense Department of Defense OFFICE OF THE SECRETARY OF DEFENSE SECURITY DEPARTMENT OF DEFENSE... Safeguarding procedures. Personnel security investigative reports and personnel security determination...

  16. Training to raise staff awareness about safeguarding children.

    PubMed

    Fleming, Jane

    2015-04-01

    To improve outcomes for children and young people health organisations are required to train all staff in children's safeguarding. This creates difficulties for large complex organisations where most staff provide services to the adult population. Heart of England NHS Foundation Trust is a large acute and community trust that had difficulties in engaging staff in children's safeguarding training. Compliance rates for clinical staff who were trained in children's safeguarding were low and needed to be addressed. This article sets out why safeguarding training is important for all staff and how the trust achieved staff engagement and improved compliance rates. To evaluate, maintain and develop safeguarding knowledge, understanding, skills, attitude and behaviour further resources are planned to allow access to learning resources in a variety of formats.

  17. JAEA's actions and contributions to the strengthening of nuclear non-proliferation

    NASA Astrophysics Data System (ADS)

    Suda, Kazunori; Suzuki, Mitsutoshi; Michiji, Toshiro

    2012-06-01

    Japan, a non-nuclear weapons state, has established a commercial nuclear fuel cycle including LWRs, and now is developing a fast neutron reactor fuel cycle as part of the next generation nuclear energy system, with commercial operation targeted for 2050. Japan Atomic Energy Agency (JAEA) is the independent administrative agency for conducting comprehensive nuclear R&D in Japan after the merger of Japan Atomic Energy Research Institute (JAERI) and Japan Nuclear Cycle Development Institute (JNC). JAEA and its predecessors have extensive experience in R&D, facility operations, and safeguards development and implementation for new types of nuclear facilities for the peaceful use of nuclear energy. As the operator of various nuclear fuel cycle facilities and numerous nuclear materials, JAEA makes international contributions to strengthen nuclear non-proliferation. This paper provides an overview of JAEA's development of nuclear non-proliferation and safeguards technologies, including remote monitoring of nuclear facilities, environmental sample analysis methods and new efforts since the 2010 Nuclear Security Summit in Washington D.C.

  18. Spectroscopic methods of process monitoring for safeguards of used nuclear fuel separations

    NASA Astrophysics Data System (ADS)

    Warburton, Jamie Lee

    To support the demonstration of a more proliferation-resistant nuclear fuel processing plant, techniques and instrumentation to allow the real-time, online determination of special nuclear material concentrations in-process must be developed. An ideal materials accountability technique for proliferation resistance should provide nondestructive, realtime, on-line information of metal and ligand concentrations in separations streams without perturbing the process. UV-Visible spectroscopy can be adapted for this precise purpose in solvent extraction-based separations. The primary goal of this project is to understand fundamental URanium EXtraction (UREX) and Plutonium-URanium EXtraction (PUREX) reprocessing chemistry and corresponding UV-Visible spectroscopy for application in process monitoring for safeguards. By evaluating the impact of process conditions, such as acid concentration, metal concentration and flow rate, on the sensitivity of the UV-Visible detection system, the process-monitoring concept is developed from an advanced application of fundamental spectroscopy. Systematic benchtop-scale studies investigated the system relevant to UREX or PUREX type reprocessing systems, encompassing 0.01-1.26 M U and 0.01-8 M HNO3. A laboratory-scale TRansUranic Extraction (TRUEX) demonstration was performed and used both to analyze for potential online monitoring opportunities in the TRUEX process, and to provide the foundation for building and demonstrating a laboratory-scale UREX demonstration. The secondary goal of the project is to simulate a diversion scenario in UREX and successfully detect changes in metal concentration and solution chemistry in a counter current contactor system with a UV-Visible spectroscopic process monitor. UREX uses the same basic solvent extraction flowsheet as PUREX, but has a lower acid concentration throughout and adds acetohydroxamic acid (AHA) as a complexant/reductant to the feed solution to prevent the extraction of Pu. By examining

  19. Process monitoring in modern safeguards applications

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ehinger, M.H.

    1989-11-01

    From the safeguards standpoint, regulatory requirements are finally moving into the modern world of communication and information processing. Gone are the days when the accountant with the green eye shade and arm bands made judgments on the material balance a month after the balance was closed. The most recent Nuclear Regulatory Commission (NRC) regulations and U.S. Department of Energy (DOE) orders have very strict standards for timeliness and sensitivity to loss or removal of material. The latest regulations recognize that plant operators have a lot of information on and control over the location and movement of material within their facilities.more » This information goes beyond that traditionally reported under accountability requirements. These new regulations allow facility operators to take credit for many of the more informal process controls.« less

  20. 78 FR 66968 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-07

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced Boiling Water Reactor; Notice of Meeting The ACRS Subcommittee on Advanced Boiling Water Reactor (ABWR) will hold a meeting on November 22, 2013, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The meeting will be...

  1. 76 FR 16458 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-23

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR); Notice of Meeting The ACRS Subcommittee on U.S. EPR... of the Safety Evaluation Report (SER) with open items associated with U.S. EPR Design Control...

  2. 77 FR 73497 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-10

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR; Notice of Meeting The ACRS Subcommittee on US-APWR will hold a meeting on January 15....'' Both Topical Reports are associated with the design certification of the US-APWR. The Subcommittee will...

  3. 78 FR 47802 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-06

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR; Notice of Meeting The ACRS Subcommittee on US-APWR will hold a meeting on September 17...) associated with the US-APWR design certification and the Comanche Peak Combined License Application (COLA...

  4. 78 FR 59076 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-25

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR; Notice of Meeting The ACRS Subcommittee on US-APWR will hold a meeting on October 1... cooling for the US-APWR design. The Subcommittee will hear presentations by and hold discussions with...

  5. 78 FR 8202 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-05

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR; Notice of Meeting The ACRS Subcommittee on US-APWR will hold a meeting on February 21... the Safety Evaluation Reports (SERs) associated with the US-APWR design certification and the Comanche...

  6. 77 FR 61791 - Advisory Committee On Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee On US-APWR...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-11

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee On Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee On US-APWR; Notice of Meeting The ACRS Subcommittee on US-APWR will hold a meeting on October 18... Subcommittee will review Chapter 4, ``Reactor,'' of the Safety Evaluation Reports associated with the US-APWR...

  7. Measurement and simulation of a Compton suppression system for safeguards application

    NASA Astrophysics Data System (ADS)

    Lee, Seung Kyu; Seo, Hee; Won, Byung-Hee; Lee, Chaehun; Shin, Hee-Sung; Na, Sang-Ho; Song, Dae-Yong; Kim, Ho-Dong; Park, Geun-Il; Park, Se-Hwan

    2015-11-01

    Plutonium (Pu) contents in spent nuclear fuels, recovered uranium (U) or uranium/transuranium (U/TRU) products must be measured in order to secure the safeguardability of a pyroprocessing facility. Self-induced X-Ray fluorescence (XRF) and gamma-ray spectroscopy are useful techniques for determining Pu-to-U ratios and Pu isotope ratios of spent fuel. Photon measurements of spent nuclear fuel by using high-resolution spectrometers such as high-purity germanium (HPGe) detectors show a large continuum background in the low-energy region, which is due in large part to Compton scattering of energetic gamma rays. This paper proposes a Compton suppression system for reducing of the Compton continuum background. In the present study, the system was configured by using an HPGe main detector and a BGO (bismuth germanate: Bi4Ge3O12) guard detector. The system performances for gamma-ray measurement and XRF were evaluated by means of Monte Carlo simulations and measurements of the radiation source. The Monte Carlo N-Particle eXtended (MCNPX) simulations were performed using the same geometry as for the experiments, and considered, for exact results, the production of secondary electrons and photons. As a performance test of the Compton suppression system, the peak-to-Compton ratio, which is a figure of merit to evaluate the gamma-ray detection, was enhanced by a factor of three or more when the Compton suppression system was used.

  8. Safeguards Workforce Repatriation, Retention and Utilization

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gallucci, Nicholas; Poe, Sarah

    Brookhaven National Laboratory was tasked by NA-241 to assess the transition of former IAEA employees back to the United States, investigating the rate of retention and overall smoothness of the repatriation process among returning safeguards professionals. Upon conducting several phone interviews, study authors found that the repatriation process went smoothly for the vast majority and that workforce retention was high. However, several respondents expressed irritation over the minimal extent to which their safeguards expertise had been leveraged in their current positions. This sentiment was pervasive enough to prompt a follow-on study focusing on questions relating to the utilization rather thanmore » the retention of safeguards professionals. A second, web-based survey was conducted, soliciting responses from a larger sample pool. Results suggest that the safeguards workforce may be oversaturated, and that young professionals returning to the United States from Agency positions may soon encounter difficulties finding jobs in the field.« less

  9. Safeguards Challenges for Pebble-Bed Reactors (PBRs):Peoples Republic of China (PRC)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Forsberg, Charles W.; Moses, David Lewis

    2009-11-01

    The Peoples Republic of China (PRC) is operating the HTR-10 pebble-bed reactor (PBR) and is in the process of building a prototype PBR plant with two modular reactors (250-MW(t) per reactor) feeding steam to a single turbine-generator. It is likely to be the first modular hightemperature reactor to be ready for commercial deployment in the world because it is a highpriority project for the PRC. The plant design features multiple modular reactors feeding steam to a single turbine generator where the number of modules determines the plant output. The design and commercialization strategy are based on PRC strengths: (1) amore » rapidly growing electric market that will support low-cost mass production of modular reactor units and (2) a balance of plant system based on economics of scale that uses the same mass-produced turbine-generator systems used in PRC coal plants. If successful, in addition to supplying the PRC market, this strategy could enable China to be the leading exporter of nuclear reactors to developing countries. The modular characteristics of the reactor match much of the need elsewhere in the world. PBRs have major safety advantages and a radically different fuel. The fuel, not the plant systems, is the primary safety system to prevent and mitigate the release of radionuclides under accident conditions. The fuel consists of small (6-cm) pebbles (spheres) containing coatedparticle fuel in a graphitized carbon matrix. The fuel loading per pebble is small (~9 grams of low-enriched uranium) and hundreds of thousands of pebbles are required to fuel a nuclear plant. The uranium concentration in the fuel is an order of magnitude less than in traditional nuclear fuels. These characteristics make the fuel significantly less attractive for illicit use (weapons production or dirty bomb); but, its unusual physical form may require changes in the tools used for safeguards. This report describes PBRs, what is different, and the safeguards challenges. A series of

  10. Nuclear Forensics: Scientific Analysis Supporting Law Enforcement and Nuclear Security Investigations

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Keegan, Elizabeth; Kristo, Michael J.; Toole, Kaitlyn

    In Nuclear Forensic Science, analytical chemists join forces with nuclear physicists, material scientists, radiochemists, and traditional forensic scientists, as well as experts in nuclear security, nuclear safeguards, law enforcement, and policy development, in an effort to deter nuclear smuggling. Nuclear forensic science, or “nuclear forensics,” aims to answer questions about nuclear material found outside of regulatory control, questions such as ‘where did this material come from?’ and ‘what is the intended use of the material?’ In this Feature, we provide a general overview of nuclear forensics, selecting examples of key “nuclear forensic signatures” which have allowed investigators to determine themore » identity of unknown nuclear material in real investigations.« less

  11. Nuclear Forensics: Scientific Analysis Supporting Law Enforcement and Nuclear Security Investigations

    DOE PAGES

    Keegan, Elizabeth; Kristo, Michael J.; Toole, Kaitlyn; ...

    2015-12-24

    In Nuclear Forensic Science, analytical chemists join forces with nuclear physicists, material scientists, radiochemists, and traditional forensic scientists, as well as experts in nuclear security, nuclear safeguards, law enforcement, and policy development, in an effort to deter nuclear smuggling. Nuclear forensic science, or “nuclear forensics,” aims to answer questions about nuclear material found outside of regulatory control, questions such as ‘where did this material come from?’ and ‘what is the intended use of the material?’ In this Feature, we provide a general overview of nuclear forensics, selecting examples of key “nuclear forensic signatures” which have allowed investigators to determine themore » identity of unknown nuclear material in real investigations.« less

  12. Nuclear exports: the perilous enterprise

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Thomas, G.

    1977-03-01

    A representative of the Sierra Club proposes that the United States can at least provide an opportunity for a break in the trend toward nuclear proliferation and may be able to offer the moral and economic persuasion for a worldwide moratorium. The combination of plutonium toxicity and its use in making nuclear explosives, together with the number of countries who have recently entered the nuclear community, indicate an increasing problem in limiting nuclear power to peaceful purposes. The ease with which plutonium can be diverted from power-generating plants into the hands of terrorists and unstable rulers limits the security options.more » The non-proliferation agreements are felt to have created additional problems by making it possible for non-signers of the treaty to have less-stringent safeguards than the signers. The International Atomic Energy Agency is considered to be effective only in a bookkeeping and monitoring capacity, while competition between nuclear suppliers may lead them to relax standards. The author feels that efforts to negotiate voluntary restraints on exporters could offer guarantees of fuel services and other nuclear assistance to those countries agreeing to forego nuclear explosives and reprocessing facilities and accepting safeguards restraints and export restrictions. (DCK)« less

  13. 78 FR 37595 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-21

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Advanced Boiling Water Reactor; Notice of Meeting The ACRS Subcommittee on Advanced Boiling Water Reactor (ABWR) will hold a meeting on July 9, 2013, Room T-2B3, 11545 Rockville Pike, Rockville, Maryland. The meeting will be open to...

  14. 77 FR 36581 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-19

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S. Advanced Pressurized Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Advanced Pressurized Power Reactor (US-APWR) will hold a meeting on July 9-10, 2012, Room T-2B3, 11545...

  15. 76 FR 44964 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-27

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on August 18, 2011, Room T-2B3, 11545 Rockville Pike...

  16. 76 FR 4739 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-26

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR); Notice of Meeting The ACRS Subcommittee on U.S. EPR... 6 and Chapter 15 of the U.S. EPR Safety Evaluation Report (SER) with Open Items. The Subcommittee...

  17. 75 FR 20398 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on AP1000...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-19

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on AP1000; Notice of Meeting The ACRS Subcommittee on the AP1000 will hold a meeting on April 22... Loss of Large Areas due to Fire/Explosions, and by Westinghouse on the subject of Shield Building...

  18. 76 FR 5220 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-28

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant Designs The ACRS Subcommittee on Future Plant Designs will hold a meeting on February 9, 2011, at 11545 Rockville Pike, Room T-2B1, Rockville, Maryland. The entire meeting will be open...

  19. 76 FR 16016 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-22

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant Designs The ACRS Subcommittee on Future Plant Designs will hold a meeting on April 5, 2011, at 11545 Rockville Pike, Room T-2B1, Rockville, Maryland. The entire meeting will be open...

  20. 78 FR 68867 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on US-APWR...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-15

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on US-APWR; Notice of Meeting The ACRS Subcommittee on US-APWR will hold a meeting on November 20... Sections 3.7 and 3.8) of the Safety Evaluation Report (SER) associated with the US-APWR design...

  1. 78 FR 20959 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-08

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR The ACRS Subcommittee on US-APWR will hold a meeting on April 25- 26, 2013, Room T-2B1... 7, ``Instrumentation and Control,'' of the Safety Evaluation Report (SER) associated with the US...

  2. 45 CFR 164.310 - Physical safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 45 Public Welfare 1 2011-10-01 2011-10-01 false Physical safeguards. 164.310 Section 164.310... Information § 164.310 Physical safeguards. A covered entity must, in accordance with § 164.306: (a)(1) Standard: Facility access controls. Implement policies and procedures to limit physical access to its...

  3. 45 CFR 164.310 - Physical safeguards.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 45 Public Welfare 1 2012-10-01 2012-10-01 false Physical safeguards. 164.310 Section 164.310... Information § 164.310 Physical safeguards. A covered entity must, in accordance with § 164.306: (a)(1) Standard: Facility access controls. Implement policies and procedures to limit physical access to its...

