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...

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...

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...

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...

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.

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

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

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

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

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...

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.

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

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

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

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

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

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

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

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

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

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

10 CFR 75.36 - Special reports.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Special reports. 75.36 Section 75.36 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) SAFEGUARDS ON NUCLEAR MATERIAL-IMPLEMENTATION OF US/IAEA AGREEMENT Reports § 75.36 Special reports. (a) This section applies only to licenses or certificate holders who have been...

10 CFR 75.36 - Special reports.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Special reports. 75.36 Section 75.36 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) SAFEGUARDS ON NUCLEAR MATERIAL-IMPLEMENTATION OF US/IAEA AGREEMENT Reports § 75.36 Special reports. (a) This section applies only to licenses or certificate holders who have been...

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.

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

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

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

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

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.

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.

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.

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

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

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

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.

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

Rattling Nucleons: New Developments in Active Interrogation of Special Nuclear Material

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

Robert C. Runkle; David L. Chichester; Scott J. Thompson

2012-01-01

Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding - special nuclear material itself, incidental materials, or intentional shielding - and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important formore » nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.« less

Rattling nucleons: New developments in active interrogation of special nuclear material

NASA Astrophysics Data System (ADS)

Runkle, Robert C.; Chichester, David L.; Thompson, Scott J.

2012-01-01

Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding—special nuclear material itself, incidental materials, or intentional shielding—and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important for nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.

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.

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...

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...

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

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

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...

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...

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

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

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...

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...

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...

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...

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

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

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.

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

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

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

Applications of a Fast Neutron Detector System to Verification of Special Nuclear Materials

NASA Astrophysics Data System (ADS)

Mayo, Douglas R.; Byrd, Roger C.; Ensslin, Norbert; Krick, Merlyn S.; Mercer, David J.; Miller, Michael C.; Prettyman, Thomas H.; Russo, Phyllis A.

1998-04-01

An array of boron-loaded plastic optically coupled to bismuth germanate scintillators has been developed to detect neutrons for measurement of special nuclear materials. The phoswiched detection system has the advantage of a high neutron detection efficiency and short die-away time. This is achieved by mixing the moderator (plastic) and the detector (^10B) at the molecular level. Simulations indicate that the neutron capture probabilities equal or exceed those of the current thermal neutron multiplicity techniques which have the moderator (polyethylene) and detectors (^3He gas proportional tubes) macroscopically separate. Experiments have been performed to characterize the response of these detectors and validate computer simulations. The fast neutron detection system may be applied to the quantitative assay of plutonium in high (α,n) backgrounds, with emphasis on safeguards and enviromental scenarios. Additional applications of the insturment, in a non-quantative mode, has been tested for possible verification activities involving dismantlement of nuclear weapons. A description of the detector system, simulations and preliminary data will be presented.

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

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

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

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

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

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

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

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

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

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

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...

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

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

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

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.

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...

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

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

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...

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...

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

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.

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...

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

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

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...

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...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

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

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.

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...

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

78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

Federal Register 2010, 2011, 2012, 2013, 2014

2013-06-27

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0109] Special Nuclear Material Control and Accounting... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

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

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

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...

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...

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...

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...

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

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

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

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

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

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

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Nuclear material control and accounting for special nuclear material of low strategic significance. 74.31 Section 74.31 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material of Low...

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Nuclear material control and accounting for special nuclear material of low strategic significance. 74.31 Section 74.31 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material of Low...

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Nuclear material control and accounting for special nuclear material of low strategic significance. 74.31 Section 74.31 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material of Low...

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Nuclear material control and accounting for special nuclear material of low strategic significance. 74.31 Section 74.31 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material of Low...

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

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

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...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 1 2013-01-01 2013-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 1 2011-01-01 2011-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 1 2014-01-01 2014-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

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...

Special nuclear material simulation device

DOEpatents

Leckey, John H.; DeMint, Amy; Gooch, Jack; Hawk, Todd; Pickett, Chris A.; Blessinger, Chris; York, Robbie L.

