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Sample records for relevant biodiversity safeguards

  1. Thorium based power systems and relevant safeguards considerations

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Thorium based power systems and relevant safeguards considerations Citation Details In-Document Search Title: Thorium based power systems and relevant safeguards considerations Ă— You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit OSTI to utilize additional information resources in energy science and

  2. Thorium based power systems and relevant safeguards considerations

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Conference: Thorium based power systems and relevant safeguards considerations Citation Details In-Document Search Title: Thorium based power systems and relevant safeguards considerations Authors: Fane, Brian M [1] ; Murphy, Chantell L [1] ; Boyer, Brian D [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2011-06-10 OSTI Identifier: 1072334 Report Number(s): LA-UR-11-03368; LA-UR-11-3368 DOE Contract Number: AC52-06NA25396

  3. safeguards

    National Nuclear Security Administration (NNSA)

    %2A en NGSI Safeguards by Design http:nnsa.energy.govaboutusourprogramsdnnnissafeguardssbd

  4. safeguards

    National Nuclear Security Administration (NNSA)

    %2A en NGSI Safeguards by Design http:www.nnsa.energy.govaboutusourprogramsdnnnissafeguardssbd

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

    SciTech Connect (OSTI)

    Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

    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 ability 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.

  6. International safeguards data authentication

    SciTech Connect (OSTI)

    Melton, R.B.; Smith, C.E.; DeLand, S.M.; Manatt, D.R.

    1996-07-01

    The International Safeguards community is becoming increasingly reliant on information stored in electronic form. In international monitoring and related activities it must be possible to verify and maintain the integrity of this electronic information. This paper discusses the use of data authentication technology to assist in accomplishing this task. The paper provides background information, identifies the relevance to international safeguards, discusses issues related to export controls, algorithm patents, key management and the use of commercial vs. custom software.

  7. nuclear safeguards

    National Nuclear Security Administration (NNSA)

    The design projects were supported by the Next Generation Safeguards Initiative Human Capital Development (NGSI HCD) program, which works to recruit, train and retain qualified...

  8. Safeguards Culture: Lessons Learned

    SciTech Connect (OSTI)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2010-06-01

    Today, safeguards culture can be a useful tool for measuring nonproliferation postures, but so far its impact on the international safeguards regime has been underappreciated. There is no agreed upon definition for safeguards culture nor agreement on how it should be measured. This paper argues that safeguards culture as an indicator of a country’s nonproliferation posture can be a useful tool.

  9. Forecasting Water Quality & Biodiversity

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

    Forecasting Water Quality & Biodiversity March 25, 2015 Cross-cutting Sustainability ... that measure feedstock production, water quality, water quantity, and biodiversity. ...

  10. Nuclear Safeguards and Security Challenge:

    National Nuclear Security Administration (NNSA)

    Safeguards and Security Challenge: The international safeguards and security system is being challenged by evolving proliferation and terrorism threats, expanding International Atomic Energy Agency (IAEA) responsibilities, a retiring safeguards workforce, and the need for better technologies to detect and deter proliferation, theft, and sabotage. Response: Revitalize, strengthen, and sustain U.S. and international safeguards and security capabilities through the Next Generation Safeguards

  11. safeguards and security

    National Nuclear Security Administration (NNSA)

    0%2A en NGSI Safeguards by Design http:nnsa.energy.govaboutusourprogramsdnnnissafeguardssbd

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

    SciTech Connect (OSTI)

    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 a 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.

  13. Safeguards by Design (SBD): Safeguards Guidance for Research...

    Office of Scientific and Technical Information (OSTI)

    Safeguards by Design (SBD): Safeguards Guidance for Research Reactors and Critical ... Language: English Subject: Energy Planning, Policy, & Economy(29); Nuclear Disarmament, ...

  14. The safeguards options study

    SciTech Connect (OSTI)

    Hakkila, E.A.; Mullen, M.F.; Olinger, C.T.; Stanbro, W.D.; Olsen, A.P.; Roche, C.T.; Rudolph, R.R.; Bieber, A.M.; Lemley, J.; Filby, E.

    1995-04-01

    The Safeguards Options Study was initiated to aid the International Safeguards Division (ISD) of the DOE Office of Arms Control and Nonproliferation in developing its programs in enhanced international safeguards. The goal was to provide a technical basis for the ISD program in this area. The Safeguards Options Study has been a cooperative effort among ten organizations. These are Argonne National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Mound Laboratory, Oak Ridge National Laboratory, Pacific Northwest Laboratories, Sandia National Laboratories, and Special Technologies Laboratory. Much of the Motivation for the Safeguards Options Study is the recognition after the Iraq experience that there are deficiencies in the present approach to international safeguards. While under International Atomic Energy Agency (IAEA) safeguards at their declared facilities, Iraq was able to develop a significant weapons program without being noticed. This is because negotiated safeguards only applied at declared sites. Even so, their nuclear weapons program clearly conflicted with Iraq`s obligations under the Nuclear Nonproliferation Treaty (NPT) as a nonnuclear weapon state.

  15. Designing and Operating for Safeguards: Lessons Learned From the Rokkasho Reprocessing Plant (RRP)

    SciTech Connect (OSTI)

    Johnson, Shirley J.; Ehinger, Michael

    2010-08-07

    This paper will address the lessons learned during the implementation of International Atomic Energy Agency (IAEA) safeguards at the Rokkasho Reprocessing Plant (RRP) which are relevant to the issue of ‘safeguards by design’. However, those lessons are a result of a cumulative history of international safeguards experiences starting with the West Valley reprocessing plant in 1969, continuing with the Barnwell plant, and then with the implementation of international safeguards at WAK in Germany and TRP in Japan. The design and implementation of safeguards at RRP in Japan is the latest and most challenging that the IAEA has faced. This paper will discuss the work leading up to the development of a safeguards approach, the design and operating features that were introduced to improve or aid in implementing the safeguards approach, and the resulting recommendations for future facilities. It will provide an overview of how ‘safeguardability’ was introduced into RRP.

  16. Safeguards Guidance for Designers of Commercial Nuclear Facilities – International Safeguards Requirements for Uranium Enrichment Plants

    SciTech Connect (OSTI)

    Philip Casey Durst; Scott DeMuth; Brent McGinnis; Michael Whitaker; James Morgan

    2010-04-01

    For the past two years, the United States National Nuclear Security Administration, Office of International Regimes and Agreements (NA-243), has sponsored the Safeguards-by-Design Project, through which it is hoped new nuclear facilities will be designed and constructed worldwide more amenable to nuclear safeguards. In the course of this project it was recognized that commercial designer/builders of nuclear facilities are not always aware of, or understand, the relevant domestic and international safeguards requirements, especially the latter as implemented by the International Atomic Energy Agency (IAEA). To help commercial designer/builders better understand these requirements, a report was prepared by the Safeguards-by-Design Project Team that articulated and interpreted the international nuclear safeguards requirements for the initial case of uranium enrichment plants. The following paper summarizes the subject report, the specific requirements, where they originate, and the implications for design and construction. It also briefly summarizes the established best design and operating practices that designer/builder/operators have implemented for currently meeting these requirements. In preparing the subject report, it is recognized that the best practices are continually evolving as the designer/builder/operators and IAEA consider even more effective and efficient means for meeting the safeguards requirements and objectives.

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

    SciTech Connect (OSTI)

    Robert Bean; Casey Durst

    2009-10-01

    This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called “Safeguards-by-Design.” This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, “International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,” published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a legal document. As such, it is written in a legalese that is understood by specialists in international law and treaties, but not by most outside of this field, including designers of nuclear facilities. For this reason, many of the requirements have been simplified and restated. However, in all cases, the relevant source document and passage is noted so that readers may trace the requirement to the source. This is a helpful living guide, since some of these requirements are subject to revision over time. More importantly, the practices by which the requirements are met are continuously modernized by the IAEA and nuclear facility operators to improve not only the effectiveness of international nuclear safeguards, but also the efficiency. As these improvements are made, the following guidelines should be updated and revised accordingly.

  18. Safeguards and Security Program

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

    2011-07-21

    The order establishes responsibilities and program planning and management requirements for the Safeguards and Security Program. Admin Chg 1, dated 2-15-13, supersedes DOE O 470.4B.

  19. Safeguards and Security Program

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

    1988-01-22

    To establish the policy and responsibilities for the Department of Energy safeguards and security program. Does not cancel another directive. Canceled by DOE O 5630.11A dated 12-7-92.

  20. Strengthening regional safeguards

    SciTech Connect (OSTI)

    Palhares, L.; Almeida, G.; Mafra, O.

    1996-08-01

    Nuclear cooperation between Argentina and Brazil has been growing since the early 1980`s and as it grew, so did cooperation with the US Department of Energy (DOE). The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) was formed in December 1991 to operate the Common System of Accounting and Control of Nuclear Materials (SCCC). In April 1994, ABACC and the DOE signed an Agreement of Cooperation in nuclear material safeguards. This cooperation has included training safeguards inspectors, exchanging nuclear material measurement and containment and surveillance technology, characterizing reference materials, and studying enrichment plant safeguards. The goal of the collaboration is to exchange technology, evaluate new technology in Latin American nuclear facilities, and strengthen regional safeguards. This paper describes the history of the cooperation, its recent activities, and future projects. The cooperation is strongly supported by all three governments: the Republics of Argentina and Brazil and the United States.

  1. Safeguards and Security Program

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

    2007-05-25

    The Order establishes roles and responsibilities for the Department of Energy Safeguards and Security Program. Cancels DOE O 470.4. Canceled by DOE O 470.4B

  2. Safeguards Culture: Lessons Learned

    SciTech Connect (OSTI)

    Mladineo, Stephen V.

    2009-05-27

    Abstract: At the 2005 INMM/ESARDA Workshop in Santa Fe, New Mexico, I presented a paper entitled “Changing the Safeguards Culture: Broader Perspectives and Challenges.” That paper described a set of theoretical models that can be used as a basis for evaluating changes to safeguards culture. This paper builds on that theoretical discussion to address practical methods for influencing culture. It takes lessons from methods used to influence change in safety culture and security culture, and examines the applicability of these lessons to changing safeguards culture. Paper: At the 2005 INMM/ESARDA Workshop on “Changing the Safeguards Culture: Broader Perspectives and Challenges,” in Santa Fe, New Mexico, I presented a paper entitled “Changing the Safeguards Culture: Broader Perspectives and Challenges.” That paper, coauthored by Karyn R. Durbin and Andrew Van Duzer, described a set of theoretical models that can be used as a basis for evaluating changes to safeguards culture. This paper updates that theoretical discussion, and seeks to address practical methods for influencing culture. It takes lessons from methods used to influence change in safety culture and security culture, and examines the applicability of these lessons to changing safeguards culture. Implicit in this discussion is an understanding that improving a culture is not an end in itself, but is one method of improving the underlying discipline, that is safety, security, or safeguards. Culture can be defined as a way of life, or general customs and beliefs of a particular group of people at a particular time. There are internationally accepted definitions of safety culture and nuclear security culture. As yet, there is no official agreed upon definition of safeguards culture. At the end of the paper I will propose my definition. At the Santa Fe Workshop the summary by the Co-Chairs of Working Group 1, “The Further Evolution of Safeguards,” noted: “It is clear that ‘safeguards culture’ needs to be addressed if the efficiency and effectiveness are to continue to be improved. This will require commitment and change at all levels, from States to facility operators. Cultural change has to come from good leadership, doing the right thing and ‘beliefs’ are not sufficient – behavior is what counts. We are optimistic that with sufficient effort and the right incentives, change can be accomplished quickly.”

  3. Measuring Safeguards Culture

    SciTech Connect (OSTI)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2011-07-19

    As the International Atomic Energy Agency (IAEA) implements a State Level Approach to its safeguards verification responsibilities, a number of countries are beginning new nuclear power programs and building new nuclear fuel cycle faculties. The State Level approach is holistic and investigatory in nature, creating a need for transparent, non-discriminatory judgments about a state's nonproliferation posture. In support of this need, the authors previously explored the value of defining and measuring a state's safeguards culture. We argued that a clear definition of safeguards culture and an accompanying set of metrics could be applied to provide an objective evaluation and demonstration of a country's nonproliferation posture. As part of this research, we outlined four high-level metrics that could be used to evaluate a state's nuclear posture. We identified general data points. This paper elaborates on those metrics, further refining the data points to generate a measurable scale of safeguards cultures. We believe that this work could advance the IAEA's goals of implementing a safeguards system that is fully information driven, while strengthening confidence in its safeguards conclusions.

  4. Safeguards-By-Design: Guidance and Tools for Stakeholders

    SciTech Connect (OSTI)

    Mark Schanfein; Shirley Johnson

    2012-02-01

    Effective implementation of the Safeguards-by-Design (SBD) approach can help meet the challenges of global nuclear energy growth, by designing facilities that have improved safeguardability and reduced safeguards-related life cycle costs. The ultimate goal of SBD is to implement effective and efficient safeguards that reduce the burden to both the facility operator and the International Atomic Energy Agency. Since 2008, the National Nuclear Security Administration's Next Generation Safeguards Initiative's Safeguards By Design Project has initiated multiple studies and workshops with industry and regulatory stakeholders, including the IAEA, to develop relevant documents to support the implementation of SBD. These 'Good Practices Guides' describe facility and process design features that will facilitate implementation of effective nuclear material safeguards starting in the earliest phases of design through to final design. These guides, which are in their final editorial stages, start at a high level and then narrow down to specific nuclear fuel cycle facilities such as Light Water Reactors, Generation III/IV Reactors, High Temperature Gas Cooled Reactors, and Gas Centrifuge Enrichment Plants. Most recently, NGSI has begun development of a facility safeguardability assessment toolkit to assist the designer. This paper will review the current status of these efforts, provide some examples of these documents, and show some standard IAEA Unattended Instrumentation that is permanently installed in nuclear facilities for monitoring.

  5. Safeguards and Security Program References

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

    2005-08-26

    The manual establishes definitions for terms related to the Department of Energy Safeguards and Security (S&S) Program and includes lists of references and acronyms/abbreviations applicable to S&S Program directives. Cancels the Safeguards and Security Glossary of Terms, dated 12-18-95. Current Safeguards and Security Program References can also be found at Safeguards and Security Policy Information Resource (http://pir.pnl.gov/)

  6. Safeguard Security and Awareness Program

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

    2002-10-02

    Provides detailed requirements and procedures to supplement DOE O 470.1, Safeguards and Security Program, Chapter IV.

  7. Facility Safeguardability Assessment Report

    National Nuclear Security Administration (NNSA)

    PNNL-21698 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Overview of the Facility Safeguardability Analysis (FSA) Process RA Bari SJ Johnson J Hockert R Wigeland EF Wonder MD Zentner August 2012 PNNL- 21698 Overview of the Facility Safeguardability Analysis (FSA) Process RA Bari 1 SJ Johnson 2 J Hockert 3 R Wigeland 4 EF Wonder 5 M.D. Zentner August 2012 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 1 Brookhaven National Laboratory 2

  8. Safeguards and Security Program

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

    2010-12-29

    The Safeguards and Security Program ensures that the Department of Energy efficiently and effectively meets all its obligations to protect Special Nuclear Material, other nuclear materials, classified matter, sensitive information, government property, and the safety and security of employees, contractors, and the general public. Supersedes DOE P 470.1.

  9. Safeguards and Security Program

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

    2016-02-10

    The Safeguards and Security Program ensures that the Department of Energy efficiently and effectively meets all its obligations to protect Special Nuclear Material, other nuclear materials, classified matter, sensitive information, government property and facilities, and the safety and security of employees, contractors, and the general public. Supersedes DOE P 470.1A.

  10. Safeguards and Security Program

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

    2005-08-26

    Establishes roles and responsibilities for the Department of Energy Safeguards and Security Program. Cancels: DOE O 470.1, DOE O 471.2A, DOE O 471.4, DOE O 472.1C, DOE O 473.1, DOE O 473.2, DOE O 474.1A. Canceled by DOE O 470.4A.

  11. Safeguards and Security Program

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

    2011-07-21

    To establish responsibilities for the U.S. Department of Energy (DOE) Safeguards and Security (S&S) Program, and to establish program planning and management requirements for the S&S Program. Cancels DOE O 470.4A, DOE M 470.4-1, Chg. 2, and DOE O 142.1.

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

    SciTech Connect (OSTI)

    Bingham, C.D.

    1986-01-01

    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 recently 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.

  13. International Nuclear Safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

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

  14. Safeguards & Security | Department of Energy

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

    cyber system operations and security, and business and budget operations including property management. Supports EM headquarters with safeguards and security assistance. ...

  15. Biodiversity conservation and NEPA

    SciTech Connect (OSTI)

    Southerland, M.T. )

    1993-01-01

    The Council of Environmental Quality (CEQ) and the Environmental Protection Agency (EPA) have recently developed new guidelines to facilitate the consideration of biodiversity in the preparation and review of environmental impact assessments. The purpose of these efforts is to facilitate the incorporation of biodiversity considerations into the ecological analyses of all federal agencies. Because federal decisions requiring environmental impact assessments under NEPA affect hundreds of millions of federal and non-federal lands and waters, improved consideration of the impacts of federal activities is essential to stemming the loss of biological diversity in the United States. The designation of ecosystems or habitats'' of concern is a useful first step identifying risks to biodiversity. After reviewing the status and trends of habitats within eight major regions of the US, the EPA guidelines identify habitats contributing to regional and global biodiversity such as remnant prairies, riparian habitats, and old-growth forests. This document also discusses how the impacts on habitats vary with the different activities of land conversion, timber harvesting, grazing, mining, and water management.