  4. 45 CFR 164.310 - Physical safeguards.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 45 Public Welfare 1 2013-10-01 2013-10-01 false Physical safeguards. 164.310 Section 164.310... Information § 164.310 Physical safeguards. A covered entity or business associate must, in accordance with... physical access to its electronic information systems and the facility or facilities in which they are...

  5. 45 CFR 164.310 - Physical safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 45 Public Welfare 1 2010-10-01 2010-10-01 false Physical safeguards. 164.310 Section 164.310... Information § 164.310 Physical safeguards. A covered entity must, in accordance with § 164.306: (a)(1) Standard: Facility access controls. Implement policies and procedures to limit physical access to its...

  6. 45 CFR 164.310 - Physical safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 45 Public Welfare 1 2014-10-01 2014-10-01 false Physical safeguards. 164.310 Section 164.310... Information § 164.310 Physical safeguards. A covered entity or business associate must, in accordance with... physical access to its electronic information systems and the facility or facilities in which they are...

  7. 16 CFR 314.3 - Standards for safeguarding customer information.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Standards for safeguarding customer... OF CONGRESS STANDARDS FOR SAFEGUARDING CUSTOMER INFORMATION § 314.3 Standards for safeguarding customer information. (a) Information security program. You shall develop, implement, and maintain a...

  8. An Assessment of the Attractiveness of Material Associated with a MOX Fuel Cycle from a Safeguards Perspective

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bathke, Charles G; Wallace, Richard K; Ireland, John R

    2009-01-01

    This paper is an extension to earlier studies that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, coextraction, THOREX, and PYROX reprocessing schemes. This study extends the figure of merit (FOM) for evaluating attractiveness to cover a broad range of proliferant State and sub-national group capabilities. This study also considers those materials that will be recycled and burned, possibly multiple times, in LWRs [e.g., plutonium in the form of mixed oxide (MOX) fuel]. The primary conclusion of this study is that all fissile material needs to bemore » rigorously safeguarded to detect diversion by a State and provided the highest levels of physical protection to prevent theft by sub-national groups; no 'silver bullet' has been found that will permit the relaxation of current international safeguards or national physical security protection levels. This series of studies has been performed at the request of the United States Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for nuclear materials in DOE nuclear facilities. The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.« less

  9. AN ASSESSMENT OF THE ATTRACTIVENESS OF MATERIAL ASSOCIATED WITH A MOX FUEL CYCLE FROM A SAFEGUARDS PERSPECTIVE

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bathke, C. G.; Ebbinghaus, B. B.; Sleaford, Brad W.

    2009-07-09

    This paper is an extension to earlier studies [1,2] that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, coextraction, THOREX, and PYROX reprocessing schemes. This study extends the figure of merit (FOM) for evaluating attractiveness to cover a broad range of proliferant State and sub-national group capabilities. This study also considers those materials that will be recycled and burned, possibly multiple times, in LWRs [e.g., plutonium in the form of mixed oxide (MOX) fuel]. The primary conclusion of this study is that all fissile material needs tomore » be rigorously safeguarded to detect diversion by a State and provided the highest levels of physical protection to prevent theft by sub-national groups; no “silver bullet” has been found that will permit the relaxation of current international safeguards or national physical security protection levels. This series of studies has been performed at the request of the United States Department of Energy (DOE) and is based on the calculation of "attractiveness levels" that are expressed in terms consistent with, but normally reserved for nuclear materials in DOE nuclear facilities [3]. The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.« less

  10. Nuclear Security Objectives of an NMAC System

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    West, Rebecca Lynn

    After completing this module, you should be able to: Describe the role of Nuclear Material Accounting and Control (NMAC) in comprehensive nuclear security at a facility; Describe purpose of NMAC; Identify differences between the use of NMAC for IAEA safeguards and for facility nuclear security; List NMAC elements and measures; and Describe process for resolution of irregularities

  11. 77 FR 74696 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on AP-1000...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-17

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on AP-1000; Notice of Meeting The ACRS Subcommittee on AP-1000 will hold a meeting on January 18, 2013, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public...

  12. 77 FR 56240 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on US-APWR...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-12

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on US-APWR; Notice of Meeting The ACRS Subcommittee on US-APWR will hold a meeting on September 20, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public...

  13. Apparatus for safeguarding a radiological source

    DOEpatents

    Bzorgi, Fariborz M

    2014-10-07

    A tamper detector is provided for safeguarding a radiological source that is moved into and out of a storage location through an access porthole for storage and use. The radiological source is presumed to have an associated shipping container approved by the U.S. Nuclear Regulatory Commission for transporting the radiological source. The tamper detector typically includes a network of sealed tubing that spans at least a portion of the access porthole. There is an opening in the network of sealed tubing that is large enough for passage therethrough of the radiological source and small enough to prevent passage therethrough of the associated shipping cask. Generally a gas source connector is provided for establishing a gas pressure in the network of sealed tubing, and a pressure drop sensor is provided for detecting a drop in the gas pressure below a preset value.

  14. 76 FR 7882 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital I&C...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-02-11

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital I&C Systems The ACRS Subcommittee on Digital Instrumentation & Control (DI&C) Systems will hold a meeting on February 23, 2011, Room T-2B3, 11545 Rockville Pike, Rockville, Maryland. The...

  15. 34 CFR 300.150 - SEA implementation of procedural safeguards.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 34 Education 2 2012-07-01 2012-07-01 false SEA implementation of procedural safeguards. 300.150... EDUCATION OF CHILDREN WITH DISABILITIES State Eligibility Sea Responsibility for General Supervision and Implementation of Procedural Safeguards § 300.150 SEA implementation of procedural safeguards. The SEA (and any...

  16. 34 CFR 300.150 - SEA implementation of procedural safeguards.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 34 Education 2 2013-07-01 2013-07-01 false SEA implementation of procedural safeguards. 300.150... EDUCATION OF CHILDREN WITH DISABILITIES State Eligibility Sea Responsibility for General Supervision and Implementation of Procedural Safeguards § 300.150 SEA implementation of procedural safeguards. The SEA (and any...

  17. 34 CFR 300.150 - SEA implementation of procedural safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 34 Education 2 2014-07-01 2013-07-01 true SEA implementation of procedural safeguards. 300.150... EDUCATION OF CHILDREN WITH DISABILITIES State Eligibility Sea Responsibility for General Supervision and Implementation of Procedural Safeguards § 300.150 SEA implementation of procedural safeguards. The SEA (and any...

  18. 34 CFR 300.150 - SEA implementation of procedural safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 34 Education 2 2011-07-01 2010-07-01 true SEA implementation of procedural safeguards. 300.150... EDUCATION OF CHILDREN WITH DISABILITIES State Eligibility Sea Responsibility for General Supervision and Implementation of Procedural Safeguards § 300.150 SEA implementation of procedural safeguards. The SEA (and any...

  19. 34 CFR 300.150 - SEA implementation of procedural safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 34 Education 2 2010-07-01 2010-07-01 false SEA implementation of procedural safeguards. 300.150... EDUCATION OF CHILDREN WITH DISABILITIES State Eligibility Sea Responsibility for General Supervision and Implementation of Procedural Safeguards § 300.150 SEA implementation of procedural safeguards. The SEA (and any...

  20. Safeguards: The past present, and future

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Seaton, M.B.

    1987-07-01

    The non-destructive assay techniques developed at Los Alamos have become a primary means for verification by the IAEA and most important for domestic safeguards. We must challenge our assumptions, e.g., that inventory differences are a valid measure of safeguards performance, that more money is the solution, and the threats are much exaggerated. A human reliability program will be initiated. Material control, accounting, and physical protection need further integration. A serious effort involving scholarships, internships, etc. is needed to attract and motivate young people. Increased emphasis will be placed on designing safeguards into new systems such as laser isotope separation. Finally,more » continuing generous support for the IAEA is most important.« less

  1. 10 CFR Appendix G to Part 73 - Reportable Safeguards Events

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... vulnerability in a safeguard system that could allow unauthorized or undetected access to a protected area... the safeguards event log. (a) Any failure, degradation, or discovered vulnerability in a safeguards...

  2. 77 FR 59994 - Nuclear Fuel Services, Inc., Erwin, TN; Issuance of License Renewal

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-01

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 70-143; NRC-2009-0435] Nuclear Fuel Services, Inc., Erwin, TN; Issuance of License Renewal AGENCY: U.S. Nuclear Regulatory Commission. ACTION: Notice of... Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001...

  3. Keeping Nuclear Materials Secure

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    For 50 years, Los Alamos National Laboratory has been helping to keep nuclear materials secure. We do this by developing instruments and training inspectors that are deployed to other countries to make sure materials such as uranium are being used for peaceful purposes and not diverted for use in weapons. These measures are called “nuclear safeguards,” and they help make the world a safer place.

  4. 75 FR 82094 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-29

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR); Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on January 12, 2011, Room T-2B1, 11545 Rockville Pike...

  5. 78 FR 17945 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-25

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant Designs; Notice of Meeting The ACRS Subcommittee on Future Plant Designs will hold a meeting on April 9, 2013, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public attendance....

  6. 76 FR 64123 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-17

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant Designs; Notice of Meeting The ACRS Subcommittee on Future Plant Designs will hold a meeting on November 2, 2011, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public...

  7. 77 FR 74698 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-17

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant Designs; Notice of Meeting The ACRS Subcommittee on Future Plant Designs will hold a meeting on January 17, 2013, Room T-2B3, 11545 Rockville Pike, Rockville, Maryland. The meeting will be open to public attendance, wit...

  8. 75 FR 51499 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital I&C...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-20

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital I&C Systems The ACRS Subcommittee on Digital Instrumentation and Controls (I&C) Systems...: Wednesday, September 8, 2010--8:30 a.m. until 12 p.m. The Subcommittee will review Digital I&C Interim Staff...

  9. ASME Nuclear Crane Standards for Enhanced Crane Safety and Increased Profit

    NASA Astrophysics Data System (ADS)

    Parkhurst, Stephen N.

    2000-01-01

    The ASME NOG-1 standard, 'Rules for Construction of Overhead and Gantry Cranes', covers top running cranes for nuclear facilities; with the ASME NUM-1 standard, 'Rules for Construction of Cranes, Monorails, and Hoists', covering the single girder, underhung, wall and jib cranes, as well as the monorails and hoists. These two ASME nuclear crane standards provide criteria for designing, inspecting and testing overhead handling equipment with enhanced safety to meet the 'defense-in-depth' approach of the United States Nuclear Regulatory Commission (USNRC) documents NUREG 0554 and NUREG 0612. In addition to providing designs for enhanced safety, the ASME nuclear crane standards provide a basis for purchasing overhead handling equipment with standard safety features, based upon accepted engineering principles, and including performance and environmental parameters specific to nuclear facilities. The ASME NOG-1 and ASME NUM-1 standards not only provide enhanced safety for handling a critical load, but also increase profit by minimizing the possibility of load drops, by reducing cumbersome operating restrictions, and by providing the foundation for a sound licensing position. The ASME nuclear crane standards can also increase profit by providing the designs and information to help ensure that the right standard equipment is purchased. Additionally, the ASME nuclear crane standards can increase profit by providing designs and information to help address current issues, such as the qualification of nuclear plant cranes for making 'planned engineered lifts' for steam generator replacement and decommissioning.

  10. 10 CFR 1.13 - Advisory Committee on Reactor Safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Advisory Committee on Reactor Safeguards. 1.13 Section 1... Headquarters Panels, Boards, and Committees § 1.13 Advisory Committee on Reactor Safeguards. The Advisory Committee on Reactor Safeguards (ACRS) was established by section 29 of the Atomic Energy Act of 1954, as...

  11. 10 CFR 1.13 - Advisory Committee on Reactor Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Advisory Committee on Reactor Safeguards. 1.13 Section 1... Headquarters Panels, Boards, and Committees § 1.13 Advisory Committee on Reactor Safeguards. The Advisory Committee on Reactor Safeguards (ACRS) was established by section 29 of the Atomic Energy Act of 1954, as...

  12. 77 FR 67688 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital I&C...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-13

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital I&C; Notice of Meeting The ACRS Subcommittee on Digital I&C will hold a meeting on November 16, 2012, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open...

  13. Modeling and Simulation for Safeguards and Nonproliferation Workshop

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gilligan, Kimberly V.; Kirk, Bernadette Lugue

    2015-01-01

    The Modeling and Simulation for Safeguards and Nonproliferation Workshop was held December 15–18, 2014, at Oak Ridge National Laboratory. This workshop was made possible by the Next Generation Safeguards Initiative Human Capital Development (NGSI HCD) Program. The idea of the workshop was to move beyond the tried-and-true boot camp training of nonproliferation concepts to spend several days on the unique perspective of applying modeling and simulation (M&S) solutions to safeguards challenges.

  14. Report on {open_quotes}audit of internal controls over special nuclear materials{close_quotes}

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1996-04-01

    The Department of Energy (Department) is responsible for safeguarding a significant amount of plutonium, uranium-233 and enriched uranium - collectively referred to as special nuclear materials - stored in the United States. The Department`s office of Nonproliferation and National Security has overall management cognizance for developing policies for safeguarding these materials, while other Headquarters program offices have {open_quotes}landlord{close_quotes} responsibilities for the sites where the materials are stored, and the Department`s operations and field offices provide onsite management of contractor operations. The Department`s management and operating contractors, under the direction of the Department, safeguard and account for the special nuclear materialmore » stored at Department sites.« less

  15. 32 CFR 635.2 - Safeguarding official information.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 32 National Defense 4 2010-07-01 2010-07-01 true Safeguarding official information. 635.2 Section 635.2 National Defense Department of Defense (Continued) DEPARTMENT OF THE ARMY (CONTINUED) LAW ENFORCEMENT AND CRIMINAL INVESTIGATIONS LAW ENFORCEMENT REPORTING Records Administration § 635.2 Safeguarding official information. (a) Military police...

  16. 7 CFR 352.10 - Inspection; safeguards; disposal.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... facilities for immediate exportation. (x) Any other related factor which should be considered, such as intent...; safeguards; disposal. (a) Inspection and release. Prohibited and restricted products and articles subject to... restricted products and articles under this part shall be subject to such safeguards as may be prescribed in...

  17. 30 CFR 77.1013 - Air drills; safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Air drills; safeguards. 77.1013 Section 77.1013... Control § 77.1013 Air drills; safeguards. Air shall be turned off and bled from the air hoses before hand-held air drills are moved from one working area to another. ...

  18. 30 CFR 77.1013 - Air drills; safeguards.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Air drills; safeguards. 77.1013 Section 77.1013... Control § 77.1013 Air drills; safeguards. Air shall be turned off and bled from the air hoses before hand-held air drills are moved from one working area to another. ...

  19. 30 CFR 77.1013 - Air drills; safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Air drills; safeguards. 77.1013 Section 77.1013... Control § 77.1013 Air drills; safeguards. Air shall be turned off and bled from the air hoses before hand-held air drills are moved from one working area to another. ...

  20. 30 CFR 77.1013 - Air drills; safeguards.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Air drills; safeguards. 77.1013 Section 77.1013... Control § 77.1013 Air drills; safeguards. Air shall be turned off and bled from the air hoses before hand-held air drills are moved from one working area to another. ...

  1. 30 CFR 77.1013 - Air drills; safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Air drills; safeguards. 77.1013 Section 77.1013... Control § 77.1013 Air drills; safeguards. Air shall be turned off and bled from the air hoses before hand-held air drills are moved from one working area to another. ...

  2. Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 3

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Libby, R.A.; Segal, J.E.; Stanbro, W.D.

    1995-08-01

    This document is appendices D-J for the Special Nuclear Materials Cutoff Exercise: Issues and Lessons Learned. Included are discussions of the US IAEA Treaty, safeguard regulations for nuclear materials, issue sheets for the PUREX process, and the LANL follow up activity for reprocessing nuclear materials.

  3. Minor isotope safeguards techniques (MIST): Analysis and visualization of gas centrifuge enrichment plant process data using the MSTAR model

    NASA Astrophysics Data System (ADS)

    Shephard, Adam M.; Thomas, Benjamin R.; Coble, Jamie B.; Wood, Houston G.