2014-08-12

An apparatus for simulating special nuclear material is provided. The apparatus typically contains a small quantity of special nuclear material (SNM) in a configuration that simulates a much larger quantity of SNM. Generally the apparatus includes a spherical shell that is formed from an alloy containing a small quantity of highly enriched uranium. Also typically provided is a core of depleted uranium. A spacer, typically aluminum, may be used to separate the depleted uranium from the shell of uranium alloy. A cladding, typically made of titanium, is provided to seal the source. Methods are provided to simulate SNM for testing radiation monitoring portals. Typically the methods use at least one primary SNM spectral line and exclude at least one secondary SNM spectral line.

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...

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...

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

34 CFR 300.121 - Procedural safeguards.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 34 Education 2 2011-07-01 2010-07-01 true 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 CHILDREN WITH...

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

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

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 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

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

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.

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 1 2013-01-01 2013-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 1 2011-01-01 2011-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 1 2014-01-01 2014-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

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...

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...

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...

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

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

34 CFR 300.504 - Procedural safeguards notice.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 34 Education 2 2010-07-01 2010-07-01 false Procedural safeguards notice. 300.504 Section 300.504 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...

Uncertainty quantification in application of the enrichment meter principle for nondestructive assay of special nuclear material

DOE PAGES

Burr, Tom; Croft, Stephen; Jarman, Kenneth D.

2015-09-05

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 quantify total uncertainty in terms of “random” and “systematic” components, and then specify error bars for the total mass estimate in multiple items. Uncertainty quantification (UQ) for NDA has always been important, but it is recognized that greater rigor is needed andmore » achievable using modern statistical methods. To this end, we describe the extent to which the guideline for expressing uncertainty in measurements (GUM) can be used for NDA. Also, we propose improvements over GUM for NDA by illustrating UQ challenges that it does not address, including calibration with errors in predictors, model error, and item-specific biases. A case study is presented using low-resolution NaI spectra and applying the enrichment meter principle to estimate the U-235 mass in an item. The case study illustrates how to update the current American Society for Testing and Materials guide for application of the enrichment meter principle using gamma spectra from a NaI detector.« less

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.

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

76 FR 62857 - Notice of Acceptance of Application for Special Nuclear Materials Licensen From Rapiscan...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-10-11

... the following methods: NRC's Public Document Room (PDR): The public may examine and have copied, for a... Manager, Fuel Manufacturing Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear... systems. The SNM would be used as test objects for concept demonstrations and characterization testing...

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...

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...

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...

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...

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 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...

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...

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...

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...

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...

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

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

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

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.

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

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

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

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

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...

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

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

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

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.

10 CFR 73.72 - Requirement for advance notice of shipment of formula quantities of strategic special nuclear...

Code of Federal Regulations, 2012 CFR

2012-01-01

... quantities of strategic special nuclear material, special nuclear material of moderate strategic significance, or irradiated reactor fuel. 73.72 Section 73.72 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED... shipment of formula quantities of strategic special nuclear material, special nuclear material of moderate...

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...

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...

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...

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...

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...

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

10 CFR 11.16 - Cancellation of request for special nuclear material access authorization.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 1 2013-01-01 2013-01-01 false Cancellation of request for special nuclear material access authorization. 11.16 Section 11.16 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for...

10 CFR 11.16 - Cancellation of request for special nuclear material access authorization.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 1 2014-01-01 2014-01-01 false Cancellation of request for special nuclear material access authorization. 11.16 Section 11.16 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for...

10 CFR 11.16 - Cancellation of request for special nuclear material access authorization.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false Cancellation of request for special nuclear material access authorization. 11.16 Section 11.16 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for...

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

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

48 CFR 1850.403 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 48 Federal Acquisition Regulations System 6 2011-10-01 2011-10-01 false Special procedures for unusually hazardous or nuclear risks. 1850.403 Section 1850.403 Federal Acquisition Regulations System... Residual Powers 1850.403 Special procedures for unusually hazardous or nuclear risks. ...

48 CFR 1850.403 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Special procedures for unusually hazardous or nuclear risks. 1850.403 Section 1850.403 Federal Acquisition Regulations System... Residual Powers 1850.403 Special procedures for unusually hazardous or nuclear risks. ...

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

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 ...

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

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

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...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

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...

76 FR 63672 - Notice of Acceptance of Application for Special Nuclear Materials License From Passport Systems...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-10-13

... Application for Special Nuclear Materials License From Passport Systems, Inc., Opportunity To Request a... special nuclear material (SNM), submitted by Passport Systems, Inc. (Passport or the Applicant). The..., if approved, would authorize Passport to possess and use special nuclear materials under 10 CFR Part...