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

    National Nuclear Security Administration (NNSA)

    Nuclear Materials Management & Safeguards System NMMSS U.S. Department of Energy U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards System NMMSS ...

  17. Safeguards and Security Program - DOE Directives, Delegations...

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

    4B Admin Chg 1, Safeguards and Security Program by Marc Brooks Functional areas: Administrative Change, Safeguards, Security, and Emergency Management, Safety, Safety and Security,...

  18. Next generation safeguards initiative university outreach: the...

    Office of Scientific and Technical Information (OSTI)

    Next generation safeguards initiative university outreach: the unique Los Alamos and the ... Title: Next generation safeguards initiative university outreach: the unique Los Alamos ...

  19. Full spectrum optical safeguard

    DOE Patents [OSTI]

    Ackerman, Mark R.

    2008-12-02

    An optical safeguard device with two linear variable Fabry-Perot filters aligned relative to a light source with at least one of the filters having a nonlinear dielectric constant material such that, when a light source produces a sufficiently high intensity light, the light alters the characteristics of the nonlinear dielectric constant material to reduce the intensity of light impacting a connected optical sensor. The device can be incorporated into an imaging system on a moving platform, such as an aircraft or satellite.

  20. Los Alamos safeguards program overview and NDA in safeguards

    SciTech Connect (OSTI)

    Keepin, G.R.

    1988-01-01

    Over the years the Los Alamos safeguards program has developed, tested, and implemented a broad range of passive and active nondestructive analysis (NDA) instruments (based on gamma and x-ray detection and neutron counting) that are now widely employed in safeguarding nuclear materials of all forms. Here very briefly, the major categories of gamma ray and neutron based NDA techniques, give some representative examples of NDA instruments currently in use, and cite a few notable instances of state-of-the-art NDA technique development. Historical aspects and a broad overview of the safeguards program are also presented.

  1. Master Safeguards and Security Agreements

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

    1988-02-03

    To establish the Department of Energy policy, requirements, responsibilities, and authorities for the development and implementation of Master Safeguards and Security Agreements (MSSA's). Does not cancel another directive. Canceled by DOE O 5630.13A

  2. Overview of enrichment plant safeguards

    SciTech Connect (OSTI)

    Swindle, D.W. Jr.; Wheeler, L.E.

    1982-01-01

    The relationship of enrichment plant safeguards to US nonproliferation objectives and to the operation and management of enrichment facilities is reviewed. During the review, the major components of both domestic and international safeguards systems for enrichment plants are discussed. In discussing domestic safeguards systems, examples of the technology currently in use to support nuclear materials accountability are described including the measurement methods, procedures and equipment used for weighing, sampling, chemical and isotopic analyses and nondestructive assay techniques. Also discussed is how the information obtained as part of the nuclear material accountancy task is useful to enrichment plant operations. International material accountancy verification and containment/surveillance concepts for enrichment plants are discussed, and the technologies presently being developed for international safeguards in enrichment plants are identified and the current development status is reported.

  3. Incorporating Biodiversity Considerations Into Environmental...

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

    provide background on the emerging, complex subject of biodiversity, outline some general concepts that underlie biological diversity analysis and management, describe how the ...

  4. Voluntary Protection Program Onsite Review, Safeguards and Security...

    Office of Environmental Management (EM)

    Safeguards and Security - August 2012 Voluntary Protection Program Onsite Review, Safeguards and Security - August 2012 August 2012 Evaluation to determine whether Safeguards and...

  5. International safeguards: experience and prospects

    SciTech Connect (OSTI)

    Keepin, G.R.; Menlove, H.O.

    1982-01-01

    IAEA safeguards have been applied to over 95% of the nuclear material and facilities outside of the nuclear weapon states. The present system of nonproliferation agreements implemented by IAEA safeguards likely will not be changed in the foreseeable future. Instruments used for nondestructive analysis are described: portable multichannel analyzer, high-level neutron coincidence counter, active well coincidence counter, and neutron coincidence collar. 7 figs. (DLC)

  6. Safeguarding wetland on Laboratory property

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

    Safeguarding wetland on Laboratory property Community Connections: Your link to news and opportunities from Los Alamos National Laboratory Latest Issue:May 2016 all issues All Issues » submit Safeguarding wetland on Laboratory property Protecting our environment August 1, 2013 The wetlands in Sandia Canyon on Lab property provide a home to a large amount of wildlife. Work is taking place to preserve the area and manage its water supply The wetlands in Sandia Canyon on Lab property provide a

  7. Thorium based power systems and relevant safeguards considerations...

    Office of Scientific and Technical Information (OSTI)

    APA Chicago Bibtex Export Metadata Endnote Excel CSV XML Save to My Library Send to Email Send to Email Email address: Content: Close Send Cite: MLA Format Close Cite: APA ...

  8. Safeguards and Security Program

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

    1995-09-28

    Ensures appropriate levels of protection against unauthorized access; theft, diversion, loss of custody, or destruction of nuclear weapons, or weapons components; espionage; loss or theft of classified matter or Government property; and other hostile acts that may cause unacceptable adverse impacts on national security or on the health and safety of Department of Energy (DOE) and contractor employees, the public, or the environment. DOE O 470.1 Extended until 5-11-06 by DOE N 251.63, dated 5-11-05. Chg 1, Safeguards and Security Program, dated 9/28/95, extended by DOE N 251.57, dated 4/28/2004. Change 1, 5/21/96, revises Chapter IV. Cancels: DOE 5630.11B, DOE 5630.13A, DOE 5630.14A, DOE 5630.15, DOE 5630.16A, DOE 5630.17, DOE 5631.1C, DOE 5631.4A, DOE 5634.1B, DOE 5634.3, DOE 5639.3, DOE M 5632.1C-1 in part.

  9. Safeguards training course: Nuclear material safeguards for enrichment plants

    SciTech Connect (OSTI)

    Not Available

    1990-06-01

    The main objective of this course is to provide the course participants with the necessary skills to perform their inspection activities at enrichment plants. As background information, a variety of enrichment technologies will first be characterized and compared followed by a review of basic cascade, gas centrifuge, and gaseous diffusion theory. To focus on gas centrifuge and gaseous diffusion technology, the major components and system of gas centrifuge and gaseous diffusion enrichment plants including their function in routine LEU production will be identified. The objectives of safeguards at an enrichment plant, including those agreed to in the Hexapartite Safeguards Project, will then be described. Discussions will then focus on potential diversion scenarios at both a centrifuge and diffusion enrichment facility and applicable safeguards inspection activities for detecting these scenarios. This report presents a discussion on basic separation and cascade theory, uranium hexafluoride, and detailed separation theory, including gas centrifuge and gaseous diffusion.

  10. Safeguards training course: Nuclear material safeguards for enrichment plants

    SciTech Connect (OSTI)

    Not Available

    1990-06-01

    The main objective of this training course is to provide the course participants with the necessary skills to perform their inspection activities at enrichment plants. As background information, a variety of enrichment technologies will first be characterized and compared followed by a review of basic cascade, gas centrifuge, and gaseous diffusion theory. To focus on gas centrifuge and gaseous diffusion technology, the major components and systems of gas centrifuge and gaseous diffusion enrichment plants including their function in routine LEU production will be identified. The objectives of safeguards at an enrichment plant, including those agreed to in the Hexapartite Safeguards Project, will then be described. Discussion will then focus on potential diversion scenarios at both a centrifuge and diffusion enrichment facility and applicable safeguards inspection activities for detecting these scenarios.

  11. DESIGN INFORMATION VERIFICATION FOR NUCLEAR SAFEGUARDS

    SciTech Connect (OSTI)

    Robert S. Bean; Richard R. M. Metcalf; Phillip C. Durst

    2009-07-01

    A critical aspect of international safeguards activities performed by the International Atomic Energy Agency (IAEA) is the verification that facility design and construction (including upgrades and modifications) do not create opportunities for nuclear proliferation. These Design Information Verification activities require that IAEA inspectors compare current and past information about the facility to verify the operator’s declaration of proper use. The actual practice of DIV presents challenges to the inspectors due to the large amount of data generated, concerns about sensitive or proprietary data, the overall complexity of the facility, and the effort required to extract just the safeguards relevant information. Planned and anticipated facilities will (especially in the case of reprocessing plants) be ever larger and increasingly complex, thus exacerbating the challenges. This paper reports the results of a workshop held at the Idaho National Laboratory in March 2009, which considered technologies and methods to address these challenges. The use of 3D Laser Range Finding, Outdoor Visualization System, Gamma-LIDAR, and virtual facility modeling, as well as methods to handle the facility data issues (quantity, sensitivity, and accessibility and portability for the inspector) were presented. The workshop attendees drew conclusions about the use of these techniques with respect to successfully employing them in an operating environment, using a Fuel Conditioning Facility walk-through as a baseline for discussion.

  12. Process: (international) safeguards interface at the Portsmouth GCEP from the safeguards technology developer's viewpoint

    SciTech Connect (OSTI)

    Tape, J.W.; Strittmatter, R.B.; Baker, A.L.

    1983-01-01

    The design of a major portion of a safeguards system for possible use by IAEA at the Portsmouth Gas Centrifuge Enrichment Plant is described from the viewpoint of the safeguards technology developer. The process-safeguards interface is reviewed, including safeguards, process, and operational constraints on the safeguards system. The conflicting requirements of the IAEA and the plant operator are minimized through the use of advanced technology that allows safeguards data to be acquired, analyzed, and reported in an automated, unattended mode. The proposed safeguards system will reduce the impact of the inspections on both the operator and the IAEA.

  13. UNCLASSIFIED UNCLASSIFIED Nuclear Materials Management & Safeguards...

    National Nuclear Security Administration (NNSA)

    UNCLASSIFIED Nuclear Materials Management & Safeguards System CONTACT INFORMATION UPDATE REPORTING IDENTIFICATION SYMBOL (RIS) RIS: Address: Facility Name: CONTACTS Name Email:...

  14. Resource Allocation Optimization Program for Safeguards

    Energy Science and Technology Software Center (OSTI)

    1994-03-11

    RAOPS uses dynamic programming to make the best use of physical and economic resources in safeguarding special nuclear material.

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

    SciTech Connect (OSTI)

    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) 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 with the IAEA. If these requirements are understood at the earliest stages of facility design, it will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards, and will help the IAEA implement nuclear safeguards worldwide, especially in countries building their first nuclear facilities. It is also hoped that this guidance document will promote discussion between the IAEA, State Regulator/SSAC, Project Design Team, and Facility Owner/Operator at an early stage to ensure that new ISFSIs will be effectively and efficiently safeguarded. This is intended to be a living document, since the international nuclear safeguards requirements may be subject to revision over time. More importantly, the practices by which the requirements are met are continuously modernized by the IAEA and facility operators for greater efficiency and cost effectiveness. As these improvements are made, it is recommended that the subject guidance document be updated and revised accordingly.

  16. Safeguards Transporter | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Home Safeguards Transporter General Davis kicks the tires on a Safeguards Transporter Brigadier General Stephen L. Davis, NNSA's Acting Deputy Administrator for Defense Programs, gets a lesson on how to drive a Safeguards Transporter during a recent visit to the Office of Secure Transportation (OST) headquarters in Albuquerque, New Mexico. OST is responsible for transporting...

  17. Safeguards instrumentation: a computer-based catalog

    SciTech Connect (OSTI)

    Fishbone, L.G.; Keisch, B.

    1981-08-01

    The information contained in this catalog is needed to provide a data base for safeguards studies and to help establish criteria and procedures for international safeguards for nuclear materials and facilities. The catalog primarily presents information on new safeguards equipment. It also describes entire safeguards systems for certain facilities, but it does not describe the inspection procedures. Because IAEA safeguards do not include physical security, devices for physical protection (as opposed to containment and surveillance) are not included. An attempt has been made to list capital costs, annual maintenance costs, replacement costs, and useful lifetime for the equipment. For equipment which is commercially available, representative sources have been listed whenever available.

  18. Process Monitoring for Nuclear Safeguards

    SciTech Connect (OSTI)

    Ehinger, Michael H [ORNL] [ORNL; Pomeroy, George D [ORNL] [ORNL; Budlong-Sylvester, Kory W [ORNL] [ORNL

    2009-01-01

    Process Monitoring has long been used to evaluate industrial processes and operating conditions in nuclear and non-nuclear facilities. In nuclear applications there is a recognized need to demonstrate the safeguards benefits from using advanced process monitoring on spent fuel reprocessing technologies and associated facilities, as a complement to nuclear materials accounting. This can be accomplished by: defining credible diversion pathway scenarios as a sample problem; using advanced sensor and data analysis techniques to illustrate detection capabilities; and formulating 'event detection' methodologies as a means to quantify performance of the safeguards system. Over the past 30 years there have been rapid advances and improvement in the technology associated with monitoring and control of industrial processes. In the context of bulk handling facilities that process nuclear materials, modern technology can provide more timely information on the location and movement of nuclear material to help develop more effective safeguards. For international safeguards, inspection means verification of material balance data as reported by the operator through the State to the international inspectorate agency. This verification recognizes that the State may be in collusion with the operator to hide clandestine activities, potentially during abnormal process conditions with falsification of data to mask the removal. Records provided may show material is accounted for even though a removal occurred. Process monitoring can offer additional fidelity during a wide variety of operating conditions to help verify the declaration or identify possible diversions. The challenge is how to use modern technology for process monitoring and control in a proprietary operating environment subject to safeguards inspectorate or other regulatory oversight. Under the U.S. National Nuclear Security Administration's Next Generation Safeguards Initiative, a range of potential safeguards applications for process monitoring are under conceptual development and evaluation. This paper reports on a study of process monitoring for a sample problem involving spent fuel reprocessing with aqueous reprocessing technologies. This includes modeling the processes in the context of a nuclear material diversion scenario and measuring the associated process chemistry. A systems-centric model is applied using actual and simulated plant data, advanced sensors, anomaly detection methods, statistical analysis and data authentication methods, to help illustrate the benefits of process monitoring applications.

  19. REPORT OF THE WORKSHOP ON NUCLEAR FACILITY DESIGN INFORMATION EXAMINATION AND VERIFICATION FOR SAFEGUARDS

    SciTech Connect (OSTI)

    Richard Metcalf; Robert Bean

    2009-10-01

    Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA’s Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility’s general character, purpose, capacity, and location; (2) Description of the facility’s layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards in the future. Consequently, the NNSA Office of International Regimes and Agreements (NA-243) sponsored a team of U.S. Department of Energy National Laboratory nuclear safeguards experts and technologists to conduct a workshop on methods and technologies for improving this activity, under the ASA-100 Advanced Safeguards Approaches Project. The workshop focused on reviewing and discussing the fundamental safeguards needs, and presented technology and/or methods that could potentially address those needs more effectively and efficiently. Conclusions and Recommendations for technology to enhance the performance of DIV inspections are presented by the workshop team.

  20. Reversing the Trend: Creating a Growing and Sustainable Cadre of Safeguards Experts in the United States

    SciTech Connect (OSTI)

    Lockwood, Dunbar; Mathews, Caroline E.; Seward, Amy M.

    2008-07-17

    In October 2007, the National Nuclear Security Administration’s (NNSA) Office of Non-Proliferation and International Security (NA-24) completed a wide-ranging study on international safeguards issues that found, inter alia, that the human capital base in the United States must be revitalized and expanded to ensure a seamless succession from the current generation of safeguards experts. Many current safeguards experts will soon retire and a new generation of talent with capabilities that cover the full spectrum of safeguards-relevant disciplines is needed. The success of this effort will have direct bearing on the International Atomic Energy Agency (IAEA). An effective international safeguards system that responds to current and future nonproliferation challenges requires a cadre of skilled safeguards specialists. However, a number of factors have converged in recent years that have challenged the IAEA’s ability to effectively carry out its safeguards mission, e.g. flat funding, expanding responsibilities, and several ad hoc high profile investigations. In the near future, the Agency will require increased numbers of qualified staff to address the expansion and evolution of its mission and anticipated worldwide growth in nuclear energy production. Without a large-scale effort to address this requirement in the near future, the international community will have far less confidence that nuclear material in civil programs is not being diverted for nuclear weapons and the risks of nuclear proliferation will increase around the world. This paper will describe in detail NNSA’s efforts, in coordination with other federal agencies, to address the safeguards human resources challenge, focusing on the recommendations of the Next Generation Safeguards Initiative (NGSI).

  1. Simulation enabled safeguards assessment methodology

    SciTech Connect (OSTI)

    Bean, Robert; Bjornard, Trond; Larson, Tom

    2007-07-01

    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 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 in functionality. Drag and drop wire-frame 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. (authors)

  2. Modeling and Simulation for Safeguards

    SciTech Connect (OSTI)

    Swinhoe, Martyn T.

    2012-07-26

    The purpose of this talk is to give an overview of the role of modeling and simulation in Safeguards R&D and introduce you to (some of) the tools used. Some definitions are: (1) Modeling - the representation, often mathematical, of a process, concept, or operation of a system, often implemented by a computer program; (2) Simulation - the representation of the behavior or characteristics of one system through the use of another system, especially a computer program designed for the purpose; and (3) Safeguards - the timely detection of diversion of significant quantities of nuclear material. The role of modeling and simulation are: (1) Calculate amounts of material (plant modeling); (2) Calculate signatures of nuclear material etc. (source terms); and (3) Detector performance (radiation transport and detection). Plant modeling software (e.g. FACSIM) gives the flows and amount of material stored at all parts of the process. In safeguards this allow us to calculate the expected uncertainty of the mass and evaluate the expected MUF. We can determine the measurement accuracy required to achieve a certain performance.