    2018-05-01

    This paper presents a development related to the use of minor isotope safeguards techniques (MIST) and the MSTAR cascade model as it relates to the application of international nuclear safeguards at gas centrifuge enrichment plants (GCEPs). The product of this paper is a derivation of the universal and dimensionless MSTAR cascade model. The new model can be used to calculate the minor uranium isotope concentrations in GCEP product and tails streams or to analyze, visualize, and interpret GCEP process data as part of MIST. Applications of the new model include the detection of undeclared feed and withdrawal streams at GCEPs when used in conjunction with UF6 sampling and/or other isotopic measurement techniques.

  4. Safeguardability of the vitrification option for disposal of plutonium

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pillay, K.K.S.

    1996-05-01

    Safeguardability of the vitrification option for plutonium disposition is rather complex and there is no experience base in either domestic or international safeguards for this approach. In the present treaty regime between the US and the states of the former Soviet Union, bilaterial verifications are considered more likely with potential for a third-party verification of safeguards. There are serious technological limitations to applying conventional bulk handling facility safeguards techniques to achieve independent verification of plutonium in borosilicate glass. If vitrification is the final disposition option chosen, maintaining continuity of knowledge of plutonium in glass matrices, especially those containing boron andmore » those spike with high-level wastes or {sup 137}Cs, is beyond the capability of present-day safeguards technologies and nondestructive assay techniques. The alternative to quantitative measurement of fissile content is to maintain continuity of knowledge through a combination of containment and surveillance, which is not the international norm for bulk handling facilities.« less

  5. Performance of a Boron-Coated-Straw-Based HLNCC for International Safeguards Applications

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Simone, Angela T.; Croft, Stephen; McElroy, Robert Dennis

    3He gas has been used in various scientific and security applications for decades, but it is now in short supply. Alternatives to 3He detectors are currently being integrated and tested in neutron coincidence counter designs, of a type which are widely used in nuclear safeguards for nuclear materials assay. A boron-coated-straw-based design, similar to the High-Level Neutron Coincidence Counter-II, was built by Proportional Technologies Inc., and has been tested by the Oak Ridge National Laboratory (ORNL) at both the JRC in Ispra and ORNL. Characterization measurements, along with nondestructive assays of various plutonium samples, have been conducted to determine themore » performance of this coincidence counter replacement in comparison with other similar counters. This paper presents results of these measurements.« less

  6. NUCLEAR NONPROLIFERATION AND SAFETY: Challenges Facing the International Atomic Energy Agency.

    DTIC Science & Technology

    1993-09-01

    safeguards), and the Chernobyl nuclear power plant accident have focused greater attention on nuclear proliferation and the safety of nuclear power... Chernobyl , IAEA has placed increasing emphasis on assisting member states in improving the safety of nuclear power plants. Despite funding shortfalls...report language, GAO has incorporated their comments where appropriate. 2Nuclear Power Safety: Chernobyl Accident Prompted Worldwide Actions but

  7. 42 CFR 431.305 - Types of information to be safeguarded.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 42 Public Health 4 2011-10-01 2011-10-01 false Types of information to be safeguarded. 431.305... Information on Applicants and Recipients § 431.305 Types of information to be safeguarded. (a) The agency must have criteria that govern the types of information about applicants and recipients that are safeguarded...

  8. 5 CFR 293.106 - Safeguarding information about individuals.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Safeguarding information about individuals. 293.106 Section 293.106 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL SERVICE REGULATIONS PERSONNEL RECORDS Basic Policies on Maintenance of Personnel Records § 293.106 Safeguarding...

  9. ASNC upgrade for nuclear material accountancy of ACPF

    NASA Astrophysics Data System (ADS)

    Seo, Hee; Ahn, Seong-Kyu; Lee, Chaehun; Oh, Jong-Myeong; Yoon, Seonkwang

    2018-02-01

    A safeguards neutron coincidence counter for nuclear material accountancy of the Advanced spent-fuel Conditioning Process Facility (ACPF), known as the ACP Safeguards Neutron Counter (ASNC), was upgraded to improve its remote-handling and maintenance capabilities. Based on the results of the previous design study, the neutron counter was completely rebuilt, and various detector parameters for neutron coincidence counting (i.e., high-voltage plateau, efficiency profile, dead time, die-away time, gate length, doubles gate fraction, and stability) were experimentally determined. The measurement data showed good agreement with the MCNP simulation results. To the best of the authors' knowledge, the ASNC is the only safeguards neutron coincidence counter in the world that is installed and operated in a hot-cell. The final goals to be achieved were (1) to evaluate the uncertainty level of the ASNC in nuclear material accountancy of the process materials of the oxide-reduction process for spent fuels and (2) to evaluate the applicability of the neutron coincidence counting technique within a strong radiation field (e.g., in a hot-cell environment).

  10. Decommissioning: Nuclear Power's Missing Link. Worldwatch Paper 69.

    ERIC Educational Resources Information Center

    Pollock, Cynthia

    The processes and associated dilemmas of nuclear power plant decommissioning are reviewed in this publication. Decommissioning involves the clearing up and disposal of a retired nuclear plant and its equipment of such a way as to safeguard the public from the dangers of radioactivity. Related problem areas are identified and include: (1) closure…

  11. 10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

  12. 10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

  13. 10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

  14. 10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

  15. 10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

  16. Health Information Security in Hospitals: the Application of Security Safeguards.

    PubMed

    Mehraeen, Esmaeil; Ayatollahi, Haleh; Ahmadi, Maryam

    2016-02-01

    A hospital information system has potentials to improve the accessibility of clinical information and the quality of health care. However, the use of this system has resulted in new challenges, such as concerns over health information security. This paper aims to assess the status of information security in terms of administrative, technical and physical safeguards in the university hospitals. This was a survey study in which the participants were information technology (IT) managers (n=36) who worked in the hospitals affiliated to the top ranked medical universities (university A and university B). Data were collected using a questionnaire. The content validity of the questionnaire was examined by the experts and the reliability of the questionnaire was determined using Cronbach's coefficient alpha (α=0.75). The results showed that the administrative safeguards were arranged at a medium level. In terms of the technical safeguards and the physical safeguards, the IT managers rated them at a strong level. According to the results, among three types of security safeguards, the administrative safeguards were assessed at the medium level. To improve it, developing security policies, implementing access control models and training users are recommended.

  17. 42 CFR 438.58 - Conflict of interest safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false Conflict of interest safeguards. 438.58 Section 438... (CONTINUED) MEDICAL ASSISTANCE PROGRAMS MANAGED CARE State Responsibilities § 438.58 Conflict of interest... safeguards against conflict of interest on the part of State and local officers and employees and agents of...

  18. 10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

  19. 10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

  20. 10 CFR 76.113 - Formula quantities of strategic special nuclear material-Category I.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Formula quantities of strategic special nuclear material-Category I. 76.113 Section 76.113 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.113 Formula quantities of strategic special nuclear material...

  1. 10 CFR 76.113 - Formula quantities of strategic special nuclear material-Category I.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Formula quantities of strategic special nuclear material-Category I. 76.113 Section 76.113 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.113 Formula quantities of strategic special nuclear material...

  2. 10 CFR 76.113 - Formula quantities of strategic special nuclear material-Category I.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Formula quantities of strategic special nuclear material-Category I. 76.113 Section 76.113 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.113 Formula quantities of strategic special nuclear material...

  3. 10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

  4. 10 CFR 76.113 - Formula quantities of strategic special nuclear material-Category I.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Formula quantities of strategic special nuclear material-Category I. 76.113 Section 76.113 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.113 Formula quantities of strategic special nuclear material...

  5. 10 CFR 76.113 - Formula quantities of strategic special nuclear material-Category I.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Formula quantities of strategic special nuclear material-Category I. 76.113 Section 76.113 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.113 Formula quantities of strategic special nuclear material...

  6. 10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

  7. 10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Eipeldauer, Mary D; Shelander Jr, Bruce R

    2012-01-01

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

  9. Integrative Curriculum Development in Nuclear Education and Research Vertical Enhancement Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Egarievwe, Stephen U.; Jow, Julius O.; Edwards, Matthew E.

    Using a vertical education enhancement model, a Nuclear Education and Research Vertical Enhancement (NERVE) program was developed. The NERVE program is aimed at developing nuclear engineering education and research to 1) enhance skilled workforce development in disciplines relevant to nuclear power, national security and medical physics, and 2) increase the number of students and faculty from underrepresented groups (women and minorities) in fields related to the nuclear industry. The program uses multi-track training activities that vertically cut across the several education domains: undergraduate degree programs, graduate schools, and post-doctoral training. In this paper, we present the results of an integrativemore » curriculum development in the NERVE program. The curriculum development began with nuclear content infusion into existing science, engineering and technology courses. The second step involved the development of nuclear engineering courses: 1) Introduction to Nuclear Engineering, 2) Nuclear Engineering I, and 2) Nuclear Engineering II. The third step is the establishment of nuclear engineering concentrations in two engineering degree programs: 1) electrical engineering, and 2) mechanical engineering. A major outcome of the NERVE program is a collaborative infrastructure that uses laboratory work, internships at nuclear facilities, on-campus research, and mentoring in collaboration with industry and government partners to provide hands-on training for students. The major activities of the research and education collaborations include: - One-week spring training workshop at Brookhaven National Laboratory: The one-week training and workshop is used to enhance research collaborations and train faculty and students on user facilities/equipment at Brookhaven National Laboratory, and for summer research internships. Participants included students, faculty members at Alabama A and M University and research collaborators at BNL. The activities include 1

  10. 10 CFR 72.78 - Nuclear material transaction reports.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... writing to the U.S. Nuclear Regulatory Commission, Division of Fuel Cycle Safety and Safeguards... instructions no later than the close of business the next working day. Each licensee who receives the material...

  11. 30 CFR 77.1008 - Relocation of drills; safeguards.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Relocation of drills; safeguards. 77.1008... COAL MINES Ground Control § 77.1008 Relocation of drills; safeguards. (a) When a drill is being moved from one drilling area to another, drill steel, tools, and other equipment shall be secured and the...

  12. 30 CFR 77.1008 - Relocation of drills; safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Relocation of drills; safeguards. 77.1008... COAL MINES Ground Control § 77.1008 Relocation of drills; safeguards. (a) When a drill is being moved from one drilling area to another, drill steel, tools, and other equipment shall be secured and the...

  13. 30 CFR 77.1008 - Relocation of drills; safeguards.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Relocation of drills; safeguards. 77.1008... COAL MINES Ground Control § 77.1008 Relocation of drills; safeguards. (a) When a drill is being moved from one drilling area to another, drill steel, tools, and other equipment shall be secured and the...

  14. 30 CFR 77.1008 - Relocation of drills; safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Relocation of drills; safeguards. 77.1008... COAL MINES Ground Control § 77.1008 Relocation of drills; safeguards. (a) When a drill is being moved from one drilling area to another, drill steel, tools, and other equipment shall be secured and the...

  15. Next Generation Safeguards Initiative research to determine the Pu mass in spent fuel assemblies: Purpose, approach, constraints, implementation, and calibration

    NASA Astrophysics Data System (ADS)

    Tobin, S. J.; Menlove, H. O.; Swinhoe, M. T.; Schear, M. A.

    2011-10-01

    The Next Generation Safeguards Initiative (NGSI) of the U.S. Department of Energy has funded a multi-lab/multi-university collaboration to quantify the plutonium mass in spent nuclear fuel assemblies and to detect the diversion of pins from them. The goal of this research effort is to quantify the capability of various non-destructive assay (NDA) technologies as well as to train a future generation of safeguards practitioners. This research is "technology driven" in the sense that we will quantify the capabilities of a wide range of safeguards technologies of interest to regulators and policy makers; a key benefit to this approach is that the techniques are being tested in a unified manner. When the results of the Monte Carlo modeling are evaluated and integrated, practical constraints are part of defining the potential context in which a given technology might be applied. This paper organizes the commercial spent fuel safeguard needs into four facility types in order to identify any constraints on the NDA system design. These four facility types are the following: future reprocessing plants, current reprocessing plants, once-through spent fuel repositories, and any other sites that store individual spent fuel assemblies (reactor sites are the most common facility type in this category). Dry storage is not of interest since individual assemblies are not accessible. This paper will overview the purpose and approach of the NGSI spent fuel effort and describe the constraints inherent in commercial fuel facilities. It will conclude by discussing implementation and calibration of measurement systems. This report will also provide some motivation for considering a couple of other safeguards concepts (base measurement and fingerprinting) that might meet the safeguards need but not require the determination of plutonium mass.

  16. Safeguards Approaches for Black Box Processes or Facilities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Diaz-Marcano, Helly; Gitau, Ernest TN; Hockert, John

    2013-09-25

    The objective of this study is to determine whether a safeguards approach can be developed for “black box” processes or facilities. These are facilities where a State or operator may limit IAEA access to specific processes or portions of a facility; in other cases, the IAEA may be prohibited access to the entire facility. The determination of whether a black box process or facility is safeguardable is dependent upon the details of the process type, design, and layout; the specific limitations on inspector access; and the restrictions placed upon the design information that can be provided to the IAEA. Thismore » analysis identified the necessary conditions for safeguardability of black box processes and facilities.« less

  17. Overview of nuclear energy: Present and projected use

    NASA Astrophysics Data System (ADS)

    Stanculescu, Alexander

    2012-06-01

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

  18. 10 CFR 73.71 - Reporting of safeguards events.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Reporting of safeguards events. 73.71 Section 73.71 Energy... § 73.71 Reporting of safeguards events. (a)(1) Each licensee subject to the provisions of §§ 73.25, 73... revised information. Each licensee shall maintain a copy of the written report of an event submitted under...

  19. 10 CFR 73.71 - Reporting of safeguards events.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Reporting of safeguards events. 73.71 Section 73.71 Energy... § 73.71 Reporting of safeguards events. (a)(1) Each licensee subject to the provisions of §§ 73.25, 73... revised information. Each licensee shall maintain a copy of the written report of an event submitted under...

  20. 10 CFR 73.71 - Reporting of safeguards events.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Reporting of safeguards events. 73.71 Section 73.71 Energy... § 73.71 Reporting of safeguards events. (a)(1) Each licensee subject to the provisions of §§ 73.25, 73... revised information. Each licensee shall maintain a copy of the written report of an event submitted under...

  1. Secure Video Surveillance System (SVSS) for unannounced safeguards inspections.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Galdoz, Erwin G.; Pinkalla, Mark

    2010-09-01

    The Secure Video Surveillance System (SVSS) is a collaborative effort between the U.S. Department of Energy (DOE), Sandia National Laboratories (SNL), and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC). The joint project addresses specific requirements of redundant surveillance systems installed in two South American nuclear facilities as a tool to support unannounced inspections conducted by ABACC and the International Atomic Energy Agency (IAEA). The surveillance covers the critical time (as much as a few hours) between the notification of an inspection and the access of inspectors to the location in facility where surveillance equipment is installed.more » ABACC and the IAEA currently use the EURATOM Multiple Optical Surveillance System (EMOSS). This outdated system is no longer available or supported by the manufacturer. The current EMOSS system has met the project objective; however, the lack of available replacement parts and system support has made this system unsustainable and has increased the risk of an inoperable system. A new system that utilizes current technology and is maintainable is required to replace the aging EMOSS system. ABACC intends to replace one of the existing ABACC EMOSS systems by the Secure Video Surveillance System. SVSS utilizes commercial off-the shelf (COTS) technologies for all individual components. Sandia National Laboratories supported the system design for SVSS to meet Safeguards requirements, i.e. tamper indication, data authentication, etc. The SVSS consists of two video surveillance cameras linked securely to a data collection unit. The collection unit is capable of retaining historical surveillance data for at least three hours with picture intervals as short as 1sec. Images in .jpg format are available to inspectors using various software review tools. SNL has delivered two SVSS systems for test and evaluation at the ABACC Safeguards Laboratory. An additional 'proto-type' system

  2. 10 CFR 2.103 - Action on applications for byproduct, source, special nuclear material, facility and operator...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... nuclear material, facility and operator licenses. (a) If the Director, Office of Nuclear Reactor... repository operations area under parts 60 or 63 of this chapter, the Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear Material Safety and Safeguards, or...