Neutron interrogation system using high gamma ray signature to detect contraband special nuclear materials in cargo

DOEpatents

Slaughter, Dennis R.; Pohl, Bertram A.; Dougan, Arden D.; Bernstein, Adam; Prussin, Stanley G.; Norman, Eric B.

2008-04-15

A system for inspecting cargo for the presence of special nuclear material. The cargo is irradiated with neutrons. The neutrons produce fission products in the special nuclear material which generate gamma rays. The gamma rays are detecting indicating the presence of the special nuclear material.

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)

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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.

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...

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

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

48 CFR 1450.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2014 CFR

2014-10-01

... 48 Federal Acquisition Regulations System 5 2014-10-01 2014-10-01 false Special procedures for unusually hazardous or nuclear risks. 1450.104-3 Section 1450.104-3 Federal Acquisition Regulations System... Extraordinary Contractual Actions 1450.104-3 Special procedures for unusually hazardous or nuclear risks. The CO...

48 CFR 1450.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Special procedures for unusually hazardous or nuclear risks. 1450.104-3 Section 1450.104-3 Federal Acquisition Regulations System... Extraordinary Contractual Actions 1450.104-3 Special procedures for unusually hazardous or nuclear risks. The CO...

48 CFR 1450.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2013 CFR

2013-10-01

... 48 Federal Acquisition Regulations System 5 2013-10-01 2013-10-01 false Special procedures for unusually hazardous or nuclear risks. 1450.104-3 Section 1450.104-3 Federal Acquisition Regulations System... Extraordinary Contractual Actions 1450.104-3 Special procedures for unusually hazardous or nuclear risks. The CO...

48 CFR 1450.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 48 Federal Acquisition Regulations System 5 2011-10-01 2011-10-01 false Special procedures for unusually hazardous or nuclear risks. 1450.104-3 Section 1450.104-3 Federal Acquisition Regulations System... Extraordinary Contractual Actions 1450.104-3 Special procedures for unusually hazardous or nuclear risks. The CO...

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

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

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

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

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

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...

19 CFR 201.27 - Special procedures: Medical records.

Code of Federal Regulations, 2014 CFR

2014-04-01

... 19 Customs Duties 3 2014-04-01 2014-04-01 false Special procedures: Medical records. 201.27... APPLICATION Safeguarding Individual Privacy Pursuant to 5 U.S.C. 552a § 201.27 Special procedures: Medical... maintained by the Commission which pertain to him or her, medical and psychological records merit special...

The Attractiveness of Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios

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

Bathke, C. G.; Wallace, R. K.; Ireland, J. R.

2010-09-01

This paper is an extension to earlier studies1,2 that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, COEX, 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. The primary conclusion of this study is that all fissile material needs to 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 beenmore » 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

The attractiveness of materials in advanced nuclear fuel cycles for various proliferation and theft scenarios

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, COEX, 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. The primary conclusion of this study is that all fissile material needs to 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 beenmore » 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

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...

Detecting special nuclear materials in containers using high-energy gamma rays emitted by fission products

DOEpatents

Norman, Eric B.; Prussin, Stanley G.

2007-10-02

A method and a system for detecting the presence of special nuclear materials in a container. The system and its method include irradiating the container with an energetic beam, so as to induce a fission in the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

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

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...

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...

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.

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...

Active and Passive Diagnostic Signatures of Special Nuclear Materials

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

Myers, William L.; Karpius, Peter Joseph; Myers, Steven Charles

2017-05-26

An overview will be given discussing signatures associated with special nuclear materials acquired using both active and passive diagnostic techniques. Examples of how technology advancements have helped improve diagnostic capabilities to meet the challenges of today’s applications will be discussed.