  3. Safeguards Envelope Progress FY10

    SciTech Connect (OSTI)

    Richard Metcalf

    2010-10-01

    The Safeguards Envelope is a strategy to determine a set of specific operating parameters within which nuclear facilities may operate to maximize safeguards effectiveness without sacrificing safety or plant efficiency. This paper details the additions to the advanced operating techniques that will be applied to real plant process monitoring (PM) data from the Idaho Chemical Processing Plant (ICPP). Research this year focused on combining disparate pieces of data together to maximize operating time with minimal downtime due to safeguards. A Chi-Square and Croiser's cumulative sum were both included as part of the new analysis. Because of a major issue with the original data, the implementation of the two new tests did not add to the existing set of tests, though limited one-variable optimization made a small increase in detection probability. Additional analysis was performed to determine if prior analysis would have caused a major security or safety operating envelope issue. It was determined that a safety issue would have resulted from the prior research, but that the security may have been increased under certain conditions.

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

    SciTech Connect (OSTI)

    Frazar, Sarah L.; Gastelum, Zoe N.; Olson, Jarrod; Mathews, Caroline E.; Solodov, Alexander; Zhernosek, Alena; Raffo-Caiado, Ana; Baldwin, George; Horak, Karl; McClelland-Kerr, John; VanSickle, Matthew; Mininni, Margot; Kovacic, Donald

    2009-10-06

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

  5. Safeguards and Security Program, acronyms and abbereviations...

    Office of Environmental Management (EM)

    More Documents & Publications Safeguards and Security Glossary - DOE M 470.4-7 References, Canceled -7 Section B - April 16 2010 Briefing, Classification of Nuclear Weapons-Related ...

  6. Safeguards & Security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    programmatic input to assist the Assistant Manager for Contract Administration and Business Management with the formulation and execution oversight of the safeguards and...

  7. International safeguards recommendations for the Indian advanced...

    Office of Scientific and Technical Information (OSTI)

    advanced heavy water reactor (AHWR) Citation Details In-Document Search Title: International safeguards recommendations for the Indian advanced heavy water reactor (AHWR) ...

  8. Office of Safeguards, Security & Emergency Preparedness | Department...

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

    Foster continuous improvement across the Environmental Management (EM) complex through application of Integrated Safeguards and Security Management principles. Serve as a liaison ...

  9. Next Generation Safeguards Initiative Inaugural Conference |...

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

    And they will continue to change. And our efforts to combat ... international safeguards system, cannot do the job alone. ... at our network of world class Department of Energy ...

  10. nuclear safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    with Washington State University students for the past seven years to develop new instruments, tools, and methods to support nonproliferation and international safeguards. ...

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

    National Nuclear Security Administration (NNSA)

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

  12. FAQS Reference Guide – Safeguards and Security

    Broader source: Energy.gov [DOE]

    This reference guide addresses the competency statements in the May 2009 edition of DOE-STD-1171-2009, Safeguards and Security Functional Area Qualification Standard.

  13. UNCLASSIFIED Nuclear Materials Management & Safeguards System

    National Nuclear Security Administration (NNSA)

    Nuclear Materials Management & Safeguards System CHANGE OF PROJECT NUMBER UPDATE PROJECT Project Number: Title: Date Valid: Date Deactivated: Classification Codes: Project Number: ...

  14. NNSA Next Generation Safeguards Initiative | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Administered by the International Atomic Energy Agency (IAEA), international safeguards serve to monitor nuclear activities under the Non-Proliferation Treaty (NPT) and are the ...

  15. Nuclear Nonproliferation, International Safeguards and Nuclear...

    Office of Scientific and Technical Information (OSTI)

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

  16. Nuclear Nonproliferation, International Safeguards and Nuclear...

    Office of Scientific and Technical Information (OSTI)

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

  17. RADIO FREQUENCY IDENTIFICATION DEVICES: EFFECTIVENESS IN IMPROVING SAFEGUARDS AT GAS-CENTRIFUGE URANIUM-ENRICHMENT PLANTS.

    SciTech Connect (OSTI)

    JOE,J.

    2007-07-08

    Recent advances in radio frequency identification devices (RFIDs) have engendered a growing interest among international safeguards experts. Potentially, RFIDs could reduce inspection work, viz. the number of inspections, number of samples, and duration of the visits, and thus improve the efficiency and effectiveness of international safeguards. This study systematically examined the applications of RFIDs for IAEA safeguards at large gas-centrifuge enrichment plants (GCEPs). These analyses are expected to help identify the requirements and desirable properties for RFIDs, to provide insights into which vulnerabilities matter most, and help formulate the required assurance tests. This work, specifically assesses the application of RFIDs for the ''Option 4'' safeguards approach, proposed by Bruce Moran, U. S. Nuclear Regulatory Commission (NRC), for large gas-centrifuge uranium-enrichment plants. The features of ''Option 4'' safeguards include placing RFIDs on all feed, product and tails (F/P/T) cylinders, along with WID readers in all FP/T stations and accountability scales. Other features of Moran's ''Option 4'' are Mailbox declarations, monitoring of load-cell-based weighing systems at the F/P/T stations and accountability scales, and continuous enrichment monitors. Relevant diversion paths were explored to evaluate how RFIDs improve the efficiency and effectiveness of safeguards. Additionally, the analysis addresses the use of RFIDs in conjunction with video monitoring and neutron detectors in a perimeter-monitoring approach to show that RFIDs can help to detect unidentified cylinders.

  18. Audit of the Department of Energy's Site Safeguards and Security...

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

    Energy's Site Safeguards and Security Plans TO: The Secretary BACKGROUND: The Department's Safeguards and Security program is designed to provide appropriate, efficient, and...

  19. GNEP Element:Develop Enhanced Nuclear Safeguards | Department...

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

    A description of GNEP development of enhanced nuclear safeguards. GNEP Element:Develop Enhanced Nuclear Safeguards More Documents & Publications Global Nuclear Energy Partnership...

  20. Simulated process test bed for integrated safeguards operations...

    Office of Scientific and Technical Information (OSTI)

    Simulated process test bed for integrated safeguards operations monitoring Citation Details In-Document Search Title: Simulated process test bed for integrated safeguards ...

  1. NNSA Kicks Off Next Generation Safeguards Initiative | National...

    National Nuclear Security Administration (NNSA)

    People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy ... safeguards, which protect against proliferation. "Effective nuclear safeguards are the ...

  2. Safeguards Issues at Nuclear Reactors and Enrichment Plants ...

    Office of Scientific and Technical Information (OSTI)

    Safeguards Issues at Nuclear Reactors and Enrichment Plants Citation Details In-Document Search Title: Safeguards Issues at Nuclear Reactors and Enrichment Plants The Agency's ...

  3. Safeguards Issues at Nuclear Reactors and Enrichment Plants ...

    Office of Scientific and Technical Information (OSTI)

    Safeguards Issues at Nuclear Reactors and Enrichment Plants Citation Details In-Document Search Title: Safeguards Issues at Nuclear Reactors and Enrichment Plants Authors: Boyer, ...

  4. Safeguards at Gas Centrifuge Enrichment Plants: Why is Iran a...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Safeguards at Gas Centrifuge Enrichment Plants: Why is Iran a Threat? Citation Details In-Document Search Title: Safeguards at Gas Centrifuge Enrichment Plants: ...

  5. Safeguards at Gas Centrifuge Enrichment Plants: Why is Iran a...

    Office of Scientific and Technical Information (OSTI)

    Safeguards at Gas Centrifuge Enrichment Plants: Why is Iran a Threat? Citation Details In-Document Search Title: Safeguards at Gas Centrifuge Enrichment Plants: Why is Iran a ...

  6. Proceedings of the Advisory Committee on Reactor Safeguards Safety...

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

    Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop December 16, ...

  7. Safeguards Issues at Nuclear Reactors and Enrichment Plants ...

    Office of Scientific and Technical Information (OSTI)

    Safeguards Issues at Nuclear Reactors and Enrichment Plants Citation Details In-Document Search Title: Safeguards Issues at Nuclear Reactors and Enrichment Plants You are ...

  8. Optical assay technology for safeguards

    SciTech Connect (OSTI)

    Edelson, M.C.; Lipert, R.J.; Murray, G.M.; Schuler, R.A.; Vera, J.; Wang, Z.M.; Weeks, S.J.

    1990-10-01

    Research conducted in the Ames Laboratory Nuclear Safeguards and Security Program during the period July 1, 1990 to September 30, 1990 is reviewed; included are reprints and preprints of papers written during this quarter. The first demonstration of isotopic selectivity in Inductively Coupled Plasma -- Laser Excited Atomic Fluorescence Spectroscopy (ICP-LEAFS) is reported and the application of ICP-LEAFS to U isotopic analysis is discussed. Current work in applying optical spectroscopy to the analytical determination of gas phase metal atoms is reviewed. Program administration topics are included in a separately bound Management Supplement to this report.

  9. Gas Centrifuge Enrichment Plant Safeguards System Modeling

    SciTech Connect (OSTI)

    Elayat, H A; O'Connell, W J; Boyer, B D

    2006-06-05

    The U.S. Department of Energy (DOE) is interested in developing tools and methods for potential U.S. use in designing and evaluating safeguards systems used in enrichment facilities. This research focuses on analyzing the effectiveness of the safeguards in protecting against the range of safeguards concerns for enrichment plants, including diversion of attractive material and unauthorized modes of use. We developed an Extend simulation model for a generic medium-sized centrifuge enrichment plant. We modeled the material flow in normal operation, plant operational upset modes, and selected diversion scenarios, for selected safeguards systems. Simulation modeling is used to analyze both authorized and unauthorized use of a plant and the flow of safeguards information. Simulation tracks the movement of materials and isotopes, identifies the signatures of unauthorized use, tracks the flow and compilation of safeguards data, and evaluates the effectiveness of the safeguards system in detecting misuse signatures. The simulation model developed could be of use to the International Atomic Energy Agency IAEA, enabling the IAEA to observe and draw conclusions that uranium enrichment facilities are being used only within authorized limits for peaceful uses of nuclear energy. It will evaluate improved approaches to nonproliferation concerns, facilitating deployment of enhanced and cost-effective safeguards systems for an important part of the nuclear power fuel cycle.

  10. Safeguards and Security Independent Oversight Program

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

    1998-12-23

    Establishes the DOE Safeguards and Security Independent Oversight Program that provides DOE and contractor managers, Congress, and other stakeholders with an independent evaluation of the effectiveness of DOE safeguards and security policy and programs, and the implementation of those policies and programs. Cancels DOE 5630.12A.

  11. Improving the Transparency of IAEA Safeguards Reporting

    SciTech Connect (OSTI)

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

    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 a 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.

  12. Materials management in an internationally safeguarded fuels reprocessing plant

    SciTech Connect (OSTI)

    Hakkila, E.A.; Baker, A.L.; Cobb, D.D.

    1980-04-01

    The following appendices are included: aqueous reprocessing and conversion technology, reference facilities, process design and operating features relevant to materials accounting, operator's safeguards system structure, design principles of dynamic materials accounting systems, modeling and simulation approach, optimization of measurement control, aspects of international verification problem, security and reliability of materials measurement and accounting system, estimation of in-process inventory in solvent-extraction contactors, conventional measurement techniques, near-real-time measurement techniques, isotopic correlation techniques, instrumentation available to IAEA inspectors, and integration of materials accounting and containment and surveillance. (DLC)

  13. Relevant Links

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

    Relevant Links **Light Source Facilities Around the World** Advanced Materials Research Institiute(AMRI), UNO Area Hotels Chase Suite Hotel Baton Rouge Extended Stay America Holiday Inn South Baton Rouge Marriott Residence Inns Wyndham Garden Gulf Coast Protein Crystallography Consortium Health Physics Society Institute for Micromanufacturing, LA Tech University Interactions.org - Particle Physics News and Resources International Nuclear Information System (INIS) Light Sources.org The Louisiana

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

    SciTech Connect (OSTI)

    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.

  15. Multimedia systems for safeguards training

    SciTech Connect (OSTI)

    Guardini, S.; Loeschner, J.

    1995-12-31

    The Joint Research Center as part of its support program to Euratom safeguards, is developing a line of unattended systems for fresh fuel assemblies in fabrication plants (low enrichment and mixed oxide). These systems combine neutron coincidence counting in the form of a neutron collar and a vision system for identification of the fuel assembly. The system is unattended, i.e. it is integrated into the production flow of the facility, and there is no inspector presence during verification measurement. The facility operator loads the assembly into the unattended measurement station which then automatically starts its predefined measurement cycle without the intervention of the facility operator. The station positions the collar according to a programming strategy for each assembly type and loads/unloads its own AmLi source for active and passive measurements. This paper is a discussion of the training requirements for such a system and the development of multimedia training aids to meet these requirements.

  16. IAEA Safeguards: Past, Present, and Future

    SciTech Connect (OSTI)

    Santi, Peter A.; Hypes, Philip A.

    2012-06-14

    This talk will present an overview of the International Atomic Energy Agency with a specific focus on its international safeguards mission and activities. The talk will first present a brief history of the IAEA and discuss its current governing structure. It will then focus on the Safeguards Department and its role in providing assurance that nuclear materials are being used for peaceful purposes. It will then look at how the IAEA is currently evolving the way in which it executes its safeguards mission with a focus on the idea of a state-level approach.

  17. Overview of the Facility Safeguardability Analysis (FSA) Process

    SciTech Connect (OSTI)

    Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Scott J.; Wigeland, Roald; Zentner, Michael D.

    2012-08-01

    Executive Summary The safeguards system of the International Atomic Energy Agency (IAEA) is intended to provide the international community with credible assurance that a State is fulfilling its safeguards obligations. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of IAEA safeguards as those safeguards evolve towards a “State-Level approach.” The Safeguards by Design (SBD) concept can facilitate the implementation of these effective and cost-efficient facility-level safeguards (Bjornard, et al. 2009a, 2009b; IAEA, 1998; Wonder & Hockert, 2011). This report, sponsored by the National Nuclear Security Administration’s Office of Nuclear Safeguards and Security, introduces a methodology intended to ensure that the diverse approaches to Safeguards by Design can be effectively integrated and consistently used to cost effectively enhance the application of international safeguards.

  18. Safeguards and Security and Cyber Security RM | Department of Energy

    Energy Savers [EERE]

    Safeguards and Security and Cyber Security RM Safeguards and Security and Cyber Security RM The SSCS RM is a tool that assists the DOE federal project review teams in evaluating the technical sufficiency of the project SSCS activities at CD-0 through CD-4. PDF icon Safeguards and Security and Cyber Security RM More Documents & Publications Safeguards and Security Program, acronyms and abbereviations - DOE M 470.4-7 Safeguards and Security Glossary - DOE M 470.4-7 References, Canceled -7

  19. Next generation safeguards initiative university outreach: the unique Los

    Office of Scientific and Technical Information (OSTI)

    Alamos and the Pennsylvania state university nuclear fuel cycle and safeguards graduate course (Conference) | SciTech Connect Next generation safeguards initiative university outreach: the unique Los Alamos and the Pennsylvania state university nuclear fuel cycle and safeguards graduate course Citation Details In-Document Search Title: Next generation safeguards initiative university outreach: the unique Los Alamos and the Pennsylvania state university nuclear fuel cycle and safeguards

  20. Next generation safeguards initiative university outreach: the unique Los

    Office of Scientific and Technical Information (OSTI)

    Alamos and the Pennsylvania state university nuclear fuel cycle and safeguards graduate course (Conference) | SciTech Connect Next generation safeguards initiative university outreach: the unique Los Alamos and the Pennsylvania state university nuclear fuel cycle and safeguards graduate course Citation Details In-Document Search Title: Next generation safeguards initiative university outreach: the unique Los Alamos and the Pennsylvania state university nuclear fuel cycle and safeguards

  1. Safeguards and Security Program, acronyms and abbereviations - DOE M

    Office of Environmental Management (EM)

    470.4-7 | Department of Energy Program, acronyms and abbereviations - DOE M 470.4-7 Safeguards and Security Program, acronyms and abbereviations - DOE M 470.4-7 August 26, 2005 Canceled Safeguards and Security Program acronyms and abbereviations Canceled -7 Section C Safeguards and Security Program acronyms and abbereviations PDF icon Safeguards and Security Program, acronyms and abbereviations - DOE M 470.4-7 More Documents & Publications Safeguards and Security Glossary - DOE M 470.4-7

  2. Integration of Biodiversity into National Forestry Planning:...

    Open Energy Info (EERE)

    Biodiversity into National Forestry Planning: An Annotated Bibliography of Web-Based Resources, Methods, Experiences, and Case Studies Jump to: navigation, search Tool Summary...

  3. Safeguards and Security Program Planning and Management

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

    2005-08-26

    Establishes program planning and management requirements for the Departments Safeguards and Security (S&S) Program. Cancels: DOE N 473.9 and DOE M 470.1-1

  4. Safeguards and Security Program Planning and Management

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

    2005-08-26

    The manual establishes program planning and management requirements for the Departments Safeguards and Security. Chg 1, dated 3-7-06 Cancels DOE N 473.9, DOE M 470.1-1 Chg 2.

  5. Safeguards Workforce Repatriation, Retention and Utilization

    SciTech Connect (OSTI)

    Gallucci, Nicholas; Poe, Sarah

    2015-10-01

    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 than 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.

  6. safeguards and security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    safeguards and security ProForce marks 65 years protecting Sandia resources, facilities, ... Over the past 65 years, the force has changed in size and structure but its mission has... ...

  7. Safeguards and Security Program - DOE Directives, Delegations...

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

    O 470.4B, Safeguards and Security Program by Mary Gallion Functional areas: Safety, Safety and Security, Security, Work Processes, To establish responsibilities for the U.S....