  3. 10 CFR 2.103 - Action on applications for byproduct, source, special nuclear material, facility and operator...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... nuclear material, facility and operator licenses. (a) If the Director, Office of Nuclear Reactor... repository operations area under parts 60 or 63 of this chapter, the Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear Material Safety and Safeguards, or...

  4. Using Deep Learning Algorithm to Enhance Image-review Software for Surveillance Cameras

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cui, Yonggang; Thomas, Maikael A.

    We propose the development of proven deep learning algorithms to flag objects and events of interest in Next Generation Surveillance System (NGSS) surveillance to make IAEA image review more efficient. Video surveillance is one of the core monitoring technologies used by the IAEA Department of Safeguards when implementing safeguards at nuclear facilities worldwide. The current image review software GARS has limited automated functions, such as scene-change detection, black image detection and missing scene analysis, but struggles with highly cluttered backgrounds. A cutting-edge algorithm to be developed in this project will enable efficient and effective searches in images and video streamsmore » by identifying and tracking safeguards relevant objects and detect anomalies in their vicinity. In this project, we will develop the algorithm, test it with the IAEA surveillance cameras and data sets collected at simulated nuclear facilities at BNL and SNL, and implement it in a software program for potential integration into the IAEA’s IRAP (Integrated Review and Analysis Program).« less

  5. 5 CFR 293.107 - Special safeguards for automated records.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Special safeguards for automated records. 293.107 Section 293.107 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL SERVICE REGULATIONS PERSONNEL RECORDS Basic Policies on Maintenance of Personnel Records § 293.107 Special safeguards...

  6. Routine inspection effort required for verification of a nuclear material production cutoff convention

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dougherty, D.; Fainberg, A.; Sanborn, J.

    On 27 September 1993, President Clinton proposed {open_quotes}... a multilateral convention prohibiting the production of highly enriched uranium or plutonium for nuclear explosives purposes or outside of international safeguards.{close_quotes} The UN General Assembly subsequently adopted a resolution recommending negotiation of a non-discriminatory, multilateral, and internationally and effectively verifiable treaty (hereinafter referred to as {open_quotes}the Cutoff Convention{close_quotes}) banning the production of fissile material for nuclear weapons. The matter is now on the agenda of the Conference on Disarmament, although not yet under negotiation. This accord would, in effect, place all fissile material (defined as highly enriched uranium and plutonium) produced aftermore » entry into force (EIF) of the accord under international safeguards. {open_quotes}Production{close_quotes} would mean separation of the material in question from radioactive fission products, as in spent fuel reprocessing, or enrichment of uranium above the 20% level, which defines highly enriched uranium (HEU). Facilities where such production could occur would be safeguarded to verify that either such production is not occurring or that all material produced at these facilities is maintained under safeguards.« less

  7. Safeguard monitoring of direct electrolytic reduction

    NASA Astrophysics Data System (ADS)

    Jurovitzki, Abraham L.

    Nuclear power is regaining global prominence as a sustainable energy source as the world faces the consequences of depending on limited fossil based, CO2 emitting fuels. A key component to achieving this sustainability is to implement a closed nuclear fuel cycle. Without achieving this goal, a relatively small fraction of the energy value in nuclear fuel is actually utilized. This involves recycling of spent nuclear fuel (SNF)---separating fissile actinides from waste products and using them to fabricate fresh fuel. Pyroprocessing is a viable option being developed for this purpose with a host of benefits compared to other recycling options, such as PUREX. Notably, pyroprocessing is ill suited to separate pure plutonium from spent fuel and thus has non-proliferation benefits. Pyroprocessing involves high temperature electrochemical and chemical processing of SNF in a molten salt electrolyte. During this batch process, several intermediate and final streams are produced that contain radioactive material. While pyroprocessing is ineffective at separating pure plutonium, there are various process misuse scenarios that could result in diversion of impure plutonium into one or more of these streams. This is a proliferation risk that should be addressed with innovative safeguards technology. One approach to meeting this challenge is to develop real time monitoring techniques that can be implemented in the hot cells and coupled with the various unit operations involved with pyroprocessing. Current state of the art monitoring techniques involve external chemical assaying which requires sample removal from these unit operations. These methods do not meet International Atomic Energy Agency's (IAEA) timeliness requirements. In this work, a number of monitoring techniques were assessed for their viability as online monitoring tools. A hypothetical diversion scenario for the direct electrolytic reduction process was experimentally verified (using Nd2O3 as a surrogate for PuO2

  8. 5 CFR 293.107 - Special safeguards for automated records.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... for automated records. (a) In addition to following the security requirements of § 293.106 of this... security safeguards for data about individuals in automated records, including input and output documents, reports, punched cards, magnetic tapes, disks, and on-line computer storage. The safeguards must be in...

  9. 5 CFR 293.107 - Special safeguards for automated records.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... for automated records. (a) In addition to following the security requirements of § 293.106 of this... security safeguards for data about individuals in automated records, including input and output documents, reports, punched cards, magnetic tapes, disks, and on-line computer storage. The safeguards must be in...

  10. 5 CFR 293.107 - Special safeguards for automated records.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... for automated records. (a) In addition to following the security requirements of § 293.106 of this... security safeguards for data about individuals in automated records, including input and output documents, reports, punched cards, magnetic tapes, disks, and on-line computer storage. The safeguards must be in...

  11. 5 CFR 293.107 - Special safeguards for automated records.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... for automated records. (a) In addition to following the security requirements of § 293.106 of this... security safeguards for data about individuals in automated records, including input and output documents, reports, punched cards, magnetic tapes, disks, and on-line computer storage. The safeguards must be in...

  12. NR4A nuclear receptors support memory enhancement by histone deacetylase inhibitors

    PubMed Central

    Hawk, Joshua D.; Bookout, Angie L.; Poplawski, Shane G.; Bridi, Morgan; Rao, Allison J.; Sulewski, Michael E.; Kroener, Brian T.; Manglesdorf, David J.; Abel, Ted

    2012-01-01

    The formation of a long-lasting memory requires a transcription-dependent consolidation period that converts a short-term memory into a long-term memory. Nuclear receptors compose a class of transcription factors that regulate diverse biological processes, and several nuclear receptors have been implicated in memory formation. Here, we examined the potential contribution of nuclear receptors to memory consolidation by measuring the expression of all 49 murine nuclear receptors after learning. We identified 13 nuclear receptors with increased expression after learning, including all 3 members of the Nr4a subfamily. These CREB-regulated Nr4a genes encode ligand-independent “orphan” nuclear receptors. We found that blocking NR4A activity in memory-supporting brain regions impaired long-term memory but did not impact short-term memory in mice. Further, expression of Nr4a genes increased following the memory-enhancing effects of histone deacetylase (HDAC) inhibitors. Blocking NR4A signaling interfered with the ability of HDAC inhibitors to enhance memory. These results demonstrate that the Nr4a gene family contributes to memory formation and is a promising target for improving cognitive function. PMID:22996661

  13. 75 FR 2163 - Constellation Energy; Notice of Docketing of Special Nuclear Material License SNM-2505 Amendment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-14

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 72-8; NRC-2010-0011] Constellation Energy; Notice of... Independent Spent Fuel Storage Installation AGENCY: Nuclear Regulatory Commission. ACTION: Notice of license..., Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards, U.S...

  14. 75 FR 25301 - Nuclear Fuel Services, Inc.; Environmental Assessment and Finding of No Significant Impact for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-07

    ... procedures for storing and handling radioactive materials. Thus, the impacts under the ``no action... of Special Nuclear Material AGENCY: Nuclear Regulatory Commission. ACTION: Environmental Assessment... Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Mail Stop EBB-2C40M, Rockville, MD...

  15. Safeguards Knowledge Management & Retention at U.S. National Laboratories.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Haddal, Risa; Jones, Rebecca; Bersell, Bridget

    In 2017, four U.S. National Laboratories collaborated on behalf of DOE/NNSA to explore the safeguards knowledge retention problem, identify possible approaches, and develop a strategy to address it. The one-year effort consisted of four primary tasks. First, the project sought to identify critical safeguards information at risk of loss. Second, a survey and workshop were conducted to assess nine U.S. National Laboratories' efforts to determine current safeguards knowledge retention practices and challenges, and identify best practices. Third, specific tools were developed to identify and predict critical safeguards knowledge gaps and how best to recruit in order to fill those gaps.more » Finally, based on findings from the first three tasks and research on other organizational approaches to address similar issues, a strategy was developed on potential knowledge retention methods, customized HR policies, and best practices that could be implemented across the National Laboratory Complex.« less

  16. Assessing State Nuclear Weapons Proliferation: Using Bayesian Network Analysis of Social Factors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Coles, Garill A.; Brothers, Alan J.; Olson, Jarrod

    A Bayesian network (BN) model of social factors can support proliferation assessments by estimating the likelihood that a state will pursue a nuclear weapon. Social factors including political, economic, nuclear capability, security, and national identity and psychology factors may play as important a role in whether a State pursues nuclear weapons as more physical factors. This paper will show how using Bayesian reasoning on a generic case of a would-be proliferator State can be used to combine evidence that supports proliferation assessment. Theories and analysis by political scientists can be leveraged in a quantitative and transparent way to indicate proliferationmore » risk. BN models facilitate diagnosis and inference in a probabilistic environment by using a network of nodes and acyclic directed arcs between the nodes whose connections, or absence of, indicate probabilistic relevance, or independence. We propose a BN model that would use information from both traditional safeguards and the strengthened safeguards associated with the Additional Protocol to indicate countries with a high risk of proliferating nuclear weapons. This model could be used in a variety of applications such a prioritization tool and as a component of state safeguards evaluations. This paper will discuss the benefits of BN reasoning, the development of Pacific Northwest National Laboratory’s (PNNL) BN state proliferation model and how it could be employed as an analytical tool.« less

  17. 48 CFR 52.239-1 - Privacy or Security Safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 48 Federal Acquisition Regulations System 2 2014-10-01 2014-10-01 false Privacy or Security....239-1 Privacy or Security Safeguards. As prescribed in 39.107, insert a clause substantially the same as the following: Privacy or Security Safeguards (AUG 1996) (a) The Contractor shall not publish or...

  18. 48 CFR 52.239-1 - Privacy or Security Safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 48 Federal Acquisition Regulations System 2 2011-10-01 2011-10-01 false Privacy or Security....239-1 Privacy or Security Safeguards. As prescribed in 39.107, insert a clause substantially the same as the following: Privacy or Security Safeguards (AUG 1996) (a) The Contractor shall not publish or...

  19. 48 CFR 52.239-1 - Privacy or Security Safeguards.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 48 Federal Acquisition Regulations System 2 2012-10-01 2012-10-01 false Privacy or Security....239-1 Privacy or Security Safeguards. As prescribed in 39.107, insert a clause substantially the same as the following: Privacy or Security Safeguards (AUG 1996) (a) The Contractor shall not publish or...

  20. 48 CFR 52.239-1 - Privacy or Security Safeguards.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 48 Federal Acquisition Regulations System 2 2013-10-01 2013-10-01 false Privacy or Security....239-1 Privacy or Security Safeguards. As prescribed in 39.107, insert a clause substantially the same as the following: Privacy or Security Safeguards (AUG 1996) (a) The Contractor shall not publish or...

  1. 48 CFR 52.239-1 - Privacy or Security Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Privacy or Security....239-1 Privacy or Security Safeguards. As prescribed in 39.107, insert a clause substantially the same as the following: Privacy or Security Safeguards (AUG 1996) (a) The Contractor shall not publish or...

  2. 17 CFR 37.1400 - Core Principle 14-System safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... procedures, and automated systems, that: (1) Are reliable and secure; and (2) Have adequate scalable capacity... 17 Commodity and Securities Exchanges 1 2014-04-01 2014-04-01 false Core Principle 14-System... SWAP EXECUTION FACILITIES System Safeguards § 37.1400 Core Principle 14—System safeguards. The swap...

  3. University-level Non-proliferation and Safeguards Education and Human Capital Development Activities at Brookhaven National Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bachner K. M.; Pepper, S.; Gomera, J.

    BNL has offered Nuclear Nonproliferation, Safeguards and Security in the 21st Century,? referred to as NNSS, every year since 2009 for graduate students in technical and policy fields related to nuclear safeguards and nonproliferation. The course focuses on relevant policy issues, in addition to technical components, and is part of a larger NGSI short course initiative that includes separate courses that are delivered at three other national laboratories and NNSA headquarters. [SCHOLZ and ROSENTHAL] The course includes lectures from esteemed nonproliferation experts, tours of various BNL facilities and laboratories, and in-field and table-top exercises on both technical and policy subjects.more » Topics include the history of the Treaty on the Non-proliferation of Nuclear Weapons (NPT) and other relevant treaties, the history of and advances in international nuclear safeguards, current relevant political situations in countries such as Iran, Iraq, and the Democratic Peoples? Republic of Korea (DPRK), nuclear science and technology, instrumentation and techniques used for verification activities, and associated research and development. The students conduct a mock Design Information Verification (DIV) at BNL?s decommissioned Medical Research Reactor. The capstone of the course includes a series of student presentations in which students act as policy advisors and provide recommendations in response to scenarios involving a current nonproliferation related event that are prepared by the course organizers. ?The course is open to domestic and foreign students, and caters to students in, entering, or recently having completed graduate school. Interested students must complete an application and provide a resume and a statement describing their interest in the course. Eighteen to 22 students attend annually; 165 students have completed the course to date. A stipend helps to defray students? travel and subsistence expenses. In 2015, the course was shortened from three

  4. "Capacity is key": investigating new legal provisions in England and Wales for adult safeguarding.

    PubMed

    Manthorpe, Jill; Samsi, Kritika; Rapaport, Joan

    2013-01-01

    This study aimed to investigate the views and experiences of local Safeguarding Adults Coordinators of the newly implemented Mental Capacity Act 2005. This legislation in England and Wales has both protection and empowerment as its dual goals. Fifteen Safeguarding Adults Coordinators (SACs) employed by local authorities in the London area were interviewed in 2008, and again 2 years later. A total of 12 SACs participated in the 2010 follow-up interviews. The findings are reported here, covering experiences and views on the implementation and uses of the Act. There was overwhelming support for the Act as enhancing people's rights to a life free from abuse, of providing a framework for the assessment of decision-making capacity, and of assisting practitioners in reducing risks and responding to abusive situations. Participants urged better publicity about the Act, more detailed guidance on the new offenses, and greater attention to the interactions with other government policy goals.

  5. Cosmic Ray Muon Imaging of Spent Nuclear Fuel in Dry Storage Casks

    DOE PAGES

    Durham, J. Matthew; Guardincerri, Elena; Morris, Christopher L.; ...

    2016-04-29

    In this paper, cosmic ray muon radiography has been used to identify the absence of spent nuclear fuel bundles inside a sealed dry storage cask. The large amounts of shielding that dry storage casks use to contain radiation from the highly radioactive contents impedes typical imaging methods, but the penetrating nature of cosmic ray muons allows them to be used as an effective radiographic probe. This technique was able to successfully identify missing fuel bundles inside a sealed Westinghouse MC-10 cask. This method of fuel cask verification may prove useful for international nuclear safeguards inspectors. Finally, muon radiography may findmore » other safety and security or safeguards applications, such as arms control verification.« less

  6. Comprehensive Glossary of Nuclear Science

    NASA Astrophysics Data System (ADS)

    Langlands, Tracy; Stone, Craig; Meyer, Richard

    2001-10-01

    We have developed a comprehensive glossary of terms covering the broad fields of nuclear and related areas of science. The glossary has been constructed with two sections. A primary section consists of over 6,000 terms covering the fields of nuclear and high energy physics, nuclear chemistry, radiochemistry, health physics, astrophysics, materials science, analytical science, environmental science, nuclear medicine, nuclear engineering, nuclear instrumentation, nuclear weapons, and nuclear safeguards. Approximately 1,500 terms of specific focus on military and nuclear weapons testing define the second section. The glossary is currently larger than many published glossaries and dictionaries covering the entire field of physics. Glossary terms have been defined using an extensive collection of current and historical publications. Historical texts extend back into the 1800's, the early days of atomic physics. The glossary has been developed both as a software application and as a hard copy document.