Making It My IDEA: Notice of Procedural Safeguards Designed for Increased Readability

ERIC Educational Resources Information Center

Dinnesen, Megan Schneider

2013-01-01

Procedural safeguards have been in place for years with the intention of protecting the rights of parents and their children with disabilities. Despite the promises of the Individuals with Disabilities Education Act, parents have not been given the tools they need to be active participants in their child's special education. Parents of children…

The Rights of Infants and Toddlers with Special Needs. Revised

ERIC Educational Resources Information Center

Tennessee Department of Education, 2007

2007-01-01

IDEA stands for The Individuals with Disabilities Education Act, which is the law that requires special services for children with disabilities from birth through the age of twenty-one years. This law has established the regulations on which the procedural safeguards in this booklet are based. The ten safeguards discussed include the right to:…

15 CFR 740.11 - Governments, international organizations, and international inspections under the Chemical...

Code of Federal Regulations, 2010 CFR

2010-01-01

... use. The IAEA is an international organization that establishes and administers safeguards designed to.... Euratom establishes and administers safeguards designed to ensure that special nuclear materials and other... or Euratom international safeguards use provided that IAEA or Euratom maintains control of or...

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...

48 CFR 50.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2012 CFR

2012-10-01

... unusually hazardous or nuclear risks. 50.104-3 Section 50.104-3 Federal Acquisition Regulations System... Extraordinary Contractual Actions 50.104-3 Special procedures for unusually hazardous or nuclear risks. (a... nuclear risks should be submitted to the contracting officer and shall include the following information...

48 CFR 50.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2013 CFR

2013-10-01

... unusually hazardous or nuclear risks. 50.104-3 Section 50.104-3 Federal Acquisition Regulations System... Extraordinary Contractual Actions 50.104-3 Special procedures for unusually hazardous or nuclear risks. (a... nuclear risks should be submitted to the contracting officer and shall include the following information...

48 CFR 50.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2014 CFR

2014-10-01

... unusually hazardous or nuclear risks. 50.104-3 Section 50.104-3 Federal Acquisition Regulations System... Extraordinary Contractual Actions 50.104-3 Special procedures for unusually hazardous or nuclear risks. (a... nuclear risks should be submitted to the contracting officer and shall include the following information...

48 CFR 50.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2011 CFR

2011-10-01

... unusually hazardous or nuclear risks. 50.104-3 Section 50.104-3 Federal Acquisition Regulations System... Extraordinary Contractual Actions 50.104-3 Special procedures for unusually hazardous or nuclear risks. (a... nuclear risks should be submitted to the contracting officer and shall include the following information...

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

Uncovering Special Nuclear Materials by Low-energy Nuclear Reaction Imaging

NASA Astrophysics Data System (ADS)

Rose, P. B.; Erickson, A. S.; Mayer, M.; Nattress, J.; Jovanovic, I.

2016-04-01

Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as “searching for a needle in a haystack” because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded special nuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method from being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material’s areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications.

Uncovering Special Nuclear Materials by Low-energy Nuclear Reaction Imaging

PubMed Central

Rose, P. B.; Erickson, A. S.; Mayer, M.; Nattress, J.; Jovanovic, I.

2016-01-01

Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as “searching for a needle in a haystack” because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded special nuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method from being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material’s areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications. PMID:27087555

Uncovering Special Nuclear Materials by Low-energy Nuclear Reaction Imaging.

PubMed

Rose, P B; Erickson, A S; Mayer, M; Nattress, J; Jovanovic, I

2016-04-18

Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as "searching for a needle in a haystack" because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded special nuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method from being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material's areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications.

Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products

DOEpatents

Norman, Eric B [Oakland, CA; Prussin, Stanley G [Kensington, CA

2009-05-05

A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products

DOEpatents

Norman, Eric B [Oakland, CA; Prussin, Stanley G [Kensington, CA

2009-01-27

A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products

DOEpatents

Norman, Eric B [Oakland, CA; Prussin, Stanley G [Kensington, CA

2009-01-06

A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

77 FR 60482 - Regulatory Guide 5.67, Material Control and Accounting for Uranium Enrichment Facilities...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-10-03

... Accounting for Uranium Enrichment Facilities Authorized To Produce Special Nuclear Material of Low Strategic... Accounting for Uranium Enrichment Facilities Authorized to Produce Special Nuclear Material of Low Strategic... INFORMATION CONTACT: Glenn Tuttle, Office of Nuclear Material Safety and Safeguards, Division of Fuel Cycle...

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

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

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

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

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.

48 CFR 250.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Special procedures for unusually hazardous or nuclear risks. 250.104-3 Section 250.104-3 Federal Acquisition Regulations System... unusually hazardous or nuclear risks. ...