  8. The Concept of Goals-Driven Safeguards

    SciTech Connect (OSTI)

    R. Wigeland; T Bjornard; B. Castle

    2009-02-01

    The IAEA, NRC, and DOE regulations and requirements for safeguarding nuclear material and facilities have been reviewed and each organization’s purpose, objectives, and scope are discussed in this report. Current safeguards approaches are re-examined considering technological advancements and how these developments are changing safeguards approaches used by these organizations. Additionally, the physical protection approaches required by the IAEA, NRC, and DOE were reviewed and the respective goals, objectives, and requirements are identified and summarized in this report. From these, a brief comparison is presented showing the high-level similarities among these regulatory organizations’ approaches to physical protection. The regulatory documents used in this paper have been assembled into a convenient reference library called the Nuclear Safeguards and Security Reference Library. The index of that library is included in this report, and DVDs containing the full library are available.

  9. Potential nuclear safeguards applications for neutron generators

    SciTech Connect (OSTI)

    Lindquist, L.O.

    1980-01-01

    Many nuclear safeguards inspection instruments use neutron sources to interrogate the fissile material (commonly /sup 235/U and /sup 239/Pu) to be measured. The neutron sources currently used in these instruments are isotopics such as Californium-252, Americium-Lithium, etc. It is becoming increasingly more difficult to transport isotopic sources from one measurement location to another. This represents a significant problem for the International Atomic Energy Agency (IAEA) safeguards inspectors because they must take their safeguards instruments with them to each nuclear installation to make an independent measurement. Purpose of this paper is to review the possibility of replacing isotopic neutron sources now used in IAEA safeguards instruments with electric neutron sources such as deuterium-tritium (D-T, 14-MeV neutrons) or deuterium-deuterium (D-D, 2-MeV neutrons). The potential for neutron generators to interrogate spent-light water reactor fuel assemblies in storage pools is also reviewed.

  10. Safeguards and Security Program and Project Management

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

    2013-04-18

    The proposed revision to this Department of Energy Guide focuses on alignment of guidance for implementing key safeguard and security components to the DOE capital asset acquisition process with the revised DOE O 413.3B, Program and Project Management for Acquisition of Capital Assets, the revised DOE O 470.4B, Safeguard and Security Program, and the new series of DOE Orders replacing the DOE M 470.4 series of manuals.

  11. Integrated Safeguards and Security Management (ISSM) Policy

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

    2001-05-08

    The purpose of this Policy is to formalize an Integrated Safeguards and Security Management (ISSM) framework. Safeguards and security management systems provide a formal, organized process for planning, performing, assessing, and improving the secure conduct of work in accordance with risk-based protection strategies. These systems are institutionalized through Department of Energy (DOE) directives and contracts. Does not cancel other directives. Canceled by DOE P 470.1A.

  12. AFCI Safeguards Enhancement Study: Technology Development Roadmap

    SciTech Connect (OSTI)

    Smith, Leon E.; Dougan, A.; Tobin, Stephen; Cipiti, B.; Ehinger, Michael H.; Bakel, A. J.; Bean, Robert; Grate, Jay W.; Santi, P.; Bryan, Steven; Kinlaw, M. T.; Schwantes, Jon M.; Burr, Tom; Lehn, Scott A.; Tolk, K.; Chichester, David; Menlove, H.; Vo, D.; Duckworth, Douglas C.; Merkle, P.; Wang, T. F.; Duran, F.; Nakae, L.; Warren, Glen A.; Friedrich, S.; Rabin, M.

    2008-12-31

    The Advanced Fuel Cycle Initiative (AFCI) Safeguards Campaign aims to develop safeguards technologies and processes that will significantly reduce the risk of proliferation in the U.S. nuclear fuel cycle of tomorrow. The Safeguards Enhancement Study was chartered with identifying promising research and development (R&D) directions over timescales both near-term and long-term, and under safeguards oversight both domestic and international. This technology development roadmap documents recognized gaps and needs in the safeguarding of nuclear fuel cycles, and outlines corresponding performance targets for each of those needs. Drawing on the collective expertise of technologists and user-representatives, a list of over 30 technologies that have the potential to meet those needs was developed, along with brief summaries of each candidate technology. Each summary describes the potential impact of that technology, key research questions to be addressed, and prospective development milestones that could lead to a definitive viability or performance assessment. Important programmatic linkages between U.S. agencies and offices are also described, reflecting the emergence of several safeguards R&D programs in the U.S. and the reinvigoration of nuclear fuel cycles across the globe.

  13. Next Generation Safeguards Initiative Workshop on Enhanced Recruiting for International Safeguards

    SciTech Connect (OSTI)

    Pepper,S.; Rosenthal, M.; Fishbone, L.; Occhiogrosso, D.; Carroll, C.; Dreicer, M.; Wallace, R.; Rankhauser, J.

    2008-10-22

    In 2007, the National Nuclear Security Administration's Office of Nonproliferation and International Security (NA-24) completed a yearlong review of the challenges facing the international safeguards system today and over the next 25 years. The study found that without new investment in international safeguards, the U.S. safeguards technology base, and our ability to support International Atomic Energy Agency (IAEA) safeguards, will continue to erode and soon may be at risk. To reverse this trend, the then U.S. Secretary of Energy, Samuel Bodman, announced at the 2007 IAEA General Conference that the Department of Energy (DOE) would launch the Next Generation Safeguards Initiative (NGSI). He stated 'IAEA safeguards must be robust and capable of addressing proliferation threats. Full confidence in IAEA safeguards is essential for nuclear power to grow safely and securely. To this end, the U.S. Department of Energy will seek to ensure that modern technology, the best scientific expertise, and adequate resources are available to keep pace with expanding IAEA responsibilities.' To meet this goal, the NGSI objectives include the recruitment of international safeguards experts to work at the U.S. national laboratories and to serve at the IAEA's headquarters. Part of the latter effort will involve enhancing our existing efforts to place well-qualified Americans in a sufficient number of key safeguards positions within the IAEA's Department of Safeguards. Accordingly, the International Safeguards Project Office (ISPO) at Brookhaven National Laboratory (BNL) hosted a Workshop on Enhanced Recruiting for International Safeguards (ERIS) on October 22 and 23, 2008. The ISPO used a workshop format developed earlier with Sonalysts, Inc., that was followed at the U.S. Support Program's (USSP's) technology road-mapping sessions. ISPO invited participants from the U.S. DOE, the IAEA, the U.S. national laboratories, private industry, academia, and professional societies who either are experts in international safeguards, or understand the challenges of recruiting for technical positions. The 44 participants represented eight national laboratories, four universities, three government organizations, two international organizations, two professional organizations, and three small companies. The goal of the ERIS workshop was to improve efforts to engage U.S. citizens for IAEA positions in the Department of Safeguards. The participants considered the specific challenges of recruiting professional staff, safeguards inspectors, and managers. At the workshop's conclusion, participants presented their findings to the NNSA Office of International Regimes and Agreements (NA-243). The report's major findings are summarized.

  14. Safeguards and Security Technology Development Directory. FY 1993

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    The Safeguards and Security Technology Development Directory is published annually by the Office of Safeguards and Security (OSS) of the US Department of Energy (DOE), and is Intended to inform recipients of the full scope of the OSS R&D program. It is distributed for use by DOE headquarters personnel, DOE program offices, DOE field offices, DOE operating contractors, national laboratories, other federal agencies, and foreign governments. Chapters 1 through 7 of the Directory provide general information regarding the Technology Development Program, including the mission, program description, organizational roles and responsibilities, technology development lifecycle, requirements analysis, program formulation, the task selection process, technology development infrastructure, technology transfer activities, and current research and development tasks. These chapters are followed by a series of appendices which contain more specific information on aspects of the Program. Appendix A is a summary of major technology development accomplishments made during FY 1992. Appendix B lists S&S technology development reports issued during FY 1992 which reflect work accomplished through the OSS Technology Development Program and other relevant activities outside the Program. Finally, Appendix C summarizes the individual task statements which comprise the FY 1993 Technology Development Program.

  15. The Role of Nuclear Data in Advanced Safeguards

    SciTech Connect (OSTI)

    Santi, P.; Vo, D.; Todosow, M.; Aronson, A.; Ludewig, H.

    2007-07-01

    An important question regarding the development of advanced safeguards for the Global Nuclear Energy Partnership (GNEP) is whether the current fundamental nuclear data are sufficient to allow for the proper development of appropriate nondestructive assay (NDA) techniques to measure the nuclear materials that would be processed within GNEP. Because the reprocessing technologies that are being considered would keep various actinides co-mingled with plutonium at all times, the nuclear fuel that is processed within GNEP presents unique challenges for the various NDA techniques. To efficiently design and develop advanced NDA techniques for safeguarding this nuclear fuel, models based on accurate fundamental physics data are needed to properly simulate the characteristics of this fuel. A multi-laboratory effort is currently underway to evaluate the relevant nuclear data for developing and applying NDA techniques to measure the nuclear materials that will be processed within GNEP. The data that are currently under review includes prompt neutron multiplicity distributions for nuclides which undergo either spontaneous or neutron-induced fission, ({alpha},n) cross sections, and gamma-ray branching ratios and energies. The current status of this evaluation effort will be given along with potential areas of improvement that are needed in the fundamental nuclear data. (authors)

  16. Fundamentals of materials accounting for nuclear safeguards

    SciTech Connect (OSTI)

    Pillay, K.K.S.

    1989-04-01

    Materials accounting is essential to providing the necessary assurance for verifying the effectiveness of a safeguards system. The use of measurements, analyses, records, and reports to maintain knowledge of the quantities of nuclear material present in a defined area of a facility and the use of physical inventories and materials balances to verify the presence of special nuclear materials are collectively known as materials accounting for nuclear safeguards. This manual, prepared as part of the resource materials for the Safeguards Technology Training Program of the US Department of Energy, addresses fundamental aspects of materials accounting, enriching and complementing them with the first-hand experiences of authors from varied disciplines. The topics range from highly technical subjects to site-specific system designs and policy discussions. This collection of papers is prepared by more than 25 professionals from the nuclear safeguards field. Representing research institutions, industries, and regulatory agencies, the authors create a unique resource for the annual course titled ''Materials Accounting for Nuclear Safeguards,'' which is offered at the Los Alamos National Laboratory.

  17. Beyond Human Capital Development: Balanced Safeguards Workforce Metrics and the Next Generation Safeguards Workforce

    SciTech Connect (OSTI)

    Burbank, Roberta L.; Frazar, Sarah L.; Gitau, Ernest TN; Shergur, Jason M.; Scholz, Melissa A.; Undem, Halvor A.

    2014-03-28

    Since its establishment in 2008, the Next Generation Safeguards Initiative (NGSI) has achieved a number of objectives under its five pillars: concepts and approaches, policy development and outreach, international nuclear safeguards engagement, technology development, and human capital development (HCD). As a result of these efforts, safeguards has become much more visible as a critical U.S. national security interest across the U.S. Department of Energy (DOE) complex. However, limited budgets have since created challenges in a number of areas. Arguably, one of the more serious challenges involves NGSI’s ability to integrate entry-level staff into safeguards projects. Laissez fair management of this issue across the complex can lead to wasteful project implementation and endanger NGSI’s long-term sustainability. The authors provide a quantitative analysis of this problem, focusing on the demographics of the current safeguards workforce and compounding pressures to operate cost-effectively, transfer knowledge to the next generation of safeguards professionals, and sustain NGSI safeguards investments.

  18. Safeguards and Security for Program and Project Management

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

    2013-08-15

    This Guide addresses the implementation steps for achieving safeguards and security systems that support the Department's projection objectives.

  19. Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture

    Energy Savers [EERE]

    Workshop | Department of Energy Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop December 16, 2003 NUREG/CP-0183, Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop, June 12, 2003 U.S. Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards Washington, DC 20555-0001. PDF icon Proceedings of the Advisory Committee on Reactor

  20. New Measures to Safeguard Gas Centrifuge Enrichment Plants (Conference) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect SciTech Connect Search Results Conference: New Measures to Safeguard Gas Centrifuge Enrichment Plants Citation Details In-Document Search Title: New Measures to Safeguard Gas Centrifuge Enrichment Plants As Gas Centrifuge Enrichment Plants (GCEPs) increase in separative work unit (SWU) capacity, the current International Atomic Energy Agency (IAEA) model safeguards approach needs to be strengthened. New measures to increase the effectiveness of the safeguards approach are

  1. ORO Office Safeguards and Security Clearance Tracking System and Visitor

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

    Control System PIA, Oak Ridge Operations Office | Department of Energy Office Safeguards and Security Clearance Tracking System and Visitor Control System PIA, Oak Ridge Operations Office ORO Office Safeguards and Security Clearance Tracking System and Visitor Control System PIA, Oak Ridge Operations Office ORO Office Safeguards and Security Clearance Tracking System and Visitor Control System PIA, Oak Ridge Operations Office PDF icon ORO Office Safeguards and Security Clearance Tracking

  2. PIA - Savannah River Nuclear Solutions Electronic Safeguards Security

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

    System (E3S) | Department of Energy Electronic Safeguards Security System (E3S) PIA - Savannah River Nuclear Solutions Electronic Safeguards Security System (E3S) PIA - Savannah River Nuclear Solutions Electronic Safeguards Security System (E3S) PDF icon PIA - Savannah River Nuclear Solutions Electronic Safeguards Security System (E3S) More Documents & Publications PIA - 10th International Nuclear Graphite Specialists Meeting registration web site PIA - HSPD-12 Physical and Logical

  3. Next Generation Safeguards Initiatives at Los Alamos National Laboratory

    National Nuclear Security Administration (NNSA)

    Next Generation Safeguards Initiatives at Los Alamos National Laboratory Strengthening Human Capital for International Safeguards - 2009 * In October 2007, NNSA's Office of Nonproliferation and International Security (NA-24) urged the national laboratories to create projects devoted to improving human capital and training for nuclear safeguards as part of the Next Generation Safeguards Initiative (NGSI). * To meet this need, Los Alamos National Laboratory (LANL), Lawrence Livermore National

  4. The evolution of information-driven safeguards

    SciTech Connect (OSTI)

    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 the 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.

  5. Safeguards and Security Program Planning and Management

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

    2005-08-26

    The manual establishes program planning and management requirements for the Department’s Safeguards and Security (S&S) Program. Change 2 is a revision to Section M of both the Manual and the CRD to realign the process for establishing deviations from DOE directives containing safeguards and security requirements to reflect established Departmental policy as set forth in DOE O 251.1C. Original publication, 8-26-05; Chg 1, 3-7-06. Canceled by DOE O 470.4B

  6. Next Generation Safeguards Initiative Summer Internship Program | Argonne

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

    National Laboratory Next Generation Safeguards Initiative The Department of Energy's National Nuclear Security Administration (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 over the next 25 years. Learn More Center for Strategic Security Argonne's Center for Strategic Security (CSS) develops and implements practical

  7. Using Process Load Cell Information for IAEA Safeguards at Enrichment Plants

    SciTech Connect (OSTI)

    Laughter, Mark D; Whitaker, J Michael; Howell, John

    2010-01-01

    Uranium enrichment service providers are expanding existing enrichment plants and constructing new facilities to meet demands resulting from the shutdown of gaseous diffusion plants, the completion of the U.S.-Russia highly enriched uranium downblending program, and the projected global renaissance in nuclear power. The International Atomic Energy Agency (IAEA) conducts verification inspections at safeguarded facilities to provide assurance that signatory States comply with their treaty obligations to use nuclear materials only for peaceful purposes. Continuous, unattended monitoring of load cells in UF{sub 6} feed/withdrawal stations can provide safeguards-relevant process information to make existing safeguards approaches more efficient and effective and enable novel safeguards concepts such as information-driven inspections. The IAEA has indicated that process load cell monitoring will play a central role in future safeguards approaches for large-scale gas centrifuge enrichment plants. This presentation will discuss previous work and future plans related to continuous load cell monitoring, including: (1) algorithms for automated analysis of load cell data, including filtering methods to determine significant weights and eliminate irrelevant impulses; (2) development of metrics for declaration verification and off-normal operation detection ('cylinder counting,' near-real-time mass balancing, F/P/T ratios, etc.); (3) requirements to specify what potentially sensitive data is safeguards relevant, at what point the IAEA gains on-site custody of the data, and what portion of that data can be transmitted off-site; (4) authentication, secure on-site storage, and secure transmission of load cell data; (5) data processing and remote monitoring schemes to control access to sensitive and proprietary information; (6) integration of process load cell data in a layered safeguards approach with cross-check verification; (7) process mock-ups constructed to provide simulated load cell data; (8) hardware and software implementation for process load cell data collection; (9) costs associated with unattended monitoring of load cells (for both operator and inspector) weighed against the potential benefits of having access to such data; (10) results from field tests of load cell data collection systems in operating facilities; and (11) use of unattended load cell data to increase efficiency of on-site inspection schedules and activities.

  8. In-Born Radio Frequency Identification Devices for Safeguards Use at Gas-Centrifuge Enrichment Plants

    SciTech Connect (OSTI)

    Ward,R.; Rosenthal,M.

    2009-07-12

    Global expansion of nuclear power has made the need for improved safeguards measures at Gas Centrifuge Enrichment Plants (GCEPs) imperative. One technology under consideration for safeguards applications is Radio Frequency Identification Devices (RFIDs). RFIDs have the potential to increase IAEA inspector"s efficiency and effectiveness either by reducing the number of inspection visits necessary or by reducing inspection effort at those visits. This study assesses the use of RFIDs as an integral component of the "Option 4" safeguards approach developed by Bruce Moran, U.S. Nuclear Regulatory Commission (NRC), for a model GCEP [1]. A previous analysis of RFIDs was conducted by Jae Jo, Brookhaven National Laboratory (BNL), which evaluated the effectiveness of an RFID tag applied by the facility operator [2]. This paper presents a similar evaluation carried out in the framework of Jo’s paper, but it is predicated on the assumption that the RFID tag is applied by the manufacturer at the birth of the cylinder, rather than by the operator. Relevant diversion scenarios are examined to determine if RFIDs increase the effectiveness and/ or efficiency of safeguards in these scenarios. Conclusions on the benefits offered to inspectors by using in-born RFID tagging are presented.