  7. Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response

    DOE PAGES

    Hu, Jianwei; Gauld, Ian C.

    2014-12-01

    The U.S. Department of Energy’s Next Generation Safeguards Initiative Spent Fuel (NGSI-SF) project is nearing the final phase of developing several advanced nondestructive assay (NDA) instruments designed to measure spent nuclear fuel assemblies for the purpose of improving nuclear safeguards. Current efforts are focusing on calibrating several of these instruments with spent fuel assemblies at two international spent fuel facilities. Modelling and simulation is expected to play an important role in predicting nuclide compositions, neutron and gamma source terms, and instrument responses in order to inform the instrument calibration procedures. As part of NGSI-SF project, this work was carried outmore » to assess the impacts of uncertainties in the nuclear data used in the calculations of spent fuel content, radiation emissions and instrument responses. Nuclear data is an essential part of nuclear fuel burnup and decay codes and nuclear transport codes. Such codes are routinely used for analysis of spent fuel and NDA safeguards instruments. Hence, the uncertainties existing in the nuclear data used in these codes affect the accuracies of such analysis. In addition, nuclear data uncertainties represent the limiting (smallest) uncertainties that can be expected from nuclear code predictions, and therefore define the highest attainable accuracy of the NDA instrument. This work studies the impacts of nuclear data uncertainties on calculated spent fuel nuclide inventories and the associated NDA instrument response. Recently developed methods within the SCALE code system are applied in this study. The Californium Interrogation with Prompt Neutron instrument was selected to illustrate the impact of these uncertainties on NDA instrument response.« less

  8. Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hu, Jianwei; Gauld, Ian C.

    The U.S. Department of Energy’s Next Generation Safeguards Initiative Spent Fuel (NGSI-SF) project is nearing the final phase of developing several advanced nondestructive assay (NDA) instruments designed to measure spent nuclear fuel assemblies for the purpose of improving nuclear safeguards. Current efforts are focusing on calibrating several of these instruments with spent fuel assemblies at two international spent fuel facilities. Modelling and simulation is expected to play an important role in predicting nuclide compositions, neutron and gamma source terms, and instrument responses in order to inform the instrument calibration procedures. As part of NGSI-SF project, this work was carried outmore » to assess the impacts of uncertainties in the nuclear data used in the calculations of spent fuel content, radiation emissions and instrument responses. Nuclear data is an essential part of nuclear fuel burnup and decay codes and nuclear transport codes. Such codes are routinely used for analysis of spent fuel and NDA safeguards instruments. Hence, the uncertainties existing in the nuclear data used in these codes affect the accuracies of such analysis. In addition, nuclear data uncertainties represent the limiting (smallest) uncertainties that can be expected from nuclear code predictions, and therefore define the highest attainable accuracy of the NDA instrument. This work studies the impacts of nuclear data uncertainties on calculated spent fuel nuclide inventories and the associated NDA instrument response. Recently developed methods within the SCALE code system are applied in this study. The Californium Interrogation with Prompt Neutron instrument was selected to illustrate the impact of these uncertainties on NDA instrument response.« less

  9. Experimental signature of collective enhancement in nuclear level density

    NASA Astrophysics Data System (ADS)

    Pandit, Deepak; Bhattacharya, Srijit; Mondal, Debasish; Roy, Pratap; Banerjee, K.; Mukhopadhyay, S.; Pal, Surajit; De, A.; Dey, Balaram; Banerjee, S. R.

    2018-04-01

    We present a probable experimental signature of collective enhancement in the nuclear level density (NLD) by measuring the neutron and the giant dipole resonance (GDR) γ rays emitted from the rare-earth 169Tm compound nucleus populated at 26.1 MeV excitation energy. An enhanced yield is observed in both neutron and γ -ray spectra corresponding to the same excitation energy in the daughter nuclei. The enhancement could only be reproduced by including a collective enhancement factor in the Fermi gas model of NLD to explain the neutron and GDR spectra simultaneously. The experimental results show that the relative enhancement factor is of the order of 10 and the fadeout occurs at ˜14 MeV excitation energy, much before the commonly accepted transition from deformed to spherical shape. We also explain how the collective enhancement contribution changes the inverse level density parameter k from 8 to 9.5 MeV observed recently in several deformed nuclei.

  10. Verification of Spent Nuclear Fuel in Sealed Dry Storage Casks via Measurements of Cosmic-Ray Muon Scattering

    NASA Astrophysics Data System (ADS)

    Durham, J. M.; Poulson, D.; Bacon, J.; Chichester, D. L.; Guardincerri, E.; Morris, C. L.; Plaud-Ramos, K.; Schwendiman, W.; Tolman, J. D.; Winston, P.

    2018-04-01

    Most of the plutonium in the world resides inside spent nuclear reactor fuel rods. This high-level radioactive waste is commonly held in long-term storage within large, heavily shielded casks. Currently, international nuclear safeguards inspectors have no stand-alone method of verifying the amount of reactor fuel stored within a sealed cask. Here we demonstrate experimentally that measurements of the scattering angles of cosmic-ray muons, which pass through a storage cask, can be used to determine if spent fuel assemblies are missing without opening the cask. This application of technology and methods commonly used in high-energy particle physics provides a potential solution to this long-standing problem in international nuclear safeguards.

  11. 14 CFR 1212.605 - Safeguarding information in systems of records.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 14 Aeronautics and Space 5 2011-01-01 2010-01-01 true Safeguarding information in systems of records. 1212.605 Section 1212.605 Aeronautics and Space NATIONAL AERONAUTICS AND SPACE ADMINISTRATION PRIVACY ACT-NASA REGULATIONS Instructions for NASA Employees § 1212.605 Safeguarding information in...

  12. Bishops and the bomb: the morality of nuclear deterrrence

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lawler, P.F.

    1982-01-01

    Roman Catholic bishops in the US are now discussing a Pastoral Letter on the morality of nuclear defense. Since a nuclear war would be an unprecedented horror, nations have a moral obligation to make such a war less likely. That, in turn, implies a moral obligation to think clearly and cogently on the best strategies for nuclear defense. The author argues that the US has a moral obligation to safeguard peace with a revised, strengthened nuclear deterrent. He contends that ideology and irresponsible international behavior, not weapons, cause war.

  13. 10 CFR 150.17a - Compliance with requirements of US/IAEA Safeguards Agreement.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Compliance with requirements of US/IAEA Safeguards... Authority in Agreement States § 150.17a Compliance with requirements of US/IAEA Safeguards Agreement. (a... shall take other action as may be necessary to implement the US/IAEA Safeguards Agreement, as described...

  14. 10 CFR 150.17a - Compliance with requirements of US/IAEA Safeguards Agreement.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Compliance with requirements of US/IAEA Safeguards... Authority in Agreement States § 150.17a Compliance with requirements of US/IAEA Safeguards Agreement. (a... shall take other action as may be necessary to implement the US/IAEA Safeguards Agreement, as described...

  15. 22 CFR 9.13 - Safeguarding.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... Relations DEPARTMENT OF STATE GENERAL SECURITY INFORMATION REGULATIONS § 9.13 Safeguarding. Specific controls on the use, processing, storage, reproduction, and transmittal of classified information within the Department to provide protection for such information and to prevent access by unauthorized...

  16. 22 CFR 9.13 - Safeguarding.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... Relations DEPARTMENT OF STATE GENERAL SECURITY INFORMATION REGULATIONS § 9.13 Safeguarding. Specific controls on the use, processing, storage, reproduction, and transmittal of classified information within the Department to provide protection for such information and to prevent access by unauthorized...

  17. Changing Landscapes in Safeguarding Babies and Young Children in England

    ERIC Educational Resources Information Center

    Lumsden, Eunice

    2014-01-01

    The importance of safeguarding children from violence is internationally recognised. However, detecting, intervening and protecting children from abuse both within the family and in institutions is complex. This paper specifically focuses on safeguarding in England and how workforce reform in the early years offers the opportunity to forge new…

  18. 7 CFR 958.56 - Safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... first file applications with the committee to ship such onions; (2) Handlers shall obtain inspection... AND ORDERS; FRUITS, VEGETABLES, NUTS), DEPARTMENT OF AGRICULTURE ONIONS GROWN IN CERTAIN DESIGNATED...) The committee, with the approval of the Secretary, may prescribe adequate safeguards to prevent onions...

  19. 7 CFR 958.56 - Safeguards.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... first file applications with the committee to ship such onions; (2) Handlers shall obtain inspection... AND ORDERS; FRUITS, VEGETABLES, NUTS), DEPARTMENT OF AGRICULTURE ONIONS GROWN IN CERTAIN DESIGNATED...) The committee, with the approval of the Secretary, may prescribe adequate safeguards to prevent onions...

  20. 7 CFR 958.56 - Safeguards.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... first file applications with the committee to ship such onions; (2) Handlers shall obtain inspection... and Orders; Fruits, Vegetables, Nuts), DEPARTMENT OF AGRICULTURE ONIONS GROWN IN CERTAIN DESIGNATED...) The committee, with the approval of the Secretary, may prescribe adequate safeguards to prevent onions...

  1. 7 CFR 958.56 - Safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... first file applications with the committee to ship such onions; (2) Handlers shall obtain inspection... and Orders; Fruits, Vegetables, Nuts), DEPARTMENT OF AGRICULTURE ONIONS GROWN IN CERTAIN DESIGNATED...) The committee, with the approval of the Secretary, may prescribe adequate safeguards to prevent onions...

  2. 42 CFR 431.305 - Types of information to be safeguarded.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 42 Public Health 4 2013-10-01 2013-10-01 false Types of information to be safeguarded. 431.305... Information on Applicants and Beneficiaries § 431.305 Types of information to be safeguarded. (a) The agency must have criteria that govern the types of information about applicants and beneficiaries that are...

  3. 14 CFR 1212.605 - Safeguarding information in systems of records.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... requirements applicable to the system of records. (c) When records or copies of records are distributed to... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Safeguarding information in systems of... systems of records. (a) Safeguards appropriate for a NASA system of records shall be developed by the...

  4. The Role of School Psychologists in Child Protection and Safeguarding

    ERIC Educational Resources Information Center

    Woods, Kevin; Bond, Caroline; Tyldesley, Kath; Farrell, Peter; Humphrey, Neil

    2011-01-01

    Child protection and safeguarding are important aspects of work for all professionals working with children. The current article outlines the international context of school psychologists' work in relation to child protection and safeguarding and describes the United Kingdom context in more detail. Given the relatively recent broadening of the UK…

  5. Investigating staff knowledge of safeguarding and pressure ulcers in care homes.

    PubMed

    Ousey, K; Kaye, V; McCormick, K; Stephenson, J

    2016-01-01

    To investigate whether nursing/care home staff regard pressure ulceration as a safeguarding issue; and to explore reporting mechanisms for pressure ulcers (PUs) in nursing/care homes. Within one clinical commissioning group, 65 staff members from 50 homes completed a questionnaire assessing their experiences of avoidable and unavoidable PUs, grading systems, and systems in place for referral to safeguarding teams. Understanding of safeguarding was assessed in depth by interviews with 11 staff members. Staff observed an average of 2.72 PUs in their workplaces over the previous 12 months, judging 45.6% to be avoidable. Only a minority of respondents reported knowledge of a grading system (mostly the EPUAP/NPUAP system). Most respondents would refer PUs to the safeguarding team: the existence of a grading system, or guidance, appeared to increase that likelihood. Safeguarding was considered a priority in most homes; interviewees were familiar with the term safeguarding, but some confusion over its meaning was apparent. Quality of written documentation and verbal communication received before residents returned from hospital was highlighted. However, respondents expressed concern over lack of information regarding skin integrity. Most staff had received education regarding ulcer prevention or wound management during training, but none reported post-registration training or formal education programmes; reliance was placed on advice of district nurses or tissue viability specialists. Staff within nursing/care homes understand the fundamentals of managing skin integrity and the importance of reporting skin damage; however, national education programmes are needed to develop knowledge and skills to promote patient health-related quality of life, and to reduce the health-care costs of pressure damage. Further research to investigate understanding, knowledge and skills of nursing/care home staff concerning pressure ulcer development and safeguarding will become increasingly

  6. Smart wearable Kevlar-based safeguarding electronic textile with excellent sensing performance.

    PubMed

    Wang, Sheng; Xuan, Shouhu; Liu, Mei; Bai, Linfeng; Zhang, Shuaishuai; Sang, Min; Jiang, Wanquan; Gong, Xinglong

    2017-03-29

    A novel S-ST/MWCNT/Kevlar-based wearable electronic textile (WET) with enhanced safeguarding performance and force sensing ability was fabricated. Stab resistance performance tests under quasi-static and dynamic conditions show that the maximum resistance force and penetration impact energy for the WET are 18 N and 11.76 J, which represent a 90% and 50% increment with respect to the neat Kevlar, respectively. Dynamic impact resistance tests show that the WET absorbs all the impact energy. The maximum resistance force of the WET is 1052 N, which represents an improvement of about 190% with respect to neat Kevlar. With the incorporation of multi-walled carbon nanotubes (MWCNTs), the WET can achieve a stable electrical conductivity of ∼10 -2 S m -1 , and the conductivity is highly sensitive to external mechanic forces. Notably, the sensing fabric also exhibits an outstanding ability to detect and analyze external forces. In addition, it can be fixed at any position of the human body and exhibits an ideal monitoring performance. Because of its flexibility, high sensitivity to various types of deformations and excellent safeguarding performance, the WET has a strong potential for wearable monitoring devices that simultaneously provide body protection and monitor the movements of the human body under various conditions.

  7. Protecting me from my Directive: Ensuring Appropriate Safeguards for Advance Directives in Dementia.

    PubMed

    Auckland, Cressida

    2018-02-01

    With one in six people over 80 now suffering from dementia, advance directives provide an important means of empowerment. Upholding directives in the context of dementia, however, raises extra challenges, given the potential for the directive to conflict with an assessment of what is in the person's current best interests. Given the profound harm that tying a person with dementia to their previous wishes can do, it is essential that we have sufficient safeguards in place to ensure that we only uphold such directives where we can be sure they are truly autonomous and are intended to apply to the situation at hand-safeguards which are at present, severely lacking. This article will consider various mechanisms by which safeguards can be built into the legal regime to ensure that the original decision is autonomous, including making it mandatory for the person to undergo a consultation with a healthcare professional, which would involve a contemporaneous capacity assessment. Clinicians must also be confident that the directive applies to the situation at hand. Introducing formalities, including a standardised (though not mandatory) proforma, may help to enhance specificity about when the directive is triggered, and to what treatments it relates, to enable clinicians to better assess the directive's applicability. A national registry for advance directives might also be beneficial. It will be argued that health care professionals will have to play a much greater role in the drafting and registering of advance directives, if we are to feel comfortable in upholding them.

  8. Verification of Spent Nuclear Fuel in Sealed Dry Storage Casks via Measurements of Cosmic-Ray Muon Scattering

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Durham, J. M.; Poulson, D.; Bacon, J.

    Most of the plutonium in the world resides inside spent nuclear reactor fuel rods. This high-level radioactive waste is commonly held in long-term storage within large, heavily shielded casks. Currently, international nuclear safeguards inspectors have no stand-alone method of verifying the amount of reactor fuel stored within a sealed cask. In this paper, we demonstrate experimentally that measurements of the scattering angles of cosmic-ray muons, which pass through a storage cask, can be used to determine if spent fuel assemblies are missing without opening the cask. Finally, this application of technology and methods commonly used in high-energy particle physics providesmore » a potential solution to this long-standing problem in international nuclear safeguards.« less

  9. Verification of Spent Nuclear Fuel in Sealed Dry Storage Casks via Measurements of Cosmic-Ray Muon Scattering

    DOE PAGES

    Durham, J. M.; Poulson, D.; Bacon, J.; ...