48 CFR 250.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2014 CFR

2014-10-01

... 48 Federal Acquisition Regulations System 3 2014-10-01 2014-10-01 false Special procedures for unusually hazardous or nuclear risks. 250.104-3 Section 250.104-3 Federal Acquisition Regulations System... unusually hazardous or nuclear risks. ...

48 CFR 250.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2013 CFR

2013-10-01

... 48 Federal Acquisition Regulations System 3 2013-10-01 2013-10-01 false Special procedures for unusually hazardous or nuclear risks. 250.104-3 Section 250.104-3 Federal Acquisition Regulations System... unusually hazardous or nuclear risks. ...

48 CFR 250.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 48 Federal Acquisition Regulations System 3 2011-10-01 2011-10-01 false Special procedures for unusually hazardous or nuclear risks. 250.104-3 Section 250.104-3 Federal Acquisition Regulations System... unusually hazardous or nuclear risks. ...

48 CFR 250.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2012 CFR

2012-10-01

... 48 Federal Acquisition Regulations System 3 2012-10-01 2012-10-01 false Special procedures for unusually hazardous or nuclear risks. 250.104-3 Section 250.104-3 Federal Acquisition Regulations System... unusually hazardous or nuclear risks. ...

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...

10 CFR 1016.24 - Special handling of classified material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Special handling of classified material. 1016.24 Section 1016.24 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security § 1016.24 Special handling of classified material. When the Restricted Data contained in material...

10 CFR 1016.24 - Special handling of classified material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Special handling of classified material. 1016.24 Section 1016.24 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security § 1016.24 Special handling of classified material. When the Restricted Data contained in material...

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.

Uncovering Special Nuclear Materials by Low-energy Nuclear Reaction Imaging

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

Rose, Jr., P. B.; Erickson, A. S.; Mayer, Michael F.

Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as “searching for a needle in a haystack” because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded special nuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method frommore » being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material’s areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications.« less

Uncovering Special Nuclear Materials by Low-energy Nuclear Reaction Imaging

DOE PAGES

Rose, P. B.; Erickson, A. S.; Mayer, M.; ...

2016-04-18

Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as “searching for a needle in a haystack” because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded special nuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method frommore » being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material’s areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications.« less

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...

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.

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...

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

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...

48 CFR 1850.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2014 CFR

2014-10-01

... 48 Federal Acquisition Regulations System 6 2014-10-01 2014-10-01 false Special procedures for unusually hazardous or nuclear risks. 1850.104-3 Section 1850.104-3 Federal Acquisition Regulations System... nuclear risks. (a) Indemnification requests. (1) Contractor indemnification requests must be submitted to...

48 CFR 1850.104-3 - Special procedures for unusually hazardous or nuclear risks.

Code of Federal Regulations, 2012 CFR

2012-10-01

... 48 Federal Acquisition Regulations System 6 2012-10-01 2012-10-01 false Special procedures for unusually hazardous or nuclear risks. 1850.104-3 Section 1850.104-3 Federal Acquisition Regulations System... nuclear risks. (a) Indemnification requests. (1) Contractor indemnification requests must be submitted to...

Rapid response sensor for analyzing Special Nuclear Material

DOE PAGES

Mitra, S. S.; Doron, O.; Chen, A. X.; ...

2015-06-18

Rapid in-situ analytical techniques are attractive for characterizing Special Nuclear Material (SNM). Present techniques are time consuming, and require sample dissolution. Proof-of-principal studies are performed to demonstrate the utility of employing low energy neutrons from a portable pulsed neutron generator for non-destructive isotopic analysis of nuclear material. In particular, time-sequenced data acquisition, operating synchronously with the pulsing of a neutron generator, partitions the characteristic elemental prompt gamma-rays according to the type of the reaction; inelastic neutron scattering reactions during the ON state and thermal neutron capture reactions during the OFF state of the generator. Thus, the key challenge is isolatingmore » these signature gamma- rays from the prompt fission and β-delayed gamma-rays that are also produced during the neutron interrogation. A commercial digital multi-channel analyzer has been specially customized to enable time-resolved gamma-ray spectral data to be acquired in multiple user-defined time bins within each of the ON/OFF gate periods of the neutron generator. Preliminary results on new signatures from depleted uranium as well as modeling and benchmarking of the concept are presented, however this approach should should be applicable for virtually all forms of SNM.« less

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...