  9. Hydropower, adaptive management, and biodiversity

    SciTech Connect (OSTI)

    Wieringa, M.J.; Morton, A.G.

    1996-11-01

    Adaptive management is a policy framework within which an iterative process of decision making is allowed based on the observed responses to and effectiveness of previous decisions. The use of adaptive management allows science-based research and monitoring of natural resource and ecological community responses, in conjunction with societal values and goals, to guide decisions concerning man`s activities. The adaptive management process has been proposed for application to hydropower operations at Glen Canyon Dam on the Colorado River, a situation that requires complex balancing of natural resources requirements and competing human uses. This example is representative of the general increase in public interest in the operation of hydropower facilities and possible effects on downstream natural resources and of the growing conflicts between uses and users of river-based resources. This paper describes the adaptive management process, using the Glen Canyon Dam example, and discusses ways to make the process work effectively in managing downstream natural resources and biodiversity. 10 refs., 2 figs.

  10. International safeguards: Accounting for nuclear materials

    SciTech Connect (OSTI)

    Fishbone, L.G.

    1988-09-28

    Nuclear safeguards applied by the International Atomic Energy Agency (IAEA) are one element of the non-proliferation regime'', the collection of measures whose aim is to forestall the spread of nuclear weapons to countries that do not already possess them. Safeguards verifications provide evidence that nuclear materials in peaceful use for nuclear-power production are properly accounted for. Though carried out in cooperation with nuclear facility operators, the verifications can provide assurance because they are designed with the capability to detect diversion, should it occur. Traditional safeguards verification measures conducted by inspectors of the IAEA include book auditing; counting and identifying containers of nuclear material; measuring nuclear material; photographic and video surveillance; and sealing. Novel approaches to achieve greater efficiency and effectiveness in safeguards verifications are under investigation as the number and complexity of nuclear facilities grow. These include the zone approach, which entails carrying out verifications for groups of facilities collectively, and randomization approach, which entails carrying out entire inspection visits some fraction of the time on a random basis. Both approaches show promise in particular situations, but, like traditional measures, must be tested to ensure their practical utility. These approaches are covered on this report. 15 refs., 16 figs., 3 tabs.

  11. Improving the Safeguardability of Nuclear Facilities

    SciTech Connect (OSTI)

    T. Bjornard; R. Bari; D. Hebditch; P. Peterson; M. Schanfein

    2009-07-01

    The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to reduce security risks and proliferation hazards while improving the synergy of major design features and raising operational efficiency, in a world where significant expansion of nuclear energy use may occur. Correspondingly, the U.S. DOE’s Next Generation Safeguards Initiative (NGSI) includes objectives to contribute to international efforts to develop SBD, and to apply SBD in the development of new U.S. nuclear infrastructure. Here, SBD is defined as a structured approach to ensure the timely, efficient and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical protection, and safety objectives into the overall design process for a nuclear facility, from initial planning through design, construction and operation. The SBD process, in its simplest form, may be applied usefully today within most national regulatory environments. Development of a mature approach to implementing SBD requires work in the areas of requirements definition, design processes, technology and methodology, and institutionalization. The U.S. efforts described in this paper are supportive of SBD work for international safeguards that has recently been initiated by the IAEA with the participation of many stakeholders including member States, the IAEA, nuclear technology suppliers, nuclear utilities, and the broader international nonproliferation community.

  12. Advanced Safeguards Approaches for New Fast Reactors

    SciTech Connect (OSTI)

    Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Rick L.; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

    2007-12-15

    This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.

  13. International inspection activity impacts upon DOE safeguards requirements

    SciTech Connect (OSTI)

    Zack, N.R.; Crawford, D.W.

    1995-09-01

    The US has placed certain special nuclear materials declared excess to their strategic needs under international safeguards through the International Atomic Energy Agency (IAEA). This Presidential initiative has obligated materials at several Department of Energy (DOE) facilities for these safeguards activities to demonstrate the willingness of the US to ban production or use of nuclear materials outside of international safeguards. However, IAEA inspection activities generally tend to be intrusive in nature and are not consistent with several domestic safeguards procedures implemented to reduce worker radiation exposures and increase the cost-effectiveness and efficiency of accounting for and storing of special nuclear materials. To help identify and provide workable solutions to these concerns, the Office of Safeguards and Security has conducted a program to determine possible changes to the DOE safeguards and security requirements designed to help facilities under international safeguards inspections more easily comply with domestic safeguards goals during international inspection activities. This paper will discuss the impact of international inspection activities on facility safeguards operations and departmental safeguards procedures and policies.

  14. Safeguards and Security progress report, January--December 1989

    SciTech Connect (OSTI)

    Smith, D.B.; Jaramillo, G.R.

    1990-11-01

    From January to December 1989, the Los Alamos Safeguards and Security Research and Development (R D) program carried out the activities described in the first four parts of this report: Science and Technology Base Development, Basic Systems Design, Onsite Test and Evaluation and Facility Support, and International Safeguards. For the most part, these activities were sponsored by the Department of Energy's Office of Safeguards and Security. Part 1 covers development of the basic technology essential to continuing improvements in the practice of safeguards and security. It includes our computer security R D and the activities of the DOE Center for Computer Security, which provides the basis for encouraging and disseminating this important technology. Part 2 treats activities aimed at developing methods for designing and evaluating safeguards systems, with special emphasis on the integration of the several subsystems into a real safeguards system. Part 3 describes efforts of direct assistance to the DOE and its contractors and includes consultation on materials control and accounting problems, development and demonstration of specialized techniques and instruments, and comprehensive participation in the design and demonstration of advanced safeguards systems. Part 3 also reports a series of training courses in various aspects of safeguards that makes the technology more accessible to those who must apply it. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Part 5 reports several safeguards-related activities that have sponsors other than the DOE/OSS. 87 refs., 52 figs.

  15. The new geospatial tools: global transparency enhancing safeguards verification

    SciTech Connect (OSTI)

    Pabian, Frank Vincent

    2010-09-16

    This paper focuses on the importance and potential role of the new, freely available, geospatial tools for enhancing IAEA safeguards and how, together with commercial satellite imagery, they can be used to promote 'all-source synergy'. As additional 'open sources', these new geospatial tools have heralded a new era of 'global transparency' and they can be used to substantially augment existing information-driven safeguards gathering techniques, procedures, and analyses in the remote detection of undeclared facilities, as well as support ongoing monitoring and verification of various treaty (e.g., NPT, FMCT) relevant activities and programs. As an illustration of how these new geospatial tools may be applied, an original exemplar case study provides how it is possible to derive value-added follow-up information on some recent public media reporting of a former clandestine underground plutonium production complex (now being converted to a 'Tourist Attraction' given the site's abandonment by China in the early 1980s). That open source media reporting, when combined with subsequent commentary found in various Internet-based Blogs and Wikis, led to independent verification of the reporting with additional ground truth via 'crowdsourcing' (tourist photos as found on 'social networking' venues like Google Earth's Panoramio layer and Twitter). Confirmation of the precise geospatial location of the site (along with a more complete facility characterization incorporating 3-D Modeling and visualization) was only made possible following the acquisition of higher resolution commercial satellite imagery that could be correlated with the reporting, ground photos, and an interior diagram, through original imagery analysis of the overhead imagery.

  16. Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design

    SciTech Connect (OSTI)

    Coles, Garill A.; Hockert, John; Gitau, Ernest TN; Zentner, Michael D.

    2013-01-26

    FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

  17. Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design

    SciTech Connect (OSTI)

    Coles, Garill A.; Gitau, Ernest TN; Hockert, John; Zentner, Michael D.

    2012-11-09

    FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

  18. The International Safeguards Technology Base: How is the Patient Doing? An Exploration of Effective Metrics

    SciTech Connect (OSTI)

    Schanfein, Mark J; Gouveia, Fernando S

    2010-07-01

    The term “Technology Base” is commonly used but what does it mean? Is there a common understanding of the components that comprise a technology base? Does a formal process exist to assess the health of a given technology base? These are important questions the relevance of which is even more pressing given the USDOE/NNSA initiatives to strengthen the safeguards technology base through investments in research & development and human capital development. Accordingly, the authors will establish a high-level framework to define and understand what comprises a technology base. Potential goal-driven metrics to assess the health of a technology base will also be explored, such as linear demographics and resource availability, in the hope that they can be used to better understand and improve the health of the U.S. safeguards technology base. Finally, through the identification of such metrics, the authors will offer suggestions and highlight choices for addressing potential shortfalls.

  19. The US Support Program Assistance to the IAEA Safeguards Information Technology, Collection, and Analysis 2008

    SciTech Connect (OSTI)

    Tackentien,J.

    2008-06-12

    One of the United States Support Program's (USSP) priorities for 2008 is to support the International Atomic Energy Agency's (IAEA) development of an integrated and efficient safeguards information infrastructure, including reliable and maintainable information systems, and effective tools and resources to collect and analyze safeguards-relevant information. The USSP has provided funding in support of this priority for the ISIS Re-engineering Project (IRP), and for human resources support to the design and definition of the enhanced information analysis architecture project (nVision). Assistance for several other information technology efforts is provided. This paper will report on the various ongoing support measures undertaken by the USSP to support the IAEA's information technology enhancements and will provide some insights into activities that the USSP may support in the future.

  20. Next generation safeguards initiative (NGSI) program plan for safeguards by design

    SciTech Connect (OSTI)

    Demuth, Scott F; Budlong - Sylvester, Kory; Lockwood, Dunbar

    2010-01-01

    Safeguards by Design (SBD) is defined as the incorporation of safeguards features early in the design phase of a new nuclear facility in order to avoid the need to redesign the facility at a later date, or retrofit the completed facility. Not only can SBD avoid the need for redesign or retrofit, but consideration of safeguards features early in the facility design effort can provide for a more efficient and effective safeguards design. A program has been initiated by the United States Department of Energy during the past several years to develop, demonstrate and institutionalization SBD. This plan has been developed in parallel with a similar effort at the IAEA while taking into account their achievements and future plans. The United States SBD program is focused on (1) identification of best practices that satisfy existing safeguards requirements, (2) identification of advanced concepts where best practices can be improved, and (3) institutionalizing SBD by gaining its acceptance as a global norm for the design of new nuclear facilities. SBD guidance documents are being prepared as an aid to industry for their design activities, to describe the relationship between requirements, best practices, and advanced concepts. SBD 'lessons learned' studies have been conducted to help identify the existing best practices and potential areas for improvement. Finally, acceptance as a global norm is being pursued by way of international workshops, engagement with industry and the IAEA, and setting an example by way of its use in new nuclear facilities in the United States.

  1. UNCLASSIFIED Nuclear Materials Management & Safeguards System

    National Nuclear Security Administration (NNSA)

    Nuclear Materials Management & Safeguards System CHANGE OF PROJECT NUMBER UPDATE PROJECT Project Number: Title: Date Valid: Date Deactivated: Classification Codes: Project Number: Project Title: Associated Materials: Programmatic RIS Previous Project Number(s) Status Code Allotment Code (S=Supplier, U=User) I authorize that the information listed above is for the NMMSS Program to use as part of the project number conversion process for this facility. Signature of Authorized Official Date

  2. Implementation of Safeguards and Security Policy Panels

    Energy Savers [EERE]

    5,2008 MEMORANDUM FOR DISTRIBUTION FROM URITY OFFICER AND SECURITY SUBJECT: Implementation of Safeguards and Security Policy Panels The Office of Health, Safety and Security (HSS) recognizes the importance of well- conceived strategies and policies to support and communicate the security posture of the Department. In order for our security policies to properly reflect and enable Department of Energy corporate strategies, early and frequent communication between policy makers and end users is

  3. Safeguards and Security Functional Area Qualification Standard

    Energy Savers [EERE]

    1-2009 May 2009 DOE STANDARD SAFEGUARDS AND SECURITY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1171-2009 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1171-2009 iii APPROVAL The Federal

  4. Science and Technology Challenges for International Safeguards

    SciTech Connect (OSTI)

    Mark Schanfein

    2009-07-01

    The science and technology challenges for international safeguards range from cutting edge physics needs to practical technology solutions for high volume data handling and analysis issues. This paper will take a narrow look at some of the predominant challenges, which include those at high throughput commercial facilities and those in the detection of undeclared facilities. It is hoped that by highlighting these areas it can encourage a concerted effort by scientific institutions and industry to provide robust cost-effective solutions.

  5. Safeguard Requirements for Fusion Power Plants

    SciTech Connect (OSTI)

    Robert J. Goldston and Alexander Glaser

    2012-08-10

    Nuclear proliferation risks from magnetic fusion energy associated with access to fissile materials can be divided into three main categories: 1) clandestine production of fissile material in an undeclared facility, 2) covert production and diversion of such material in a declared and safeguarded facility, and 3) use of a declared facility in a breakout scenario, in which a state openly produces fissile material in violation of international agreements. The degree of risk in each of these categories is assessed, taking into account both state and non-state actors, and it is found that safeguards are required for fusion energy to be highly attractive from a non-proliferation standpoint. Specific safeguard requirements and R&D needs are outlined for each category of risk, and the technical capability of the ITER experiment, under construction, to contribute to this R&D is noted. A preliminary analysis indicates a potential legal pathway for fusion power systems to be brought under the Treaty for the Non-Proliferation of Nuclear Weapons. "Vertical" proliferation risks associated with tritium and with the knowledge that can be gained from inertial fusion energy R&D are outlined.

  6. Voluntary Protection Program Onsite Review, Safeguards and Security -

    Energy Savers [EERE]

    October 2011 | Department of Energy Safeguards and Security - October 2011 Voluntary Protection Program Onsite Review, Safeguards and Security - October 2011 October 2011 Evaluation to determine whether Safeguards and Security is continuing to perform at a level deserving DOE-VPP Star recognition. The Team conducted its review during September 26 - October 6, 2011 to determine whether Mission Support Alliance, LLC is continuing to perform at a level deserving DOE-VPP Star recognition. PDF

  7. 2015 Safeguards and Security Directors Conference - July 14 - 16, 2015 |

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

    Department of Energy Safeguards and Security Directors Conference - July 14 - 16, 2015 2015 Safeguards and Security Directors Conference - July 14 - 16, 2015 April 20, 2015 - 1:20pm Addthis The 2015 Safeguards and Security Directors Conference will bring together both Federal and Contractor senior security directors and managers from across the Department of Energy and other invited government agencies. This event will address many of the significant policy updates, reorganization, and

  8. Modeling and Simulation for Safeguards and Nonproliferation Workshop

    SciTech Connect (OSTI)

    Gilligan, Kimberly V.; Kirk, Bernadette Lugue

    2015-01-01

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

  9. Voluntary Protection Program Onsite Review, Safeguards and Security -

    Office of Environmental Management (EM)

    August 2012 | Department of Energy Safeguards and Security - August 2012 Voluntary Protection Program Onsite Review, Safeguards and Security - August 2012 August 2012 Evaluation to determine whether Safeguards and Security at Hanford is continuing to perform at a level deserving DOE-VPP Star recognition. The Team conducted its review on August 23, 2012 to determine whether Mission Support Alliance, LLC is continuing to perform at a level deserving DOE-VPP Star recognition. PDF icon Voluntary

  10. Working Toward Robust Process Monitoring for Safeguards Applications

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Working Toward Robust Process Monitoring for Safeguards Applications Citation Details In-Document Search Title: Working Toward Robust Process Monitoring for Safeguards Applications New safeguards technologies allow continuous monitoring of plant processes. Efforts to deploy these technologies, as described in a preponderance of literature, typically have consisted of case studies attempting to prove their efficacy in proof-of-principle installations. While the

  11. Presented at the Second International Meeting on Next Generation Safeguards

    National Nuclear Security Administration (NNSA)

    | National Nuclear Security Administration Second International Meeting on Next Generation Safeguards October 26, 2009 Presented at the Second International Meeting on Next Generation SafeguardsPresented by Thomas D'Agostino, Administrator, NNSA Good morning and welcome to the Second International Meeting on Next Generation Safeguards. Let me start by thanking Deputy Minister Moriguchi for his opening remarks and expressing our great appreciation to the Japan Ministry of Education, Culture,

  12. Safeguards-by-Design: Early Integration of Physical Protection and Safeguardability into Design of Nuclear Facilities

    SciTech Connect (OSTI)

    T. Bjornard; R. Bean; S. DeMuth; P. Durst; M. Ehinger; M. Golay; D. Hebditch; J. Hockert; J. Morgan

    2009-09-01

    The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to minimize proliferation and security risks as the use of nuclear energy expands worldwide. This paper defines a generic SBD process and its incorporation from early design phases into existing design / construction processes and develops a framework that can guide its institutionalization. SBD could be a basis for a new international norm and standard process for nuclear facility design. This work is part of the U.S. DOE’s Next Generation Safeguards Initiative (NGSI), and is jointly sponsored by the Offices of Non-proliferation and Nuclear Energy.

  13. Safeguards and Security Oversight and Assessments Implementation Guide

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

    2007-12-21

    This Guide identifies acceptable methods for implementing the safeguards and security provisions of DOE O 226.1A. Canceled by DOE N 251.80.