    2018-04-10

    Most of the plutonium in the world resides inside spent nuclear reactor fuel rods. This high-level radioactive waste is commonly held in long-term storage within large, heavily shielded casks. Currently, international nuclear safeguards inspectors have no stand-alone method of verifying the amount of reactor fuel stored within a sealed cask. In this paper, we demonstrate experimentally that measurements of the scattering angles of cosmic-ray muons, which pass through a storage cask, can be used to determine if spent fuel assemblies are missing without opening the cask. Finally, this application of technology and methods commonly used in high-energy particle physics providesmore » a potential solution to this long-standing problem in international nuclear safeguards.« less

  10. NMR of insensitive nuclei enhanced by dynamic nuclear polarization.

    PubMed

    Miéville, Pascal; Jannin, Sami; Helm, Lothar; Bodenhausen, Geoffrey

    2011-01-01

    Despite the powerful spectroscopic information it provides, Nuclear Magnetic Resonance (NMR) spectroscopy suffers from a lack of sensitivity, especially when dealing with nuclei other than protons. Even though NMR can be applied in a straightforward manner when dealing with abundant protons of organic molecules, it is very challenging to address biomolecules in low concentration and/or many other nuclei of the periodic table that do not provide as intense signals as protons. Dynamic Nuclear Polarization (DNP) is an important technique that provides a way to dramatically increase signal intensities in NMR. It consists in transferring the very high electron spin polarization of paramagnetic centers (usually at low temperature) to the surrounding nuclear spins with appropriate microwave irradiation. DNP can lead to an enhancement of the nuclear spin polarization by up to four orders of magnitude. We present in this article some basic concepts of DNP, describe the DNP apparatus at EPFL, and illustrate the interest of the technique for chemical applications by reporting recent measurements of the kinetics of complexation of 89Y by the DOTAM ligand.

  11. Nuclear Export Inhibition Enhances HLH-30/TFEB Activity, Autophagy, and Lifespan.

    PubMed

    Silvestrini, Melissa J; Johnson, Joseph R; Kumar, Anita V; Thakurta, Tara G; Blais, Karine; Neill, Zachary A; Marion, Sarah W; St Amand, Victoria; Reenan, Robert A; Lapierre, Louis R

    2018-05-15

    Transcriptional modulation of the process of autophagy involves the transcription factor HLH-30/TFEB. In order to systematically determine the regulatory network of HLH-30/TFEB, we performed a genome-wide RNAi screen in C. elegans and found that silencing the nuclear export protein XPO-1/XPO1 enhances autophagy by significantly enriching HLH-30 in the nucleus, which is accompanied by proteostatic benefits and improved longevity. Lifespan extension via xpo-1 silencing requires HLH-30 and autophagy, overlapping mechanistically with several established longevity models. Selective XPO1 inhibitors recapitulated the effect on autophagy and lifespan observed by silencing xpo-1 and protected ALS-afflicted flies from neurodegeneration. XPO1 inhibition in HeLa cells enhanced TFEB nuclear localization, autophagy, and lysosome biogenesis without affecting mTOR activity, revealing a conserved regulatory mechanism for HLH-30/TFEB. Altogether, our study demonstrates that altering the nuclear export of HLH-30/TFEB can regulate autophagy and establishes the rationale of targeting XPO1 to stimulate autophagy in order to prevent neurodegeneration. Copyright © 2018 The Authors. Published by Elsevier Inc. All rights reserved.

  12. Field Trial of the Enhanced Data Authentication System (EDAS)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Thomas, Maikael A.; Baldwin, George T.; Hymel, Ross W.

    2016-05-01

    The goal of the field trial of EDAS was to demonstrate the utility of secure branching of operator instrumentation for nuclear safeguards, identify any unforeseen implementation and application issues with EDAS, and confirm whether the approach is compatible with operator concerns and constraints.

  13. The organisation of interagency training to safeguard children in England: a case study using realistic evaluation

    PubMed Central

    Patsios, Demi; Carpenter, John

    2010-01-01

    Background Joint training for interagency working is carried out by Local Safeguarding Children Boards in England to promote effective local working to safeguard and promote the welfare of children. Purpose This paper reports on the findings of the outputs and outcomes of interagency training to safeguard children in eight Local Safeguarding Children Boards. Methods A review of Local Safeguarding Children Board documentation, observations of Local Safeguarding Children Board training sub-group meetings and a series of interviews with training key stakeholders in each Local Safeguarding Children Board were used to assess how partner agencies in the Local Safeguarding Children Boards carried out their statutory responsibilities to organise interagency training. ‘Realistic Evaluation’ was used to evaluate the mechanisms by which a central government mandate produced particular inter-agency training outputs (number of courses, training days) and joint working outcomes (effective partnerships), within particular Local Safeguarding Children Board contexts. Results The ‘mandated partnership’ imposed on Local Safeguarding Children Boards by central government left little choice but for partner agencies to work together to deliver joint training, which in turn affected the dynamics of working partnerships across the various sites. The effectiveness of the training sub group determined the success of the organisation and delivery of training for joint working. Despite having a central mandate, Local Safeguarding Children Boards had heterogeneous funding and training arrangements. These resulted in significant variations in the outputs in terms of the number of courses per ‘children in need’ in the locality and in the cost per course. Conclusions Interagency training which takes account of the context of the Local Safeguarding Children Board is more likely to produce better trained staff, effective partnership working, and lead to better integrated safeguarding

  14. 7 CFR 958.56 - Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 958.56 Section 958.56 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... dehydrators into dehydrated onion products, from entering channels of trade for other than the purpose...

  15. 7 CFR 946.55 - Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 946.55 Section 946.55 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... channels of trade and other outlets for other than the specific purposes authorized therefor, and the...

  16. 7 CFR 966.56 - Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 966.56 Section 966.56 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... from entering channels of trade for other than the specific purpose authorized therefor, and rules...

  17. Audit Report Office of the Inspector General: Defense Nuclear Agency Activities at Johnston Atoll

    DTIC Science & Technology

    1989-12-15

    DEPARTMENT OF DEFENSE AUDIT REPORT DEFENSE NUCLEAR AGENCY ACTIVITIES AT JOHNSTON ATOLL NO. 90-020 December 15, 1989 A&piored tea ggabiic release...a 5330 Accession Number: 5320 Publication Date: Dec 15, 1989 Title: Audit Report Office Of The Inspector General: Defense Nuclear Agency...Descriptors, Keywords: DNA Johnston Atoll Audit Management Economy Efficiency BOS Administration Oversight DOE Nuclear Atmospheric Testing Safeguard

  18. Teaching to Enhance Research

    ERIC Educational Resources Information Center

    Harland, Tony

    2016-01-01

    In this paper, I present a conceptual argument for "teaching-led research" in which university lecturers construct courses that directly and positively influence their research, while at the same time, safeguard and enhance the student experience. A research-pedagogy for higher education considers the link between teaching and research,…

  19. The US Support Program to IAEA Safeguards Priority of Training and Human Resources

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Queirolo,A.

    2008-06-13

    The U.S. Support Program to IAEA Safeguards (USSP) priority of training and human resources is aimed at providing the Department of Safeguards with an appropriate mixture of regular staff and extrabudgetary experts who are qualified to meet the IAEA's technical needs and to provide personnel with appropriate instruction to improve the technical basis and specific skills needed to perform their job functions. The equipment and methods used in inspection activities are unique, complex, and evolving. New and experienced safeguards inspectors need timely and effective training to perform required tasks and to learn new skills prescribed by new safeguards policies ormore » agreements. The role of the inspector has changed from that of strictly an accountant to include that of a detective. New safeguards procedures are being instituted, and therefore, experienced inspectors must be educated on these new procedures. The USSP also recognizes the need for training safeguards support staff, particularly those who maintain and service safeguards equipment (SGTS), and those who perform information collection and analysis (SGIM). The USSP is committed to supporting the IAEA with training to ensure the effectiveness of all staff members and will continue to offer its assistance in the development and delivery of basic, refresher, and advanced training courses. This paper will discuss the USSP ongoing support in the area of training and IAEA staffing.« less

  20. Promoting Intercultural Competency in the Nuclear Workplace

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bachner K. M.

    Intercultural preparedness training is a staple of many workplaces that require international competence, including government, business, and non-profits. Even highly experienced diplomats are often advised to attend training sessions on this topic. Intercultural preparedness training promises to be especially relevant and useful for professionals working in the field of nuclear nonproliferation, including in the application of international nuclear safeguards. This paper outlines the fundamental philosophies underlying a training program that will benefit professionals in the nuclear arena, whether practitioners of nonproliferation or other sub-fields relying on international cooperation and collaboration, and how such a training program might be implemented efficiently.

  1. 10 CFR Appendix G to Part 73 - Reportable Safeguards Events

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Reportable Safeguards Events G Appendix G to Part 73.... G Appendix G to Part 73—Reportable Safeguards Events Pursuant to the provisions of 10 CFR 73.71 (b.... (b) Any other threatened, attempted, or committed act not previously defined in appendix G with the...

  2. 10 CFR Appendix G to Part 73 - Reportable Safeguards Events

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Reportable Safeguards Events G Appendix G to Part 73.... G Appendix G to Part 73—Reportable Safeguards Events Pursuant to the provisions of 10 CFR 73.71 (b.... (b) Any other threatened, attempted, or committed act not previously defined in appendix G with the...

  3. 10 CFR Appendix G to Part 73 - Reportable Safeguards Events

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Reportable Safeguards Events G Appendix G to Part 73.... G Appendix G to Part 73—Reportable Safeguards Events Pursuant to the provisions of 10 CFR 73.71 (b.... (b) Any other threatened, attempted, or committed act not previously defined in appendix G with the...

  4. 10 CFR Appendix G to Part 73 - Reportable Safeguards Events

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Reportable Safeguards Events G Appendix G to Part 73.... G Appendix G to Part 73—Reportable Safeguards Events Pursuant to the provisions of 10 CFR 73.71 (b.... (b) Any other threatened, attempted, or committed act not previously defined in appendix G with the...

  5. 17 CFR 160.30 - Procedures to safeguard customer records and information.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... customer records and information. 160.30 Section 160.30 Commodity and Securities Exchanges COMMODITY... Date § 160.30 Procedures to safeguard customer records and information. Every futures commission... physical safeguards for the protection of customer records and information. These policies and procedures...

  6. 7 CFR 945.56 - Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 945.56 Section 945.56 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... prevent shipments pursuant to § 945.53 from entering channels of trade and other outlets for other than...

  7. 7 CFR 948.24 - Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 948.24 Section 948.24 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... entering trade channels other than those authorized by regulations and by such rules as may be necessary...

  8. Machine safety: proper safeguarding techniques.

    PubMed

    Martin, K J

    1992-06-01

    1. OSHA mandates certain safeguarding of machinery to prevent accidents and protect machine operators. OSHA specifies moving parts that must be guarded and sets criteria for the guards. 2. A 1989 OSHA standard for lockout/tagout requires locking the energy source during maintenance, periodically inspecting for power transmission, and training maintenance workers. 3. In an amputation emergency, first aid for cardiopulmonary resuscitation, shock, and bleeding are the first considerations. The amputated part should be wrapped in moist gauze, placed in a sealed plastic bag, and placed in a container of 50% water and 50% ice for transport. 4. The role of the occupational health nurse in machine safety is to conduct worksite analyses to identify proper safeguarding and to communicate deficiencies to appropriate personnel; to train workers in safe work practices and observe compliance in the use of machine guards; to provide care to workers injured by machines; and to reinforce safe work practices among machine operators.

  9. Safeguarding and Protecting Children in Maternity Services: Implications for Practice

    ERIC Educational Resources Information Center

    Lazenbatt, Anne; Greer, Jean

    2009-01-01

    This article debates the issues involved in safeguarding and protecting children in maternity services and offers implications for professional practice. Midwives and other staff who work as members of the maternity team have a safeguarding role to play in the identification of babies and children who have been abused, or are at risk of abuse, and…

  10. Measured 19F(α,n) with VANDLE for Nuclear Safeguards

    NASA Astrophysics Data System (ADS)

    Peters, William; Clement, R. C. C.; Smith, M. S.; Pain, S.; Febbraro, M.; Pittman, S.; Thomspon, S.; Grinder, M.; Cizewski, J. A.; Reingold, C.; Manning, B.; Burcher, S.; Bardayan, D. W.; Tan, W.-P.; Stech, E.; Smith, M. K.; Avetisyan, R.; Gyurjinyan, A.; Lowe, M.; Ilyushkin, S.; Grzywacz, R.; Madurga, M.; Paulauskas, S. V.; Taylor, S. Z.; Smith, K.

    2015-10-01

    One of the most promising non-destructive assay (NDA) methods to monitor UF6 canisters consists of measuring gross neutron rates induced by uranium-decay alpha particles reacting with the fluorine and emitting a neutron. This method currently lacks reliable nuclear data on the 19F(α,n) reaction cross section to determine an accurate neutron yield rate for a given sample of UF6. We have measured the cross section and coincident neutron spectrum for the alpha-decay energy range using the VANDLE system. This experiment had two parts: first at Notre Dame with a LaF3 target and and a pulsed alpha-particle beam, and second at ORNL with a windowless He-gas target and a 19F beam. The motivation for this measurement and cross section results will be presented. This work is funded in part by the DOE Office of Science, the National Nuclear Security Administration SSAA and the Office of Defense Nuclear Nonproliferation R&D, and the NSF.

  11. Operations research applications in nuclear energy

    NASA Astrophysics Data System (ADS)

    Johnson, Benjamin Lloyd

    This dissertation consists of three papers; the first is published in Annals of Operations Research, the second is nearing submission to INFORMS Journal on Computing, and the third is the predecessor of a paper nearing submission to Progress in Nuclear Energy. We apply operations research techniques to nuclear waste disposal and nuclear safeguards. Although these fields are different, they allow us to showcase some benefits of using operations research techniques to enhance nuclear energy applications. The first paper, "Optimizing High-Level Nuclear Waste Disposal within a Deep Geologic Repository," presents a mixed-integer programming model that determines where to place high-level nuclear waste packages in a deep geologic repository to minimize heat load concentration. We develop a heuristic that increases the size of solvable model instances. The second paper, "Optimally Configuring a Measurement System to Detect Diversions from a Nuclear Fuel Cycle," introduces a simulation-optimization algorithm and an integer-programming model to find the best, or near-best, resource-limited nuclear fuel cycle measurement system with a high degree of confidence. Given location-dependent measurement method precisions, we (i) optimize the configuration of n methods at n locations of a hypothetical nuclear fuel cycle facility, (ii) find the most important location at which to improve method precision, and (iii) determine the effect of measurement frequency on near-optimal configurations and objective values. Our results correspond to existing outcomes but we obtain them at least an order of magnitude faster. The third paper, "Optimizing Nuclear Material Control and Accountability Measurement Systems," extends the integer program from the second paper to locate measurement methods in a larger, hypothetical nuclear fuel cycle scenario given fixed purchase and utilization budgets. This paper also presents two mixed-integer quadratic programming models to increase the precision of

  12. Nuclear forensics of a non-traditional sample: Neptunium

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Doyle, Jamie L.; Schwartz, Daniel; Tandon, Lav

    Recent nuclear forensics cases have focused primarily on plutonium (Pu) and uranium (U) materials. By definition however, nuclear forensics can apply to any diverted nuclear material. This includes neptunium (Np), an internationally safeguarded material like Pu and U, that could offer a nuclear security concern if significant quantities were found outside of regulatory control. This case study couples scanning electron microscopy (SEM) with quantitative analysis using newly developed specialized software, to evaluate a non-traditional nuclear forensic sample of Np. Here, the results of the morphological analyses were compared with another Np sample of known pedigree, as well as other traditionalmore » actinide materials in order to determine potential processing and point-of-origin.« less

  13. Nuclear forensics of a non-traditional sample: Neptunium

    DOE PAGES

    Doyle, Jamie L.; Schwartz, Daniel; Tandon, Lav

    2016-05-16

    Recent nuclear forensics cases have focused primarily on plutonium (Pu) and uranium (U) materials. By definition however, nuclear forensics can apply to any diverted nuclear material. This includes neptunium (Np), an internationally safeguarded material like Pu and U, that could offer a nuclear security concern if significant quantities were found outside of regulatory control. This case study couples scanning electron microscopy (SEM) with quantitative analysis using newly developed specialized software, to evaluate a non-traditional nuclear forensic sample of Np. Here, the results of the morphological analyses were compared with another Np sample of known pedigree, as well as other traditionalmore » actinide materials in order to determine potential processing and point-of-origin.« less

  14. 7 CFR 906.44 - Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 906.44 Section 906.44 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... pursuant to § 906.41 or § 906.42 from entering channels of trade for other than the specific purpose...