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

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...

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...

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...

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...

New Brunswick Laboratory: Progress report, October 1987--September 1988

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

Not Available

NBL has been tasked by the DOE Office of Safeguards and Security, Defense Programs (OSS/DP) to assure the application of accurate and reliable measurement technology for the safeguarding of special nuclear materials. NBL is fulfilling its mission responsibilities by identifying and addressing the measurement and measurement-related needs of the nuclear material safeguards community. These responsibilities are being addressed by activities in the following program areas: (1) reference and calibration materials, (2) measurement development, (3) measurement services, (4) measurement evaluation, (5) safeguards assessment, and (6) site-specific assistance. Highlights of each of these programs areas are provided in this summary.

U.S.-Russian cooperation in nuclear disarmament and nonproliferation

NASA Astrophysics Data System (ADS)

Podvig, Pavel

2010-02-01

The United States and Russia, the two largest nuclear powers, have a special obligation to provide leadership in nuclear disarmament and in strengthening the nuclear non-proliferation regime. In the past year the two countries made an effort to restart the arms control process by concluding a new treaty that would bring their legal disarmament obligations in line with the realities of their post-cold war relationships. The process of negotiating deeper nuclear reductions in the new environment turned out to be rather difficult, since the approaches that the countries used in the past are not well suited to dealing with issues like conversion of strategic nuclear delivery systems to conventional missions, tactical nuclear weapons, or dismantlement of nuclear warheads. This presentation considers the recent progress in U.S.-Russian arms control process and outlines the key issues at the negotiations. It also considers prospects for further progress in bilateral nuclear disarmament and issues that will be encountered at later stages of the process. The author argues that success of the arms reductions will depend on whether the United States and Russia will be able to build an institutional framework for cooperation on a range of issues - from traditional arms control to securing nuclear materials and from missile defense to strengthening the international nuclear safeguards. )

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...

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

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...

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...

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...

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...

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...

Preface: Special Topic on Nuclear Quantum Effects

NASA Astrophysics Data System (ADS)

Tuckerman, Mark; Ceperley, David

2018-03-01

Although the observable universe strictly obeys the laws of quantum mechanics, in many instances, a classical description that either ignores quantum effects entirely or accounts for them at a very crude level is sufficient to describe a wide variety of phenomena. However, when this approximation breaks down, as is often the case for processes involving light nuclei, a full quantum treatment becomes indispensable. This Special Topic in The Journal of Chemical Physics showcases recent advances in our understanding of nuclear quantum effects in condensed phases as well as novel algorithmic developments and applications that have enhanced the capability to study these effects.

Preface: Special Topic on Nuclear Quantum Effects.

PubMed

Tuckerman, Mark; Ceperley, David

2018-03-14

Although the observable universe strictly obeys the laws of quantum mechanics, in many instances, a classical description that either ignores quantum effects entirely or accounts for them at a very crude level is sufficient to describe a wide variety of phenomena. However, when this approximation breaks down, as is often the case for processes involving light nuclei, a full quantum treatment becomes indispensable. This Special Topic in The Journal of Chemical Physics showcases recent advances in our understanding of nuclear quantum effects in condensed phases as well as novel algorithmic developments and applications that have enhanced the capability to study these effects.

Semi-annual report on strategic special nuclear material inventory differences

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

Not Available

1978-01-01

This periodic report of Inventory Differences covers the period October 1, 1976, through March 31, 1977 for Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of Strategic Special Nuclear Material (SSNM). Included in this report are the low enriched uranium inventory differences for DOE's gaseous diffusion plant cascades. (LK)

THE ATTRACTIVENESS OF MATERIALS IN ADVANCED NUCLEAR FUEL CYCLES FOR VARIOUS PROLIFERATION AND THEFT SCENARIOS

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

Bathke, C. G.; Ebbinghaus, Bartley B.; Collins, Brian A.