  14. PNNL hosts NNSA early-career safeguards professionals | National...

    National Nuclear Security Administration (NNSA)

    Participants saw the inner workings of nuclear production, ... the International Atomic Energy Agency. "Participants came ... aiming for-ensuring a sustainable safeguards capability ...

  15. Microsoft PowerPoint - IAEA Safeguards Reporting Requirements...

    National Nuclear Security Administration (NNSA)

    Columbia, SC (fuel fabricator) * K-Area Material Storage (KAMS) facility at the DOE Savannah River Site, Aiken, SC - no facility attachment 10 CFR Part 75, Safeguards on ...

  16. Safeguards and Security for Program and Project Management -...

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

    Program Management, Property Management, Safety and Security The Guide provides a methodology for implementing the safeguards and security requirements of DOE O 413.3B....

  17. Using Rules-Based Event Processing For Safeguards Monitoring...

    Office of Scientific and Technical Information (OSTI)

    Title: Using Rules-Based Event Processing For Safeguards Monitoring System No abstract prepared. Authors: Younkin, James R 1 ; Pickett, Chris A 1 ; Richardson, Dave 1 ; ...

  18. Next Generation Safeguards Initiative at Los Alamos National...

    Office of Scientific and Technical Information (OSTI)

    Initiative at Los Alamos National Laboratory - student perspective Citation Details In-Document Search Title: Next Generation Safeguards Initiative at Los Alamos National ...

  19. Summary of safeguards interactions between Los Alamos and Chinese scientists

    SciTech Connect (OSTI)

    Eccleston, G.W.

    1994-04-20

    Los Alamos has been collaborating since 1984 with scientists from the Chinese Institute of Atomic Energy (CIAE) to develop nuclear measurement instrumentation and safeguards systems technologies that will help China support implementation of the nonproliferation treaty (NPT). To date, four Chinese scientists have visited Los Alamos, for periods of six months to two years, where they have studied nondestructive assay instrumentation and learned about safeguards systems and inspection techniques that are used by International Atomic Energy Agency (IAEA) inspectors. Part of this collaboration involves invitations from the CIAE to US personnel to visit China and interact with a larger number of Institute staff and to provide a series of presentations on safeguards to a wider audience. Typically, CIAE scientists, Beijing Institute of Nuclear Engineering (BINE) staff, and officials from the Government Safeguards Office attend the lectures. The BINE has an important role in developing the civilian nuclear power fuel cycle. BINE is designing a reprocessing plant for spent nuclear fuel from Chinese nuclear Power reactors. China signed the nonproliferation treaty in 1992 and is significantly expanding its safeguards expertise and activities. This paper describes the following: DOE support for US and Chinese interactions on safeguards; Chinese safeguards; impacts of US-China safeguards interactions; and possible future safeguards interactions.

  20. Voluntary Protection Program Onsite Review, Safeguards and Security...

    Office of Environmental Management (EM)

    Safeguards and Security - August 2012 Voluntary Protection Program Onsite Review, FLUOR HANFORD SAS - February 2008 Voluntary Protection Program Onsite Review, Hanford...

  1. Safeguards & Security | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Safeguards & Security Integrated Support Center (ISC) ISC Home About Services Freedom of Information Act (FOIA) Privacy Act NEPA Documents Contact Information Integrated Support ...

  2. Parker, J.L. 98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL...

    Office of Scientific and Technical Information (OSTI)

    for plutonium and americium-241 decay corrections Sampson, T.E.; Parker, J.L. 98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION; AMERICIUM 241; DECAY; PLUTONIUM;...

  3. Microsoft PowerPoint - Implementation of IAEA safeguards_Peter...

    National Nuclear Security Administration (NNSA)

    Subcommittee on International Safeguards and Monitoring (SISM) IAEA Steering Committee (IAEA-SC) National Security Council (NSC) Non-Proliferation IPC Sub-Interagency Policy ...

  4. An American Academy for Training Safeguards Inspectors - An Idea Revisited

    SciTech Connect (OSTI)

    Philip Casey Durst; Robert Bean

    2010-07-01

    In 2009, we presented the idea of an American academy for training safeguards inspectors for the International Atomic Energy Agency (IAEA), due to the declining percentage of Americans in that international organization. In this paper we assert that there is still a compelling need for this academy. While the American Safeguards Academy would be useful in preparing and pre-training American inspectors for the IAEA, it would also be useful for preparing Americans for domestic safeguards duties in the U.S. Department of Energy (DOE), U.S. DOE National Laboratories, and the U.S. Nuclear Regulatory Commission (NRC). It is envisioned that such an academy would train graduate and post-graduate university students, DOE National Laboratory interns, and nuclear safeguards professionals in the modern equipment, safeguards measures, and approaches currently used by the IAEA. It is also envisioned that the Academy would involve the domestic nuclear industry, which could provide use of commercial nuclear facilities for tours and demonstrations of the safeguards tools and methods in actual nuclear facilities. This would be in support of the U.S. DOE National Nuclear Security Administration’s Next Generation Safeguards Initiative (NGSI). This training would also help American nuclear safeguards and non-proliferation professionals better understand the potential limitations of the current tools used by the IAEA and give them a foundation from which to consider even more effective and efficient safeguards measures and approaches.

  5. FAQS Reference Guide – Safeguards and Security General Technical Base

    Broader source: Energy.gov [DOE]

    This reference guide addresses the competency statements in the July 2009 edition of DOE-STD-1123-2009, Safeguards and Security General Technical Base Qualification Standard.

  6. Safeguards and Security for Program and Project Management

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

    2013-08-15

    The Guide provides a methodology for implementing the safeguards and security requirements of DOE O 413.3B. Supersedes DOE G 413.3-3.

  7. A study of a zone approach to IAEA (International Atomic Energy Agency) safeguards: The low-enriched-uranium zone of a light-water-reactor fuel cycle

    SciTech Connect (OSTI)

    Fishbone, L.G.; Higinbotham, W.A.

    1986-06-01

    At present the IAEA designs its safeguards approach with regard to each type of nuclear facility so that the safeguards activities and effort are essentially the same for a given type and size of nuclear facility wherever it may be located. Conclusions regarding a state are derived by combining the conclusions regarding the effectiveness of safeguards for the individual facilities within a state. In this study it was convenient to define three zones in a state with a closed light-water-reactor nuclear fuel cycle. Each zone contains those facilities or parts thereof which use or process nuclear materials of the same safeguards significance: low-enriched uranium, radioactive spent fuel, or recovered plutonium. The possibility that each zone might be treated as an extended material balance area for safeguards purposes is under investigation. The approach includes defining the relevant features of the facilities in the three zones and listing the safeguards activities which are now practiced. This study has focussed on the fresh-fuel zone, the several facilities of which use or process low-enriched uranium. At one extreme, flows and inventories would be verified at each material balance area. At the other extreme, the flows into and out of the zone and the inventory of the whole zone would be verified. There are a number of possible safeguards approaches which fall between the two extremes. The intention is to develop a rational approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the approach involving the zone as a material balance area, and for some reasonable intermediate safeguards approaches.

  8. The future of IAEA safeguards: challenges and responses

    SciTech Connect (OSTI)

    Pilat, Joseph F; Budlong - Sylvester, Kory W

    2011-01-01

    For nearly two decades, the International Atomic Energy Agency (lAEA) has been transforming its safeguards system to address the challenges posed by undeclared nuclear programs, the associated revelation of an extensive non-State nuclear procurement network and other issues, including past limits to its verification mandate and the burden of noncompliance issues. Implementing the new measures, including those in the Additional Protocol, and integrating new and old safeguards measures, remains a work in progress. Implementation is complicated by factors including the limited teclmological tools that are available to address such issues as safeguarding bulk handling facilities, detection of undeclared facilities/activities, especially related to enrichment, etc. As this process continues, new challenges are arising, including the demands of expanding nuclear power production worldwide, so-called safeguards by design for a new generation of facilities, the possible IAEA role in a fissile material cutoff treaty and other elements of the arms control and disarmament agenda, the possible role in 'rollback' cases, etc. There is no doubt safeguards will need to evolve in the future, as they have over the last decades. In order for the evolutionary path to proceed, there will inter alia be a need to identify technological gaps, especially with respect to undeclared facilities, and ensure they are filled by adapting old safeguards technologies, by developing and introducing new and novel safeguards teclmologies and/or by developing new procedures and protocols. Safeguards will also need to respond to anticipated emerging threats and to future, unanticipated threats. This will require strategic planning and cooperation among Member States and with the Agency. This paper will address challenges to IAEA safeguards and the technological possibilities and R&D strategies needed to meet those challenges in the context of the forty-year evolution of safeguards, including the ongoing transformation of safeguards by the Agency.

  9. Nuclear Resonance Fluorescence for Safeguards Applications

    SciTech Connect (OSTI)

    Ludewigt, Bernhard A; Quiter, Brian J; Ambers, Scott D

    2011-02-04

    In nuclear resonance fluorescence (NRF) measurements, resonances are excited by an external photon beam leading to the emission of {gamma} rays with specific energies that are characteristic of the emitting isotope. The promise of NRF as a non-destructive analysis technique (NDA) in safeguards applications lies in its potential to directly quantify a specific isotope in an assay target without the need for unfolding the combined responses of several fissile isotopes as often required by other NDA methods. The use of NRF for detection of sensitive nuclear materials and other contraband has been researched in the past. In the safeguards applications considered here one has to go beyond mere detection and precisely quantify the isotopic content, a challenge that is discussed throughout this report. Basic NRF measurement methods, instrumentation, and the analytical calculation of NRF signal strengths are described in Section 2. Well understood modeling and simulation tools are needed for assessing the potential of NRF for safeguards and for designing measurement systems. All our simulations were performed with the radiation transport code MCNPX, a code that is widely used in the safeguards community. Our initial studies showed that MCNPX grossly underestimated the elastically scattered background at backwards angles due to an incorrect treatment of Rayleigh scattering. While new, corrected calculations based on ENDF form factors showed much better agreement with experimental data for the elastic scattering of photons on an uranium target, the elastic backscatter is still not rigorously treated. Photonuclear scattering processes (nuclear Thomson, Delbruck and Giant Dipole Resonance scattering), which are expected to play an important role at higher energies, are not yet included. These missing elastic scattering contributions were studied and their importance evaluated evaluated against data found in the literature as discussed in Section 3. A transmission experiment was performed in September 2009 to test and demonstrate the applicability of the method to the quantitative measurement of an isotope of interest embedded in a thick target. The experiment, data analysis, and results are described in Section 4. The broad goal of our NRF studies is to assess the potential of the technique in safeguards applications. Three examples are analyzed in Section 5: the isotopic assay of spent nuclear fuel (SNF), the measurement of {sup 235}U enrichment in UF{sub 6} cylinders, and the determination of {sup 239}Pu in mixed oxide (MOX) fuel. The study of NRF for the assay of SNF assemblies was supported by the Next Generation Safeguards Initiative (NGSI) of the U.S. Department of Energy as part of a large multi-lab/university effort to quantify the plutonium (Pu) mass in spent nuclear fuel assemblies and to detect the diversion of pins with non-destructive assay (NDA) methods. NRF is one of 14 NDA techniques being researched. The methodology for performing and analyzing quantitative NRF measurements was developed for determining Pu mass in SNF and is extensively discussed in this report. The same methodology was applied to the assessment of NRF for the measurement of {sup 235}U enrichment and the determination of {sup 239}Pu in MOX fuel. The analysis centers on determining suitable NRF measurement methods, measurement capabilities that could be realized with currently available instrumentation, and photon source and detector requirements for achieving useful NDA capabilities.

  10. A Simple Candle Filter Safeguard Device

    SciTech Connect (OSTI)

    Hurley, J.P.; Henderson, A.K.; Swanson, M.L.

    2002-09-18

    In order to reach the highest possible efficiencies in a coal-fired turbine-based power system, the turbine should be directly fired with the products of coal utilization. Two main designs employ these turbines: those based on pressurized fluidized-bed combustors (PFBCs) and those based on integrated gasification combined cycles (IGCCs). In both designs, the suspended particulates, or dust, must be cleaned from the gas before it enters the turbine to prevent fouling and erosion of the blades. To produce the cleanest gas, barrier filters are being developed and are in commercial use. Barrier filters are composed of porous, high-temperature materials that allow the hot gas to pass but collect the dust on the surface. The three main configurations are candle, cross-flow, and tube. Both candle and tube filters have been tested extensively. They are primarily composed of coarsely porous ceramic that serves as a structural support, overlain with a thin, microporous ceramic layer o n the dirty gas side that serves as the primary filter surface. They are highly efficient at removing particulate matter from the gas stream and, because of their ceramic construction, are resistant to gas and ash corrosion. However, ceramics are brittle, and individual elements can fail, allowing the particulates to pass through the hole left by the filter element and erode the turbine. Because of the possibility of occasional filter breakage, safeguard devices (SGDs) must be employed to prevent the dust streaming through broken filters from reaching the turbine. The Energy & Environmental Research Center (EERC) safeguard device is composed of three main parts: the ceramic substrate, the adhesive coating, and the safeguard device housing. This report describes the development and laboratory testing of each of those parts as well as the bench-scale performance of both types of complete SGDs.

  11. Safeguards and security status report, August 1981-January 1982

    SciTech Connect (OSTI)

    Shipley, J.P.

    1982-09-01

    From August 1981 through January 1982, the Los Alamos Safeguards and Security Program was involved in many activities that are described in the four parts of this report: Nuclear Facility Safeguards Support, Security Development and Support, Safeguards Technology Development, and International Support. Part 1 covers those efforts of direct assistance to the Department of Energy and the Nuclear Regulatory Commission licensee facilities. This assistance varies from consultation on materials accounting problems, through development of specialized techniques and devices, to comprehensive participation in the design and implementation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards helps make the technology more accessible to those who must apply it. Part 2 concerns a relatively new set of activities at Los Alamos aimed at the security of information and computer systems. The focus this period has been on furthering the development of the Computer Security Center, which provides the basis for encouraging and disseminating the emerging technology. Part 3 describes the development efforts that are essential to continued improvements in the practice of safeguards. Although these projects are properly classified as developmental, in every case they are directed ultimately at recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. In addition, enrichment plant safeguards, especially those concerning the Gaseous Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer.

  12. Interactive Simulation of Nuclear Materials Safeguards and Security

    Energy Science and Technology Software Center (OSTI)

    1994-03-14

    THIEF is an interactive computer simulation or computer game of the safeguards and security (S&S) systems of a nuclear facility. The user is placed in the role of a non-violent insider attempting to remove special nuclear material from the facility. All portions of the S&S system that are relevant to the non-violent insider threat are included. The computer operates the S&S systems and attempts to detect the loss of the nuclear material. Both the physicalmore » protection system and the materials control and accounting system are modeled. The description of the facility and its S&S systems are defined by the user with the aid of an input module. All aspects of the facility description are provided by the user. The program has a custom graphical user interface to facilitate its use by people with limited computer experience. The custom interface also allows it to run on relatively small computer systems.« less

  13. A colalborative environment for information driven safeguards

    SciTech Connect (OSTI)

    Scott, Mark R; Michel, Kelly D

    2010-09-15

    For two decades, the IAEA has recognized the need for a comprehensive and strongly integrated Knowledge Management system to support its Information Driven Safeguards activities. In the past, plans for the development of such a system have progressed slowly due to concerns over costs and feasibility. In recent years, Los Alamos National Laboratory has developed a knowledge management system that could serve as the basis for an IAEA Collaborative Environment (ICE). The ICE derivative knowledge management system described in this paper addresses the challenge of living in an era of information overload coupled with certain knowledge shortfalls. The paper describes and defines a system that is flexible, yet ensures coordinated and focused collaboration, broad data evaluation capabilities, architected and organized work flows, and improved communications. The paper and demonstration of ICE will utilize a hypothetical scenario to highlight the functional features that facilitate collaboration amongst and between information analysts and inspectors. The scenario will place these two groups into a simulated planning exercise for a safeguards inspection drawing upon past data acquisitions, inspection reports, analyst conclusions, and a coordinated walk-through of a 3-D model of the facility. Subsequent to the conduct of the simulated facility inspection, the detection of an anomaly and pursuit of follow up activities will illustrate the event notification, information sharing, and collaborative capabilities of the system. The use of a collaborative environment such as ICE to fulfill the complicated knowledge management demands of the Agency and facilitate the completion of annual State Evaluation Reports will also be addressed.

  14. Electrochemically Modulated Separation for Plutonium Safeguards

    SciTech Connect (OSTI)

    Pratt, Sandra H.; Breshears, Andrew T.; Arrigo, Leah M.; Schwantes, Jon M.; Duckworth, Douglas C.

    2013-12-31

    Accurate and timely analysis of plutonium in spent nuclear fuel is critical in nuclear safeguards for detection of both protracted and rapid plutonium diversions. Gamma spectroscopy is a viable method for accurate and timely measurements of plutonium provided that the plutonium is well separated from the interfering fission and activation products present in spent nuclear fuel. Electrochemically modulated separation (EMS) is a method that has been used successfully to isolate picogram amounts of Pu from nitric acid matrices. With EMS, Pu adsorption may be turned "on" and "off" depending on the applied voltage, allowing for collection and stripping of Pu without the addition of chemical reagents. In this work, we have scaled up the EMS process to isolate microgram quantities of Pu from matrices encountered in spent nuclear fuel during reprocessing. Several challenges have been addressed including surface area limitations, radiolysis effects, electrochemical cell performance stability, and chemical interferences. After these challenges were resolved, 6 µg Pu was deposited in the electrochemical cell with approximately an 800-fold reduction of fission and activation product levels from a spent nuclear fuel sample. Modeling showed that these levels of Pu collection and interference reduction may not be sufficient for Pu detection by gamma spectroscopy. The main remaining challenges are to achieve a more complete Pu isolation and to deposit larger quantities of Pu for successful gamma analysis of Pu. If gamma analyses of Pu are successful, EMS will allow for accurate and timely on-site analysis for enhanced Pu safeguards.