  15. 7 CFR 956.66 - Safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Safeguards. 956.66 Section 956.66 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Onions shipped, pursuant to §§ 956.63 and 956.64, from entering channels of trade for other than the...

  16. NUCLEAR ESPIONAGE: Report Details Spying on Touring Scientists.

    PubMed

    Malakoff, D

    2000-06-30

    A congressional report released this week details dozens of sometimes clumsy attempts by foreign agents to obtain nuclear secrets from U.S. nuclear scientists traveling abroad, ranging from offering scientists prostitutes to prying off the backs of their laptop computers. The report highlights the need to better prepare traveling researchers to safeguard secrets and resist such temptations, say the two lawmakers who requested the report and officials at the Department of Energy, which employs the scientists.

  17. 14 CFR § 1212.605 - Safeguarding information in systems of records.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 14 Aeronautics and Space 5 2014-01-01 2014-01-01 false Safeguarding information in systems of records. § 1212.605 Section § 1212.605 Aeronautics and Space NATIONAL AERONAUTICS AND SPACE... Technology Security Officer for electronic records maintained in automated systems. Safeguards must insure...

  18. 30 CFR 77.203 - Use of material or equipment overhead; safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...; safeguards. 77.203 Section 77.203 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS, SURFACE COAL MINES AND SURFACE WORK AREAS...; safeguards. Where overhead repairs are being made at surface installations and equipment or material is taken...

  19. 13 CFR 108.506 - Safeguarding the NMVC Company's assets/Internal controls.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Safeguarding the NMVC Company's assets/Internal controls. 108.506 Section 108.506 Business Credit and Assistance SMALL BUSINESS... safeguard your assets and monitor the reliability of your financial data, personnel, Portfolio, funds and...

  20. 13 CFR 108.506 - Safeguarding the NMVC Company's assets/Internal controls.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 13 Business Credit and Assistance 1 2012-01-01 2012-01-01 false Safeguarding the NMVC Company's assets/Internal controls. 108.506 Section 108.506 Business Credit and Assistance SMALL BUSINESS... safeguard your assets and monitor the reliability of your financial data, personnel, Portfolio, funds and...

  1. 13 CFR 108.506 - Safeguarding the NMVC Company's assets/Internal controls.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 13 Business Credit and Assistance 1 2011-01-01 2011-01-01 false Safeguarding the NMVC Company's assets/Internal controls. 108.506 Section 108.506 Business Credit and Assistance SMALL BUSINESS... safeguard your assets and monitor the reliability of your financial data, personnel, Portfolio, funds and...

  2. 13 CFR 108.506 - Safeguarding the NMVC Company's assets/Internal controls.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 13 Business Credit and Assistance 1 2014-01-01 2014-01-01 false Safeguarding the NMVC Company's assets/Internal controls. 108.506 Section 108.506 Business Credit and Assistance SMALL BUSINESS... safeguard your assets and monitor the reliability of your financial data, personnel, Portfolio, funds and...

  3. 13 CFR 108.506 - Safeguarding the NMVC Company's assets/Internal controls.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 13 Business Credit and Assistance 1 2013-01-01 2013-01-01 false Safeguarding the NMVC Company's assets/Internal controls. 108.506 Section 108.506 Business Credit and Assistance SMALL BUSINESS... safeguard your assets and monitor the reliability of your financial data, personnel, Portfolio, funds and...

  4. THE ATTRACTIVENESS OF MATERIAS ASSOCIATED WITH THORIUM-BASED NUCLEAR FUEL CYCLES FOR PHWRS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Prichard, Andrew W.; Niehus, Mark T.; Collins, Brian A.

    2011-07-17

    This paper reports the continued evaluation of the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with thorium based nuclear fuel cycles. Specifically, this paper examines a thorium fuel cycle in which a pressurized heavy water reactor (PHWR) is fueled with mixtures of natural uranium/233U/thorium. This paper uses a PHWR fueled with natural uranium as a base fuel cycle, and then compares material attractiveness of fuel cycles that use 233U/thorium salted with natural uranium. The results include the material attractiveness of fuel at beginning of life (BoL), end of life (EoL), and the number of fuel assemblies requiredmore » to collect a bare critical mass of plutonium or uranium. This study indicates what is required to render the uranium as having low utility for use in nuclear weapons; in addition, this study estimates the increased number of assemblies required to accumulate a bare critical mass of plutonium that has a higher utility for use in nuclear weapons. This approach identifies that some fuel cycles may be easier to implement the International Atomic Energy Agency (IAEA) safeguards approach and have a more effective safeguards by design outcome. For this study, approximately one year of fuel is required to be reprocessed to obtain one bare critical mass of plutonium. Nevertheless, the result of this paper suggests that all spent fuel needs to be rigorously safeguarded and provided with high levels of physical protection. This study was performed at the request of the United States Department of Energy /National Nuclear Security Administration (DOE/NNSA). The methodology and key findings will be presented.« less

  5. 76 FR 48184 - Exelon Nuclear, Peach Bottom Atomic Power Station, Unit 1; Exemption From Certain Security...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-08

    ... nuclear reactor facility. PBAPS Unit 1 was a high-temperature, gas-cooled reactor that was operated from... the safeguards contingency plan.'' Part 73 of 10 CFR, ``Physical Protection of Plant and Materials... physical protection system which will have capabilities for the protection of special nuclear material at...

  6. Assess How Changes in Fuel Cycle Operation Impact Safeguards

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Tobin, Stephen Joseph; Adigun, Babatunde John; Fugate, Michael Lynn

    Since the beginning of commercial nuclear power generation in the 1960s, the ability of researchers to understand and control the isotopic content of spent fuel has improved. It is therefore not surprising that both fuel assembly design and fuel assembly irradiation optimization have improved over the past 50+ years. It is anticipated that the burnup and isotopics of the spent fuel should exhibit less variation over the decades as reactor operators irradiate each assembly to the optimum amount. In contrast, older spent fuel is anticipated to vary more in burnup and resulting isotopics for a given initial enrichment. Modern fuelmore » therefore should be more uniform in composition, and thus, measured safeguards results should be easier to interpret than results from older spent fuel. With spent fuel ponds filling up, interim and long-­term storage of spent fuel will need to be addressed. Additionally after long periods of storage, spent fuel is no longer self-­protecting and, as such, the IAEA will categorize it as more attractive; in approximately 20 years many of the assemblies from early commercial cores will no longer be considered self-­protecting. This study will assess how more recent changes in the reactor operation could impact the interpretation of safeguards measurements. The status quo for spent fuel assay in the safeguards context is that the overwhelming majority of spent fuel assemblies are not measured in a quantitative way except for those assemblies about to be loaded into a difficult or impossible to access location (dry storage or, in the future, a repository). In other words, when the assembly is still accessible to a state actor, or an insider, when it is cooling in a pool, the inspectorate does not have a measurement database that could assist them in re-­verifying the integrity of that assembly. The spent fuel safeguards regime would be strengthened if spent fuel assemblies were measured from discharge to loading into a difficult or

  7. Safeguards for healthy volunteers in drug studies.

    PubMed

    Smith, R N

    1975-09-06

    Safeguards for healthy volunteers in drug studies have not been as strict as those involving patients. The shortcomings include the lack of surveillance over the scientific validity of the protocol and its ethical review, and over the financial inducements to volunteers. Recruitment is open to abuse because the volunteers may have some allegiance to the investigators. There is an urgent need to institute checks on these aspects. Most important, however, is the lack of legal safeguards for volunteers taking part in research done outside the pharmaceutical industry. The suggested procedure for obtaining consent, for health checks, and for providing compensation can be equitable to all concerned, and yet not restrict initiative, nor curtail research aims.

  8. Glycogen synthase kinase-3 enhances nuclear export of a Dictyostelium STAT protein

    PubMed Central

    Ginger, Rebecca S.; Dalton, Emma C.; Ryves, W.Jonathan; Fukuzawa, Masashi; Williams, Jeffrey G.; Harwood, Adrian J.

    2000-01-01

    Extracellular cAMP stimulates the rapid tyrosine phosphorylation and nuclear translocation of the Dictyostelium STAT protein Dd-STATa. Here we show that it also induces serine phosphorylation by GskA, a homologue of glycogen synthase kinase-3 (GSK-3). Tyrosine phosphorylation occurs within 10 s of stimulation, whereas serine phosphorylation takes 5 min, matching the kinetics observed for the cAMP regulation of GskA. Phosphorylation by GskA enhances nuclear export of Dd-STATa. The phosphorylated region, however, is not itself a nuclear export signal and we identify a region elsewhere in the protein that mediates nuclear export. These results suggest a biphasic regulation of Dd-STATa, in which extracellular cAMP initially directs nuclear import and then, via GskA, promotes its subsequent export. It also raises the possibility of an analogous regulation of STAT nuclear export in higher eukaryotes. PMID:11032815

  9. National Security to Nationalist Myth: Why Iran Wants Nuclear Weapons

    DTIC Science & Technology

    2004-09-01

    Atomic Energy Organization of Iran ( AEOI ),81 as well as Iran’s nuclear technology suppliers. By publicly embracing the “nuclear insecurity” myth and...81 The literature variously refers to the Atomic Energy Organization of Iran as “ AEOI ,” or “IAEO...I have adopted “ AEOI ,” the form used by the IAEA, except where quoting other sources. See “Implementation of the NPT Safeguards Agreement in the

  10. The Use of Performance Metrics for the Assessment of Safeguards Effectiveness at the State Level

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bachner K. M.; George Anzelon, Lawrence Livermore National Laboratory, Livermore, CA Yana Feldman, Lawrence Livermore National Laboratory, Livermore, CA Mark Goodman,Department of State, Washington, DC Dunbar Lockwood, National Nuclear Security Administration, Washington, DC Jonathan B. Sanborn, JBS Consulting, LLC, Arlington, VA.

    In the ongoing evolution of International Atomic Energy Agency (IAEA) safeguards at the state level, many safeguards implementation principles have been emphasized: effectiveness, efficiency, non-discrimination, transparency, focus on sensitive materials, centrality of material accountancy for detecting diversion, independence, objectivity, and grounding in technical considerations, among others. These principles are subject to differing interpretations and prioritizations and sometimes conflict. This paper is an attempt to develop metrics and address some of the potential tradeoffs inherent in choices about how various safeguards policy principles are implemented. The paper carefully defines effective safeguards, including in the context of safeguards approaches that take accountmore » of the range of state-specific factors described by the IAEA Secretariat and taken note of by the Board in September 2014, and (2) makes use of performance metrics to help document, and to make transparent, how safeguards implementation would meet such effectiveness requirements.« less

  11. 75 FR 74750 - In the Matter of Toshiba America Nuclear Energy Corporation and All Other Persons Who Seek or...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-01

    ... NUCLEAR REGULATORY COMMISSION [EA-10-152; Project No. 52-0001; NRC-2010-0368] In the Matter of Toshiba America Nuclear Energy Corporation and All Other Persons Who Seek or Obtain Access to Safeguards... protect SGI (73 FR 63546). The NRC is issuing this Order to Toshiba America Nuclear Energy Corporation...

  12. Long-Term Information Management (LTIM) of Safeguards Data at Repositories: Phase II

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Haddal, Risa N.

    One of the challenges of implementing safeguards for geological repositories will be the long-term preservation of safeguards-related data for 100 years or more. While most countries considering the construction and operation of such facilities agree that safeguards information should be preserved, there are gaps with respect to standardized requirements, guidelines, timescales, and approaches. This study analyzes those gaps and explores research to clarify stakeholder needs, identify current policies, approaches, best practices and international standards, and explores existing safeguards information management infrastructure. The study also attempts to clarify what a safeguards data classification system might look like, how long data shouldmore » be retained, and how information should be exchanged between stakeholders at different phases of a repository’s life cycle. The analysis produced a variety of recommendations on what information to preserve, how to preserve it, where to store it, retention options and how to exchange information in the long term. Key findings include the use of the globally recognized international records management standard, ISO15489, for guidance on the development of information management systems, and the development of a Key Information File (KIF). The KIF could be used to identify only the most relevant, high-level safeguards information and the history of decision making about the repository. The study also suggests implementing on-site and off-site records storage in digital and physical form; developing a safeguards data classification system; long-term records retention with periodic reviews every 5 to 10 years during each phase of the repository life cycle; and establishing transition procedures well in advance so that data shepherds and records officers can transfer information with incoming facility managers effectively and efficiently. These and other recommendations are further analyzed in this study.« less

  13. Evidence of an enhanced nuclear radius of the α -halo state via α +12C inelastic scattering

    NASA Astrophysics Data System (ADS)

    Ito, Makoto

    2018-04-01

    Evidence of the enhanced nuclear radius in the Hoyle rotational state, 22+, is derived from the differential cross sections in α +12C inelastic scattering. The prominent shrinkage is observed in the differential cross section of the 22+ state in comparison to the yrast 21+ state, and this shrinkage is the first evidence of the enhanced nuclear radius which originates from the 3 α structure in the 22+ state. A diffraction formula, that is, Blair's phase rule, is applied to the differential cross sections, and the present analysis predicts an enhancement of 0.6 to 1.0 fm in the nuclear radius of the 22+ state in comparison to the radius of the yrast 21+, which is considered to have a normal nuclear radius. Constraint on the recent ab initio calculation for 3 α states in 12C is also discussed.

  14. 30 CFR 75.1101-20 - Safeguards for dry powder chemical systems.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Safeguards for dry powder chemical systems. 75...-20 Safeguards for dry powder chemical systems. Adequate guards shall be provided along all belt conveyors in the vicinity of each dry powder chemical system to protect persons whose vision is restricted...

  15. 30 CFR 75.1101-20 - Safeguards for dry powder chemical systems.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Safeguards for dry powder chemical systems. 75...-20 Safeguards for dry powder chemical systems. Adequate guards shall be provided along all belt conveyors in the vicinity of each dry powder chemical system to protect persons whose vision is restricted...

  16. 30 CFR 75.1101-20 - Safeguards for dry powder chemical systems.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Safeguards for dry powder chemical systems. 75...-20 Safeguards for dry powder chemical systems. Adequate guards shall be provided along all belt conveyors in the vicinity of each dry powder chemical system to protect persons whose vision is restricted...

  17. 30 CFR 75.1101-20 - Safeguards for dry powder chemical systems.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Safeguards for dry powder chemical systems. 75...-20 Safeguards for dry powder chemical systems. Adequate guards shall be provided along all belt conveyors in the vicinity of each dry powder chemical system to protect persons whose vision is restricted...

  18. Nuclear safety policy working group recommendations on nuclear propulsion safety for the space exploration initiative

    NASA Technical Reports Server (NTRS)

    Marshall, Albert C.; Lee, James H.; Mcculloch, William H.; Sawyer, J. Charles, Jr.; Bari, Robert A.; Cullingford, Hatice S.; Hardy, Alva C.; Niederauer, George F.; Remp, Kerry; Rice, John W.

    1993-01-01

    An interagency Nuclear Safety Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program. These recommendations, which are contained in this report, should facilitate the implementation of mission planning and conceptual design studies. The NSPWG has recommended a top-level policy to provide the guiding principles for the development and implementation of the SEI nuclear propulsion safety program. In addition, the NSPWG has reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. These recommendations should be useful for the development of the program's top-level requirements for safety functions (referred to as Safety Functional Requirements). The safety requirements and guidelines address the following topics: reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations.

  19. 45 CFR 605.36 - Procedural safeguards.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION... Preschool, Elementary, and Secondary Education § 605.36 Procedural safeguards. A recipient that operates a public elementary or secondary education program shall establish and implement, with respect to actions...