2012-08-29

We must anticipate that the day is approaching when details of nuclear weapons design and fabrication will become common knowledge. On that day we must be particularly certain that all special nuclear materials (SNM) are adequately accounted for and protected and that we have a clear understanding of the utility of nuclear materials to potential adversaries. To this end, this paper examines the attractiveness of materials mixtures containing SNM and alternate nuclear materials associated with the plutonium-uranium reduction extraction (Purex), uranium extraction (UREX), coextraction (COEX), thorium extraction (THOREX), and PYROX (an electrochemical refining method) reprocessing schemes. This paper provides amore » set of figures of merit for evaluating material attractiveness that covers a broad range of proliferant state and subnational group capabilities. The primary conclusion of this paper is that all fissile material must be rigorously safeguarded to detect diversion by a state and must be provided the highest levels of physical protection to prevent theft by subnational groups; no 'silver bullet' fuel cycle has been found that will permit the relaxation of current international safeguards or national physical security protection levels. The work reported herein has been performed at the request of the U.S. Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for, the nuclear materials in DOE nuclear facilities. The methodology and findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security is discussed.« less

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...

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...

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...

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...

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...

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...

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

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...

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...

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...

An assessment of the attractiveness of material associated with thorium/uranium and uranium closed fuel cycles from a safeguards perspective

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

Bathke, Charles Gary; Wallace, Richard K; Hase, Kevin R

2010-01-01

This paper reports the continued evaluation of the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with various proposed nuclear fuel cycles. Specifically, this paper examines two closed fuel cycles. The first fuel cycle examined is a thorium fuel cycle in which a pressurized heavy water reactor (PHWR) is fueled with mixtures of plutonium/thorium and {sup 233}U/thorium. The used fuel is then reprocessed using the THOREX process and the actinides are recycled. The second fuel cycle examined consists of conventional light water reactors (LWR) whose fuel is reprocessed for actinides that are then fed to and recycled untilmore » consumed in fast-spectrum reactors: fast reactors and accelerator driven systems (ADS). As reprocessing of LWR fuel has already been examined, this paper will focus on the reprocessing of the scheme's fast-spectrum reactors' fuel. This study will indicate what is required to render these materials as having low utility for use in nuclear weapons. Nevertheless, the results of this paper suggest that all reprocessing products evaluated so far need to be rigorously safeguarded and provided high levels of physical protection. These studies were performed at the request of the United States Department of Energy (DOE). The methodology and key findings will be presented.« less

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2010 CFR

2010-01-01

... and maintain a measurement system which assures that all quantities in the material accounting records...) In each inventory period, control total material control and accounting measurement uncertainty so... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special...

15 CFR 740.11 - Governments, international organizations, international inspections under the Chemical Weapons...

Code of Federal Regulations, 2014 CFR

2014-01-01

..., including Additional Protocols, designed to ensure that special nuclear materials and other related nuclear... headquarters in Luxembourg. Euratom establishes and administers safeguards designed to ensure that special... the aggregation exceeds the APP parameter set forth in ECCN 4A003.b. (v) “600 series” items may not be...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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.

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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 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...

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...

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...

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...

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.

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...

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.

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.

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

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...

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...

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...

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...

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...

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...

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...

Nuclear positioning by actin cables and perinuclear actin: Special and general?

PubMed

Huelsmann, Sven; Brown, Nicholas H

2014-01-01

Nuclear positioning is an important process during development and homeostasis. Depending on the affected tissue, mislocalized nuclei can alter cellular processes such as polarization, differentiation, or migration and lead ultimately to diseases. Many cells actively control the position of their nucleus using their cytoskeleton and motor proteins. We have recently shown that during Drosophila oogenesis, nurse cells employ cytoplasmic actin cables in association with perinuclear actin to position their nucleus. Here, we briefly summarize our work and discuss why nuclear positioning in nurse cells is specialized but the molecular mechanisms are likely to be more generally used.

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

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

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

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

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

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...

Audit Oversight: Quality Control System at U.S. Special Operations Command Inspector General Audit Division

DTIC Science & Technology

2002-08-21

The Audit Division provides the Commander, U.S. Special Operations Command (USSOCOM) with professional auditing services to safeguard, account for...and ensure the proper use of special operations forces assets in accomplishing the USSOCOM mission. The Audit Division reports to the USSOCOM Inspector...U.S. Army Special Operations Command, Naval Special Warfare Command, and the Joint Special Operations Command. Appendix A contains a summary of the Audit Division policy and procedures.

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...

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