  15. Safeguards and security progress report, January-December 1985

    SciTech Connect (OSTI)

    Not Available

    1987-03-01

    From January to December 1985, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Safeguards Operations, Security Development and Support, Safeguards Technology Development, and International Support. Part 1 covers efforts of direct assistance to the Department of Energy and Nuclear Regulatory Commission licensee facilities. This assistance includes consultation on materials accounting problems, development and demonstration of specialized techniques and instruments, and comprehensive participation in the design and evaluation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards makes the technology more accessible to those who must apply it. Part 2 treats activities aimed at the security of information and computer systems. Our focus this period was on continuing the activities of the Center for Computer Security, which provides the basis for encouraging and disseminating this emerging technology, and on the development and demonstration of secure computer systems. Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards and international safeguards for reprocessing plants required a significant portion of our resources. All of these efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in our benefiting from field experiences in operating environments.

  16. Third International Meeting on Next Generation Safeguards:Safeguards-by-Design at Enrichment Facilities

    SciTech Connect (OSTI)

    Long, Jon D.; McGinnis, Brent R; Morgan, James B; Whitaker, Michael; Lockwood, Mr. Dunbar; Shipwash, Jacqueline L

    2011-01-01

    The Third International Meeting on Next Generation Safeguards (NGS3) was hosted by the U.S. Department of Energy (DOE)/National Nuclear Security Administration's (NNSA) Office of Nonproliferation and International Security (NIS) in Washington, D.C. on 14-15 December 2010; this meeting focused on the Safeguards-by-Design (SBD) concept. There were approximately 100 participants from 13 countries, comprised of safeguards policy and technical experts from government and industry. Representatives also were present from the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), the European Atomic Energy Agency (Euratom), and the International Atomic Energy Agency (IAEA). The primary objective of this meeting was to exchange views and provide recommendations on implementation of the SBD concept for four specific nuclear fuel cycle facility types: gas centrifuge enrichment plants (GCEPs), GEN III and GEN IV reactors, aqueous reprocessing plants, and mixed oxide fuel fabrication facilities. The general and facility-specific SBD documents generated from the four working groups, which were circulated for comment among working group participants, are intended to provide a substantive contribution to the IAEA's efforts to publish SBD guidance for these specific types of nuclear facilities in the near future. The IAEA has described the SBD concept as an approach in which 'international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and decommissioning.' As part of the Next Generation Safeguards Initiative (NGSI), the DOE is working to establish SBD as a global norm through DOE laboratory studies, international workshops, engagement with industry and the IAEA, and setting an example through its use in new nuclear facilities in the United States. This paper describes the discussion topics and final recommendations of the Enrichment Facilities Working Group. The working group participants were tasked with providing recommendations for facility operators and designers, while promoting the IAEA's objectives of: (1) avoiding costly and time-consuming redesign work or retrofits of new nuclear facilities and (2) providing for more effective and efficient implementation of international safeguards.

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

    SciTech Connect (OSTI)

    Janssens-Maenhout, Greet; Kusumi, R.; Daures, Pascal A.; Janssens, Willem; Dickman, Deborah 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 still 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 a broad range of subjects, including nuclear material accountancy principles, legal definitions and the regulatory base and inspection tools and techniques. This 60% core part is given by representatives from regulatory bodies (The International Atomic Energy Agency (IAEA), Institute for Radiological Protection and Nuclear Safety, Directorate General for Nuclear Energy and Transport), industry (AREVA, British Nuclear Group), and research (Stockholm University, Hamburg University, Joint Research Centre-Institute of Transuranic Elements, and Joint Research Centre-Institute for the Protection of the Citizen). The remaining part is completed with topical lectures addressed by invited lecturers, such as from Pacific Northwest National Laboratory and the IAEA addressing topics of physical protection, illicit trafficking, the Iraq case study, exercises, including satellite imagery interpretation etc. With this structure of a stable core plus a variable set of invited lectures, the course will remain sustainable and up-to-date. A syllabus provides the students a homogeneous set of information material in nuclear safeguards and nonproliferation matters at the European and international level. In this way, the ESARDA TKMWG aims to contribute to a two-fold scientific-technical and political-juridical education and training.

  18. Safeguards and security progress report, January-December 1984

    SciTech Connect (OSTI)

    Smith, D.B.

    1986-01-01

    From January to December 1984, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Nuclear Facility Support, Security Development and Support, Safeguards Technology Development, and International Safeguards. Part 1 covers efforts of direct assistance to the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) licensee facilities. Part 2 treats activities aimed at the security of information and computer systems. was Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards, especially those concerning the Gas Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in benefiting from field experiences in operating environments.

  19. Safeguards and security progress report, January-December 1983

    SciTech Connect (OSTI)

    Smith, D.B.

    1984-09-01

    From January to December 1983, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Nuclear Facility Support, Security Development and Support, Safeguards Technology Development, and International Safeguards. Part 1 covers efforts of direct assistance to the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) licensee facilities. This assistance includes consultation on materials accounting problems, development of specialized techniques and instruments, and comprehensive participation in the design and implementation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards makes the technology more accessible to those who must apply it. Part 2 treats activities aimed at the security of information and computer systems. Our focus this peiod was on continuing the activities of the Computer Security Center, which provides the basis for encouraging and disseminating this emerging technology, and on the development and demonstration of secure computer systems. Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards, especially those concerning the Gas Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in our benefiting from field experiences in operating environments.

  20. Apparatus for safeguarding a radiological source

    DOE Patents [OSTI]

    Bzorgi, Fariborz M

    2014-10-07

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

  1. Safeguards optimization tool for the advanced fuel cycle facility

    SciTech Connect (OSTI)

    DeMuth, Scott; Thomas, Kenneth; Dixon, Eleanor

    2007-07-01

    The planned Advanced Fuel Cycle Facility (AFCF) is intended to support the Global Nuclear Energy Partnership (GNEP) by demonstrating separation and fuel fabrication processes required to support an Advanced Burner Reactor. Advanced safeguards will be based on new world standards for the prevention of nuclear materials proliferation. Safeguarding nuclear facilities includes inventory accountancy, process monitoring, and containment and surveillance. An effort has been undertaken to optimize selection of technology for advanced safeguards accountancy, by way of using the Standard Error in the Inventory Difference (SEID) as a basis for cost/benefit analyses. (authors)

  2. Analysis of the impact of safeguards criteria

    SciTech Connect (OSTI)

    Mullen, M.F.; Reardon, P.T.

    1981-01-01

    As part of the US Program of Technical Assistance to IAEA Safeguards, the Pacific Northwest Laboratory (PNL) was asked to assist in developing and demonstrating a model for assessing the impact of setting criteria for the application of IAEA safeguards. This report presents the results of PNL's work on the task. The report is in three parts. The first explains the technical approach and methodology. The second contains an example application of the methodology. The third presents the conclusions of the study. PNL used the model and computer programs developed as part of Task C.5 (Estimation of Inspection Efforts) of the Program of Technical Assistance. The example application of the methodology involves low-enriched uranium conversion and fuel fabrication facilities. The effects of variations in seven parameters are considered: false alarm probability, goal probability of detection, detection goal quantity, the plant operator's measurement capability, the inspector's variables measurement capability, the inspector's attributes measurement capability, and annual plant throughput. Among the key results and conclusions of the analysis are the following: the variables with the greatest impact on the probability of detection are the inspector's measurement capability, the goal quantity, and the throughput; the variables with the greatest impact on inspection costs are the throughput, the goal quantity, and the goal probability of detection; there are important interactions between variables. That is, the effects of a given variable often depends on the level or value of some other variable. With the methodology used in this study, these interactions can be quantitatively analyzed; reasonably good approximate prediction equations can be developed using the methodology described here.

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

    SciTech Connect (OSTI)

    Pepper S. 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.

  4. Microsoft PowerPoint - Implementation of IAEA safeguards_Peter Habighorst [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    Implementation of IAEA Safeguards in the U.S. Peter Habighorst, MC&A Branch Chief U.S. Nuclear Regulatory Commission Background 2 1957 Nonproliferation Treaty (NPT) 1970 INFCIRC/66 Safeguards Model INFCIRC/153 Comprehensive Safeguards Model 1965 1972 International Atomic Energy Agency (IAEA) 1945 INFCIRC/540 Additional Protocol Model 1997 1953 Atoms for Peace The NPT requires NNWS to accept full-scope safeguards and to conclude a comprehensive safeguards agreement with the IAEA Information

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

    SciTech Connect (OSTI)

    Dreicer, M; Anzelon, G; Essner, J; Dougan, A; Doyle, J; Boyer, B; Hypes, P; Sokova, E; Wehling, F

    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 to 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 students were senior classmen or new master's degree graduates from MIIS specializing in nonproliferation policy studies. Other university/organizations represented: University of California in LA, Stanford University, and the IAEA. Four of the students that completed this intensive course participated in a 2-month internship at LLNL. The conclusions of the two pilot courses and internships was a NGSI Summer Student Symposium, held at LLNL, where 20 students participated in LLNL facility tours and poster sessions. The Poster sessions were designed to provide a forum for sharing the results of their summer projects and providing experience in presenting their work to a varied audience of students, faculty and laboratory staff. The success of bringing together the students from the technical and policy pilots was notable and will factor into the planning for the continued refinement of their two pilot efforts in the coming years.

  6. Electrical Safety Investment Safeguards Employees at Large Idaho Facility

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho – The Idaho Site’s main cleanup contractor is using a $1.8 million DOE investment to safeguard employees from the threat of second- and third-degree electrical arc flash burns.

  7. Development of Pattern Recognition Options for Combining Safeguards Subsystems

    SciTech Connect (OSTI)

    Burr, Thomas L.; Hamada, Michael S.

    2012-08-24

    This talk reviews project progress in combining process monitoring data and nuclear material accounting data to improve the over nuclear safeguards system. Focus on 2 subsystems: (1) nuclear materials accounting (NMA); and (2) process monitoring (PM).

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

    SciTech Connect (OSTI)

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

    1995-12-01

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

  9. International Safeguards Regime (Technical Report) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    International Safeguards Regime Citation Details In-Document Search Title: International Safeguards Regime Authors: Boyer, Brian D. [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2013-08-05 OSTI Identifier: 1089463 Report Number(s): LA-UR-13-26173 DOE Contract Number: AC52-06NA25396 Resource Type: Technical Report Research Org: Los Alamos National Laboratory (LANL) Sponsoring Org: DOE/LANL Country of Publication: United States Language: English Subject: Nuclear

  10. International safeguards recommendations for the Indian advanced heavy

    Office of Scientific and Technical Information (OSTI)

    water reactor (AHWR) (Conference) | SciTech Connect International safeguards recommendations for the Indian advanced heavy water reactor (AHWR) Citation Details In-Document Search Title: International safeguards recommendations for the Indian advanced heavy water reactor (AHWR) Authors: Murphy, Chantel L [1] ; Doyle, James E [1] ; Boyer, Brian D [1] ; Fane, Brian M [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2011-06-10 OSTI Identifier: 1072335 Report

  11. International safeguards recommendations for the Indian advanced heavy

    Office of Scientific and Technical Information (OSTI)

    water reactor (AHWR) (Conference) | SciTech Connect International safeguards recommendations for the Indian advanced heavy water reactor (AHWR) Citation Details In-Document Search Title: International safeguards recommendations for the Indian advanced heavy water reactor (AHWR) Authors: Murphy, Chantell L [1] ; Boyer, Brian D [1] ; Doyle, James E [1] ; Fane, Brian M [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2011-07-18 OSTI Identifier: 1083123 Report

  12. International safeguards recommendations for the Indian advanced heavy

    Office of Scientific and Technical Information (OSTI)

    water reactor (AHWR) (Conference) | SciTech Connect International safeguards recommendations for the Indian advanced heavy water reactor (AHWR) Citation Details In-Document Search Title: International safeguards recommendations for the Indian advanced heavy water reactor (AHWR) Ă— You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit

  13. International safeguards recommendations for the Indian advanced heavy

    Office of Scientific and Technical Information (OSTI)

    water reactor (AHWR) (Conference) | SciTech Connect International safeguards recommendations for the Indian advanced heavy water reactor (AHWR) Citation Details In-Document Search Title: International safeguards recommendations for the Indian advanced heavy water reactor (AHWR) Ă— You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit

  14. Simulated process test bed for integrated safeguards operations monitoring

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Simulated process test bed for integrated safeguards operations monitoring Citation Details In-Document Search Title: Simulated process test bed for integrated safeguards operations monitoring No abstract prepared. Authors: Laughter, Mark D [1] ; Krichinsky, Alan M [1] ; Hines, Jairus B [1] ; Kovacic, Donald N [1] ; Younkin, James R [1] + Show Author Affiliations ORNL Publication Date: 2008-01-01 OSTI Identifier: 937137 DOE Contract Number: DE-AC05-00OR22725

  15. Nuclear Materials Safeguards and Security Upgrade Project Completed Under

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

    Budget | National Nuclear Security Administration Nuclear Materials Safeguards and Security Upgrade Project Completed Under Budget April 03, 2014 WASHINGTON, D.C. - The National Nuclear Security Administration's (NNSA) Nuclear Materials Safeguards and Security Upgrade Project (NMSSUP) was recently completed approximately $1 million under its original budget of $245 million. NMSSUP upgrades security at Los Alamos National Laboratory's (LANL) Technical Area-55, a facility that houses

  16. Using Rules-Based Event Processing For Safeguards Monitoring System

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect SciTech Connect Search Results Conference: Using Rules-Based Event Processing For Safeguards Monitoring System Citation Details In-Document Search Title: Using Rules-Based Event Processing For Safeguards Monitoring System No abstract prepared. Authors: Younkin, James R [1] ; Pickett, Chris A [1] ; Richardson, Dave [1] ; Krichinsky, Alan M [1] ; Rowe, Nathan C [1] + Show Author Affiliations ORNL Publication Date: 2009-01-01 OSTI Identifier: 980699 DOE Contract

  17. Nuclear Materials Safeguards and Security Upgrade Project Completed Under

    National Nuclear Security Administration (NNSA)

    Budget | National Nuclear Security Administration Nuclear Materials Safeguards and Security Upgrade Project Completed Under Budget April 03, 2014 WASHINGTON, D.C. - The National Nuclear Security Administration's (NNSA) Nuclear Materials Safeguards and Security Upgrade Project (NMSSUP) was recently completed approximately $1 million under its original budget of $245 million. NMSSUP upgrades security at Los Alamos National Laboratory's (LANL) Technical Area-55, a facility that houses

  18. Next Generation Safeguards Initiative at Los Alamos National Laboratory -

    Office of Scientific and Technical Information (OSTI)

    student perspective (Conference) | SciTech Connect Next Generation Safeguards Initiative at Los Alamos National Laboratory - student perspective Citation Details In-Document Search Title: Next Generation Safeguards Initiative at Los Alamos National Laboratory - student perspective Authors: Murphy, Chantell L [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2011-06-10 OSTI Identifier: 1072336 Report Number(s): LA-UR-11-03370; LA-UR-11-3370 DOE Contract Number:

  19. Next Generation Safeguards Initiative at Los Alamos National Laboratory -

    Office of Scientific and Technical Information (OSTI)

    student perspective (Conference) | SciTech Connect Next Generation Safeguards Initiative at Los Alamos National Laboratory - student perspective Citation Details In-Document Search Title: Next Generation Safeguards Initiative at Los Alamos National Laboratory - student perspective Authors: Murphy, Chantell L [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2011-07-18 OSTI Identifier: 1083124 Report Number(s): LA-UR-11-04128; LA-UR-11-4128 DOE Contract Number:

  20. Nuclear Nonproliferation, International Safeguards and Nuclear Security in

    Office of Scientific and Technical Information (OSTI)

    the Middle East (Conference) | SciTech Connect Conference: Nuclear Nonproliferation, International Safeguards and Nuclear Security in the Middle East Citation Details In-Document Search Title: Nuclear Nonproliferation, International Safeguards and Nuclear Security in the Middle East Authors: Boyer, Brian D [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2012-11-20 OSTI Identifier: 1055251 Report Number(s): LA-UR-12-26430 DOE Contract Number: AC52-06NA25396

  1. Practical issues associated with implementing an advanced safeguards

    Office of Scientific and Technical Information (OSTI)

    approach at gas centrifuge enrichment facilities (Conference) | SciTech Connect Practical issues associated with implementing an advanced safeguards approach at gas centrifuge enrichment facilities Citation Details In-Document Search Title: Practical issues associated with implementing an advanced safeguards approach at gas centrifuge enrichment facilities Authors: Erpenbeck, Heather H [1] ; Boyer, Brian D [1] ; Fane, Brian M [1] ; Ianakiev, Kiril D [1] ; Miller, Karen A [1] ; Ward, Steven L

  2. Practical issues associated with implementing an advanced safeguards

    Office of Scientific and Technical Information (OSTI)

    approach at gas centrifuge enrichment facilities (Conference) | SciTech Connect Practical issues associated with implementing an advanced safeguards approach at gas centrifuge enrichment facilities Citation Details In-Document Search Title: Practical issues associated with implementing an advanced safeguards approach at gas centrifuge enrichment facilities Authors: Erpenbeck, Heather H [1] ; Boyer, Brian D [1] ; Fane, Brian M [1] ; Ianakiev, Kiril D [1] ; Miller, Karen A [1] ; Ward, Steven L