  20. 45 CFR 605.36 - Procedural safeguards.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION... Preschool, Elementary, and Secondary Education § 605.36 Procedural safeguards. A recipient that operates a public elementary or secondary education program shall establish and implement, with respect to actions...

  1. 45 CFR 605.36 - Procedural safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION... Preschool, Elementary, and Secondary Education § 605.36 Procedural safeguards. A recipient that operates a public elementary or secondary education program shall establish and implement, with respect to actions...

  2. 45 CFR 605.36 - Procedural safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION... Preschool, Elementary, and Secondary Education § 605.36 Procedural safeguards. A recipient that operates a public elementary or secondary education program shall establish and implement, with respect to actions...

  3. Safeguards Technology Strategic Planning Pentachart

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Carroll, C. J.

    Builds on earlier strategic planning workshops conducted for SGIT, SGTS, and SGCP. Many of recommendations from these workshops have been successfully implemented at the IAEA. Provide a context for evaluating new approaches for anticipated safeguards challenges of the future. Approach used by government and military to plan for an uncertain future. Uses consensus decision-making.

  4. Far-field Wireless Energy Harvesting for Increased Safeguards Equipment Battery Life.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hymel, Ross W.

    Modern unattended safeguards equipment (e.g. seals) incorporates many low-power electronic circuits, which are typically powered by expensive and toxic lithium thionyl chloride (LiSOCL2) batteries. The limited life of these batteries necessitates their periodic replacement. This replacement must be performed before total battery discharge to avoid potential loss of continuity of knowledge. Thus, the effective battery capacity becomes significantly less than the actual usable capacity. Additionally, such maintenance is a radiological hazard to personnel, as well as a monetary burden to a safeguards inspectorate. Energy harvesting, a commercially available technology, could extend the operational life of batterypowered equipment to achieve significantmore » efficiencies for safeguards deployments. Energy harvesting is the scavenging and storage of ambient energy sources, such as solar, thermal, and kinetic for use in lowpower electronic applications. While the amount of scavenged energy per unit time may be small, it most often comes from a source that will not be depleted throughout the deployment of the harvesting device. The best-known energy harvesters are solar panels and wind turbines. Recently, far-field wireless energy harvesting has become a commercially available option. Far-field wireless energy harvesting provides consistent, predictable, and un-tethered power over distances up to 50 feet. This process converts radio frequency (RF) energy, both intentionally emitted and ambient, into usable direct current (DC) power. Incorporating far-field wireless energy harvesting into safeguards equipment can significantly extend the equipment’s battery life and perhaps make it indefinite. Furthermore, additional functionality can be added to safeguards equipment without lowering its operational life expectancy. This paper explores the benefits and drawbacks of integrating far-field wireless energy harvesting into a chosen safeguards seal: the Remotely Monitored

  5. 77 FR 51496 - Federal Acquisition Regulation; Basic Safeguarding of Contractor Information Systems

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-24

    ... Federal Acquisition Regulation; Basic Safeguarding of Contractor Information Systems AGENCY: Department of... Acquisition Regulation (FAR) to add a new subpart and contract clause for the basic safeguarding of contractor... information) that will be resident on or transiting through contractor information systems. DATES: Interested...

  6. Comparison of experimental results of a Quad-CZT array detector, a NaI(Tl), a LaBr3(Ce), and a HPGe for safeguards applications

    NASA Astrophysics Data System (ADS)

    Kwak, S.-W.; Choi, J.; Park, S. S.; Ahn, S. H.; Park, J. S.; Chung, H.

    2017-11-01

    A compound semiconductor detector, CdTe (or CdZnTe), has been used in various areas including nuclear safeguards applications. To address its critical drawback, low detection efficiency, which leads to a long measurement time, a Quad-CZT array-based gamma-ray spectrometer in our previous study has been developed by combining four individual CZT detectors. We have re-designed the developed Quad-CZT array system to make it more simple and compact for a hand-held gamma-ray detector. The objective of this paper aims to compare the improved Quad-CZT array system with the traditional gamma-ray spectrometers (NaI(Tl), LaBr3(Ce), HPGe); these detectors currently have been the most commonly used for verification of nuclear materials. Nuclear materials in different physical forms in a nuclear facility of Korea were measured by the Quad-CZT array system and the existing gamma-ray detectors. For measurements of UO2 pellets and powders, and fresh fuel rods, the Quad-CZT array system turned out to be superior to the NaI(Tl) and LaBr3(Ce). For measurements of UF6 cylinders with a thick wall, the Quad-CZT array system and HPGe gave similar accuracy under the same measurement time. From the results of the field tests conducted, we can conclude that the improved Quad-CZT array system would be used as an alternative to HPGes and scintillation detectors for the purpose of increasing effectivenss and efficiency of safeguards applications. This is the first paper employing a multi-element CZT array detector for measurement of nuclear materials—particularly uranium in a UF6 cylinder—in a real nuclear facility. The present work also suggests that the multi-CZT array system described in this study would be one promising method to address a serious weakness of CZT-based radiation detection.

  7. Leveraging existing information for use in a National Nuclear Forensics Library (NNFL)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Davydov, Jerry; Dion, Heather; LaMont, Stephen

    A National Nuclear Forensics Library (NNFL) assists a State to assess whether nuclear material encountered out of regulatory control is of domestic or international origin. And by leveraging nuclear material registries, nuclear enterprise records, and safeguards accountancy information, as well as existing domestic technical capability and subject-matter domain expertise, states can better assess the effort required for setting up an NNFL. For states who are largely recipients of nuclear and radiological materials and have no internal production capabilities may create an NNFL that relies on existing information rather than carry out advanced analyses on domestic materials.

  8. Leveraging existing information for use in a National Nuclear Forensics Library (NNFL)

    DOE PAGES

    Davydov, Jerry; Dion, Heather; LaMont, Stephen; ...

    2015-12-16

    A National Nuclear Forensics Library (NNFL) assists a State to assess whether nuclear material encountered out of regulatory control is of domestic or international origin. And by leveraging nuclear material registries, nuclear enterprise records, and safeguards accountancy information, as well as existing domestic technical capability and subject-matter domain expertise, states can better assess the effort required for setting up an NNFL. For states who are largely recipients of nuclear and radiological materials and have no internal production capabilities may create an NNFL that relies on existing information rather than carry out advanced analyses on domestic materials.

  9. Project Report on Development of a Safeguards Approach for Pyroprocessing

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Robert Bean

    The Idaho National Laboratory has undertaken an effort to develop a standard safeguards approach for international commercial pyroprocessing facilities. This report details progress for the fiscal year 2010 effort. A component by component diversion pathway analysis has been performed, and has led to insight on the mitigation needs and equipment development needed for a valid safeguards approach. The effort to develop an in-hot cell detection capability led to the digital cloud chamber, and more importantly, the significant potential scientific breakthrough of the inverse spectroscopy algorithm, including the ability to identify energy and spatial location of gamma ray emitting sources withmore » a single, non-complex, stationary radiation detector system. Curium measurements were performed on historical and current samples at the FCF to attempt to determine the utility of using gross neutron counting for accountancy measurements. A solid cost estimate of equipment installation at FCF has been developed to guide proposals and cost allocations to use FCF as a test bed for safeguards measurement demonstrations. A combined MATLAB and MCNPX model has been developed to perform detector placement calculations around the electrorefiner. Early harvesting has occurred wherein the project team has been requested to provide pyroprocessing technology and safeguards short courses.« less

  10. Advancing the Fork detector for quantitative spent nuclear fuel verification

    DOE PAGES

    Vaccaro, S.; Gauld, I. C.; Hu, J.; ...

    2018-01-31

    The Fork detector is widely used by the safeguards inspectorate of the European Atomic Energy Community (EURATOM) and the International Atomic Energy Agency (IAEA) to verify spent nuclear fuel. Fork measurements are routinely performed for safeguards prior to dry storage cask loading. Additionally, spent fuel verification will be required at the facilities where encapsulation is performed for acceptance in the final repositories planned in Sweden and Finland. The use of the Fork detector as a quantitative instrument has not been prevalent due to the complexity of correlating the measured neutron and gamma ray signals with fuel inventories and operator declarations.more » A spent fuel data analysis module based on the ORIGEN burnup code was recently implemented to provide automated real-time analysis of Fork detector data. This module allows quantitative predictions of expected neutron count rates and gamma units as measured by the Fork detectors using safeguards declarations and available reactor operating data. This study describes field testing of the Fork data analysis module using data acquired from 339 assemblies measured during routine dry cask loading inspection campaigns in Europe. Assemblies include both uranium oxide and mixed-oxide fuel assemblies. More recent measurements of 50 spent fuel assemblies at the Swedish Central Interim Storage Facility for Spent Nuclear Fuel are also analyzed. An evaluation of uncertainties in the Fork measurement data is performed to quantify the ability of the data analysis module to verify operator declarations and to develop quantitative go/no-go criteria for safeguards verification measurements during cask loading or encapsulation operations. The goal of this approach is to provide safeguards inspectors with reliable real-time data analysis tools to rapidly identify discrepancies in operator declarations and to detect potential partial defects in spent fuel assemblies with improved reliability and minimal false

  11. Advancing the Fork detector for quantitative spent nuclear fuel verification

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vaccaro, S.; Gauld, I. C.; Hu, J.

    The Fork detector is widely used by the safeguards inspectorate of the European Atomic Energy Community (EURATOM) and the International Atomic Energy Agency (IAEA) to verify spent nuclear fuel. Fork measurements are routinely performed for safeguards prior to dry storage cask loading. Additionally, spent fuel verification will be required at the facilities where encapsulation is performed for acceptance in the final repositories planned in Sweden and Finland. The use of the Fork detector as a quantitative instrument has not been prevalent due to the complexity of correlating the measured neutron and gamma ray signals with fuel inventories and operator declarations.more » A spent fuel data analysis module based on the ORIGEN burnup code was recently implemented to provide automated real-time analysis of Fork detector data. This module allows quantitative predictions of expected neutron count rates and gamma units as measured by the Fork detectors using safeguards declarations and available reactor operating data. This study describes field testing of the Fork data analysis module using data acquired from 339 assemblies measured during routine dry cask loading inspection campaigns in Europe. Assemblies include both uranium oxide and mixed-oxide fuel assemblies. More recent measurements of 50 spent fuel assemblies at the Swedish Central Interim Storage Facility for Spent Nuclear Fuel are also analyzed. An evaluation of uncertainties in the Fork measurement data is performed to quantify the ability of the data analysis module to verify operator declarations and to develop quantitative go/no-go criteria for safeguards verification measurements during cask loading or encapsulation operations. The goal of this approach is to provide safeguards inspectors with reliable real-time data analysis tools to rapidly identify discrepancies in operator declarations and to detect potential partial defects in spent fuel assemblies with improved reliability and minimal false

  12. Advancing the Fork detector for quantitative spent nuclear fuel verification

    NASA Astrophysics Data System (ADS)

    Vaccaro, S.; Gauld, I. C.; Hu, J.; De Baere, P.; Peterson, J.; Schwalbach, P.; Smejkal, A.; Tomanin, A.; Sjöland, A.; Tobin, S.; Wiarda, D.

    2018-04-01

    The Fork detector is widely used by the safeguards inspectorate of the European Atomic Energy Community (EURATOM) and the International Atomic Energy Agency (IAEA) to verify spent nuclear fuel. Fork measurements are routinely performed for safeguards prior to dry storage cask loading. Additionally, spent fuel verification will be required at the facilities where encapsulation is performed for acceptance in the final repositories planned in Sweden and Finland. The use of the Fork detector as a quantitative instrument has not been prevalent due to the complexity of correlating the measured neutron and gamma ray signals with fuel inventories and operator declarations. A spent fuel data analysis module based on the ORIGEN burnup code was recently implemented to provide automated real-time analysis of Fork detector data. This module allows quantitative predictions of expected neutron count rates and gamma units as measured by the Fork detectors using safeguards declarations and available reactor operating data. This paper describes field testing of the Fork data analysis module using data acquired from 339 assemblies measured during routine dry cask loading inspection campaigns in Europe. Assemblies include both uranium oxide and mixed-oxide fuel assemblies. More recent measurements of 50 spent fuel assemblies at the Swedish Central Interim Storage Facility for Spent Nuclear Fuel are also analyzed. An evaluation of uncertainties in the Fork measurement data is performed to quantify the ability of the data analysis module to verify operator declarations and to develop quantitative go/no-go criteria for safeguards verification measurements during cask loading or encapsulation operations. The goal of this approach is to provide safeguards inspectors with reliable real-time data analysis tools to rapidly identify discrepancies in operator declarations and to detect potential partial defects in spent fuel assemblies with improved reliability and minimal false positive alarms

  13. 45 CFR 164.312 - Technical safeguards.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 45 Public Welfare 1 2014-10-01 2014-10-01 false Technical safeguards. 164.312 Section 164.312 Public Welfare Department of Health and Human Services ADMINISTRATIVE DATA STANDARDS AND RELATED REQUIREMENTS SECURITY AND PRIVACY Security Standards for the Protection of Electronic Protected Health...

  14. 34 CFR 300.121 - Procedural safeguards.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 34 Education 2 2010-07-01 2010-07-01 false Procedural safeguards. 300.121 Section 300.121 Education Regulations of the Offices of the Department of Education (Continued) OFFICE OF SPECIAL EDUCATION AND REHABILITATIVE SERVICES, DEPARTMENT OF EDUCATION ASSISTANCE TO STATES FOR THE EDUCATION OF...

  15. 40 CFR 2.211 - Safeguarding of business information; penalty for wrongful disclosure.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... for his or her private gain or advantage, any business information which came into his or her... any security procedures for handling and safeguarding business information which are contained in any... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Safeguarding of business information...

  16. Applications of nuclear physics

    NASA Astrophysics Data System (ADS)

    Hayes, A. C.

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  17. Applications of nuclear physics

    DOE PAGES

    Hayes-Sterbenz, Anna Catherine

    2017-01-10

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applicationsmore » of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Lastly, each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.« less

  18. Applications of nuclear physics.

    PubMed

    Hayes, A C

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  19. Applications of nuclear physics

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hayes-Sterbenz, Anna Catherine

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applicationsmore » of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Lastly, each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.« less

  20. Hybrid Interferometric/Dispersive Atomic Spectroscopy For Nuclear Materials Analysis

    NASA Astrophysics Data System (ADS)

    Morgan, Phyllis K.

    Laser-induced breakdown spectroscopy (LIBS) is an optical emission spectroscopy technique that holds promise for detection and rapid analysis of elements relevant for nuclear safeguards and nonproliferation, including the measurement of isotope ratios. One important application of LIBS is the measurement of uranium enrichment (235U/238U), which requires high spectral resolution (e.g., 25 pm for the 424.437 nm U II line). Measuring uranium enrichment is important in nuclear nonproliferation and safeguards because the uranium highly enriched in the 235U isotope can be used to construct nuclear weapons. High-resolution dispersive spectrometers necessary for such measurements are typically bulky and expensive. A hybrid interferometric/dispersive spectrometer prototype, which consists of an inexpensive, compact Fabry-Perot etalon integrated with a low to moderate resolution Czerny-Turner spectrometer, was assembled for making high-resolution measurements of nuclear materials in a laboratory setting. To more fully take advantage of this low-cost, compact hybrid spectrometer, a mathematical reconstruction technique was developed to accurately reconstruct relative line strengths from complex spectral patterns with high resolution. Measurement of the mercury 313.1555/313.1844 nm doublet from a mercury-argon lamp yielded a spectral line intensity ratio of 0.682, which agrees well with an independent measurement by an echelle spectrometer and previously reported values. The hybrid instrument was used in LIBS measurements and achieved the resolution needed for isotopic selectivity of LIBS of uranium in ambient air. The samples used were a natural uranium foil (0.7% of 235U) and a uranium foil highly enriched in 235U to 93%. Both samples were provided by the Penn State University's Breazeale Nuclear Reactor. The enrichment of the uranium foils was verified using a high-purity germanium detector and dedicated software for multi-group spectral analysis. Uranium spectral line