  3. Practical issues associated with implementing an advanced safeguards

    Office of Scientific and Technical Information (OSTI)

    approach at gas centrifuge enrichment facilities (Conference) | SciTech Connect Practical issues associated with implementing an advanced safeguards approach at gas centrifuge enrichment facilities Citation Details In-Document Search Title: Practical issues associated with implementing an advanced safeguards approach at gas centrifuge enrichment facilities Ă— You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of

  4. Practical issues associated with implementing an advanced safeguards

    Office of Scientific and Technical Information (OSTI)

    approach at gas centrifuge enrichment facilities (Conference) | SciTech Connect Practical issues associated with implementing an advanced safeguards approach at gas centrifuge enrichment facilities Citation Details In-Document Search Title: Practical issues associated with implementing an advanced safeguards approach at gas centrifuge enrichment facilities Ă— You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of

  5. Safeguards and Security Program - DOE Directives, Delegations, and

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

    Requirements ARCHIVED DOE O 470.1 Chg 1, Safeguards and Security Program by Website Administrator Functional areas: Environment, Safety, and Health, Hazardous Materials, Radiation Protection, Safeguards, Security, and Emergency Management, Work Processes, Ensures appropriate levels of protection against unauthorized access; theft, diversion, loss of custody, or destruction of nuclear weapons, or weapons components; espionage; loss or theft of classified matter or Government property; and

  6. FAQS Job Task Analyses - Safeguards and Security | Department of Energy

    Energy Savers [EERE]

    Security FAQS Job Task Analyses - Safeguards and Security FAQS Job Task Analyses are performed on the Function Area Qualification Standards. The FAQS Job Task Analyses consists of: Developing a comprehensive list of tasks that define the job such as the duties and responsibilities which include determining their levels of importance and frequency. Identifying and evaluating competencies. Last step is evaluating linkage between job tasks and competencies. PDF icon FAQS JTA - Safeguards and

  7. NNSA Commissions New Safeguards Tool at Chornobyl Site | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Commissions New Safeguards Tool at Chornobyl Site June 21, 2010 WASHINGTON - The National Nuclear Security Administration (NNSA) today announced the successful commissioning of a new tool to help Ukraine fulfill nuclear safeguards obligations still complicated by the 1986 explosion at the Chornobyl Nuclear Power Plant (CNPP). Following the accident at Chornobyl twenty-four years ago, a temporary sarcophagus was built around the damaged reactor to mitigate the

  8. EM Headquarters Office Ensures Safeguards, Security, Emergency Preparedness

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

    | Department of Energy Headquarters Office Ensures Safeguards, Security, Emergency Preparedness EM Headquarters Office Ensures Safeguards, Security, Emergency Preparedness January 14, 2016 - 12:35pm Addthis A Centerra Protective Force employee uses a mirror to check the undercarriage of a transport trailer before it enters a Savannah River Site Limited Area. A Centerra Protective Force employee uses a mirror to check the undercarriage of a transport trailer before it enters a Savannah River

  9. Computer safeguards system for the IAEA inspectors at GCEP

    SciTech Connect (OSTI)

    Baker, A.L.; Harris, P.W.; Fienning, W.C.

    1983-01-01

    The Safeguards Data System (SDS), which is being developed to provide improved safeguards for the Gas Centrifuge Enrichment Plant at Portsmouth, Ohio, is described. The SDS is an automated, integrated computer data acquisition and data management system. It is designed to operate in a continuous unattended mode to provide attributes measurements, summary materials accounting data, and on-site data analysis capability to the IAEA inspectors at the GCEP facility.

  10. Global change and the value of biodiversity for new product research. Final project report, September 1, 1995--August 31, 1996

    SciTech Connect (OSTI)

    Simpson, R.D.; Sedjo, R.A.

    1997-06-01

    A number of biologists believe that human activities are causing species extinctions at alarming rates. The only precedents, they claim, are to be found in the mass extinctions associated with a handful of apocalyptic volcanic eruptions and/or meteorite strikes distributed over geological time scales. Slowing the rates of greenhouse gas emissions, natural habitat destruction, and other factors that are believed to be inducing modem extinctions could be very expensive, however. It is natural to ask, then, what is the value of preserving biodiversity. One (although admittedly, among many) argument frequently made is that biodiversity is a source of new industrial, agricultural, and, particularly, pharmaceutical products. Natural organisms, it is argued, are great repositories of genetic information. Wild species, in their struggle to capture prey, escape predators, resist infection, and enhance reproductive success have evolved chemical mechanisms more elaborate and inventive than those synthetic chemists can now create. If these chemical mechanisms could be adapted and refined for human use, they could be of great value. There has, therefore, been considerable interest among natural scientists and conservation advocates in {open_quotes}biodiversity prospecting{close_quotes} the search for new commercial products among naturally occurring organisms-as both a mechanism and an argument for preserving biodiversity. In recent years economists and others have attempted to estimate the value of biodiversity for use in new product development. These studies vary considerably in their data, methods, and estimates. The Simpson, Sedjo and Reid and Polasky and Solow papers differ from previous work in that they focus on what is arguably the economically relevant issue: what is the value of biodiversity on the margin.

  11. NDA safeguards techniques for LMFBR assemblies

    SciTech Connect (OSTI)

    Persiani, P.J.; Gundy, M.L.

    1982-08-01

    The significant safeguards concerns for liquid-metal fast breeder reactors (LMFBRs), and for the LMFBR fuel handling systems are the accountability, surveillance, and identification of fuel and blanket assemblies. The introduction of fuel assemblies with a high content of Pu into the receiving and shipping areas of the LMFBR fuel cycle does allow a more direct near-real-time assay profile of the disposition of Pu. Isotope correlations and neutron assay methods have been investigated and implemented for determining plutonium and burnup in fresh and spent LMFBR fuel assemblies. The methods are based on active and passive neutron coincidence counting (NCC) techniques. Preliminary studies on neutron yield rates from the spontaneous fission of plutonium and curium isotopes have indicated that the NCC system is a most effective measure in the verification of nuclear material flow in assembly form for the entire reactor fuel handling cycle, i.e., from the fresh- to the spent-fuel stage. A consequence of the high plutonium concentration level throughout the fuel irradiation period in an LMFBR, is that the spontaneous fission neutron yield from the 242-curium and 244-curium does not dominate the spontaneous fission neutron yield from the plutonium isotopes in the spent fuel stage.

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

    SciTech Connect (OSTI)

    Rosenthal, M.D.; Fishbone, L.G.; Gallini, L.; Krass, A.; Kratzer, M.; Sanborn, J.; Ward, B.; Wulf, N. A.

    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 of 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.

  13. Lessons Learned in International Safeguards - Implementation of Safeguards at the Rokkasho Reprocessing Plant

    SciTech Connect (OSTI)

    Ehinger, Michael H; Johnson, Shirley

    2010-02-01

    The focus of this report is lessons learned at the Rokkasho Reprocessing Plant (RRP). However, the subject of lessons learned for application of international safeguards at reprocessing plants includes a cumulative history of inspections starting at the West Valley (New York, U.S.A.) reprocessing plant in 1969 and proceeding through all of the efforts over the years. The RRP is the latest and most challenging application the International Atomic Energy Agency has faced. In many ways the challenges have remained the same, timely inspection and evaluation with limited inspector resources, with the continuing realization that planning and preparations can never start early enough in the life cycle of a facility. Lessons learned over the years have involved the challenges of using ongoing advances in technology and dealing with facilities with increased throughput and continuous operation. This report will begin with a review of historical developments and lessons learned. This will provide a basis for a discussion of the experiences and lessons learned from the implementation of international safeguards at RRP.

  14. LABORATORY DEMONSTRATION OF A MULTISENSOR UNATTENDED CYLINDER VERIFICATION STATION FOR URANIUM ENRICHMENT PLANT SAFEGUARDS

    SciTech Connect (OSTI)

    Goodman, David I; Rowland, Kelly L; Smith, Sheriden; Miller, Karen A.; Flynn, Eric B.

    2014-01-10

    The objective of safeguards is the timely detection of the diversion of a significant quantity of nuclear materials, and safeguarding uranium enrichment plants is especially important in preventing the spread of nuclear weapons. The IAEA’s proposed Unattended Cylinder Verification Station (UCVS) for UF6 cylinder verification would combine the operator’s accountancy scale with a nondestructive assay system such as the Passive Neutron Enrichment Meter (PNEM) and cylinder identification and surveillance systems. In this project, we built a laboratory-scale UCVS and demonstrated its capabilities using mock UF6 cylinders. We developed a signal processing algorithm to automate the data collection and processing from four continuous, unattended sensors. The laboratory demonstration of the system showed that the software could successfully identify cylinders, snip sensor data at the appropriate points in time, determine the relevant characteristics of the cylinder contents, check for consistency among sensors, and output the cylinder data to a file. This paper describes the equipment, algorithm and software development, laboratory demonstration, and recommendations for a full-scale UCVS.

  15. Zone approaches to international safeguards of a nuclear fuel cycle

    SciTech Connect (OSTI)

    Fishbone, L.G.; Higinbotham, W.A.

    1986-01-01

    At present the IAEA designs its safeguards approach with regard to each type of nuclear facility so that the safeguards activities and effort are essentially the same for a given type and size of nuclear facility wherever it may be located. Conclusions regarding a state are derived by combining the results of safeguards verifications for the individual facilities within it. We have examined safeguards approaches for a state nuclear fuel cycle that take into account the existence of all of the nuclear facilities in the state. We have focussed on the fresh-fuel zone of an advanced nuclear fuel cycle, the several facilities of which use or process low-enriched uranium. At one extreme, flows and inventories would be verified at each material balance area. At the other extreme, the flows into and out of the zone and the inventory of the whole zone would be verified. The intention is to develop an approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the zone approach and for some reasonable intermediate safeguards approaches. Technical effectiveness, in these cases, means an estimate of the assurance that all nuclear material has been accounted for.

  16. Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities

    SciTech Connect (OSTI)

    Durst, Philip C.; Ehinger, Michael H.; Boyer, Brian; Therios, Ike; Bean, Robert; Dougan, A.; Tolk, K.

    2007-12-15

    This second report in a series of three reviews possible safeguards approaches for the new transuranic (TRU) fuel fabrication processes to be deployed at AFCF – specifically, the ceramic TRU (MOX) fuel fabrication line and the metallic (pyroprocessing) line. The most common TRU fuel has been fuel composed of mixed plutonium and uranium dioxide, referred to as “MOX”. However, under the Advanced Fuel Cycle projects custom-made fuels with higher contents of neptunium, americium, and curium may also be produced to evaluate if these “minor actinides” can be effectively burned and transmuted through irradiation in the ABR. A third and final report in this series will evaluate and review the advanced safeguards approach options for the ABR. In reviewing and developing the advanced safeguards approach for the new TRU fuel fabrication processes envisioned for AFCF, the existing international (IAEA) safeguards approach at the Plutonium Fuel Production Facility (PFPF) and the conceptual approach planned for the new J-MOX facility in Japan have been considered as a starting point of reference. The pyro-metallurgical reprocessing and fuel fabrication process at EBR-II near Idaho Falls also provided insight for safeguarding the additional metallic pyroprocessing fuel fabrication line planned for AFCF.

  17. ELECTROCHEMICALLY-MODULATED SEPARATIONS FOR SAFEGUARDS MEASUREMENTS

    SciTech Connect (OSTI)

    Green, Michael A.; Arrigo, Leah M.; Liezers, Martin; Orton, Christopher R.; Douglas, Matthew; Peper, Shane M.; Schwantes, Jon M.; Hazelton, Sandra G.; Duckworth, Douglas C.

    2010-08-11

    A critical objective of materials accountability in safeguards is the accurate and timely analysis of fuel reprocessing streams to detect both abrupt and prolonged diversions of nuclear materials. For this reason both on-line nondestructive (NDA) and destructive analysis (DA) approaches are sought-after. Current methods for DA involve grab sampling and laboratory based column extractions that are costly, hazardous, and time consuming. While direct on-line gamma measurements of Pu are desirable, they are not possible due to contributions from other actinides and fission products. Researchers at Pacific Northwest National Laboratory are currently investigating electrochemically-modulated separation (EMS) as a straightforward, cost-effective technology for selective separation of Pu or U from aqueous reprocessing streams. The EMS selectivity is electrochemically controlled and results from the sorption of Pu4+ and U4+ redox states onto the anodized target electrode, allowing for selective accumulation of U or Pu from nitric acid streams to be turned “on” or “off.” It is envisioned that this technology can be utilized to isolate Pu for both NDA and DA analysis. For the NDA approach, rapid Pu analysis by gamma-ray spectroscopy could be performed after chemical clean-up of activation and fission products by EMS. Likewise, in the DA approach, EMS could be used to retain and concentrate the Pu in nanogram quantities on the electrode surface to be transported to the lab for analysis using high precision mass spectrometry. Due to the challenges associated with complex matrices, a systematic investigation of the redox-dependent accumulation of Pu using EMS was necessary, and results will be presented. Approaches to mitigate interelement effects using large surface area cells will also be discussed. The EMS chemistry and spectroscopy for Pu isolation and measurement will be presented, proof-of-principle measurements will be described, and the application of this approach for materials accountability will be discussed.

  18. The International Safeguards Technology Base: How is the Patient Doing? An Exploration of Effective Metrics

    SciTech Connect (OSTI)

    Schanfein, Mark; Gouveia, Fernando; Crawford, Cary E.; Pickett, Chris J.; Jay, Jeffrey

    2010-07-15

    The term “Technology Base” is commonly used but what does it mean? Is there a common understanding of the components that comprise a technology base? Does a formal process exist to assess the health of a given technology base? These are important questions the relevance of which is even more pressing given the USDOE/NNSA initiatives to strengthen the safeguards technology base through investments in research & development and human capital development. Accordingly, the authors will establish a high-level framework to define and understand what comprises a technology base. Potential goal-driven metrics to assess the health of a technology base will also be explored, such as linear demographics and resource availability, in the hope that they can be used to better understand and improve the health of the U.S. safeguards technology base. Finally, through the identification of such metrics, the authors will offer suggestions and highlight choices for addressing potential shortfalls. Introduction The U.S. safeguards technology base got its start almost half a century ago in the nuclear weapons program of the U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA) and their predecessors: AEC & ERDA. Due to nuclear materials’ strategic importance and value, and the risk associated with the public’s and worker’s health and the potential for theft, significant investments were made to develop techniques to measure nuclear materials using both destructive assay (DA) and non-destructive assay (NDA). Major investment within the U.S. DOE Domestic Safeguards Program continued over the next three decades, resulting in continuous improvements in the state-of-the-art of these techniques. This was particularly true in the area of NDA with its ability to use gamma rays, neutrons, and heat to identify and quantify nuclear materials without the need to take direct samples of the material. Most of these techniques were commercialized and transferred to industry, opening their applications to the nuclear industry worldwide and to the International Atomic Energy Agency (IAEA).

  19. "Order Module--DOE O 470.4B, SAFEGUARDS AND SECURITY PROGRAM...

    Office of Environmental Management (EM)

    "Order Module--DOE O 470.4B, SAFEGUARDS AND SECURITY PROGRAM, DOE O 471.6, INFORMATION SECURITY, DOE O 473.3 "Order Module--DOE O 470.4B, SAFEGUARDS AND SECURITY PROGRAM, DOE O...

  20. Safeguards and security research and development progress report, October 1993--September 1994

    SciTech Connect (OSTI)

    Smith, D.B.; Jaramillo, G.R.

    1995-08-01

    This report describes the activities carried out by the Los Alamos Safeguards and Security Research and Development (R&D) program from October 1993 through September 1994. The activities presented in the first part of the report were directed primarily to domestic US safeguards applications and were, for the most part, sponsored by the Department of Energy`s Office of Safeguards and Security (DOE/OSS, NN-50). The activities described in Part 2, International Safeguards, were supported by the International Safeguards Division of the Office of Arms Control and Nonproliferation (DOE/OACN, NN-40). Part 3 describes several safeguards or safeguards-related activities that have other sponsors. The final part of the report lists titles and abstracts of Los Alamos safeguards R&D reports, technical journal articles, and conference papers that were published or presented in 1994.

  1. Boron-10 Based Neutron Coincidence Counter for Safeguards

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Ely, James H.; Lintereur, Azaree T.; Siciliano, Edward R.

    2014-10-01

    The shortage of 3He has triggered the search for effective alternative neutron detection technologies for national security applications, including international nuclear safeguards. Any alternative neutron detection technology must satisfy two basic criteria: it must meet a neutron detection efficiency requirement, and it must be insensitive to gamma-ray interference at a prescribed level while still meeting the neutron detection requirement. For nuclear safeguards, a system must perform measurements in the field with a prescribed precision in a specified time. This paper describes an effort to design, model and test an alternatives-based neutron coincidence counter for nuclear safeguards applications. The technology chosen for use in an alternatives-based uranium neutron coincidence collar was boron-lined proportional counters. Extensive modeling was performed of various system configurations and comparisons were made to measurements on a commercial prototype boron-10 based uranium neutron coincidence collar.

  2. End user needs for enhanced IAEA Safeguards Information Management Capabilities

    SciTech Connect (OSTI)

    Badalamente, R.; Anzelon, G.; Deland, S.; Whiteson, R.

    1994-07-01

    The International Atomic Energy Agency is undertaking a program for strengthening its safeguards on the recognition that safeguards must give assurance not only of the non-diversion of declared material or that declared facilities are not being misused, but also of the absence of any undeclared nuclear activities in States which have signed comprehensive safeguards agreements with the Agency. The IAEA has determined that the detection of undeclared nuclear activities and the creation of confidence in the continuing peaceful use of declared material and facilities is largely dependent on more information being made available to the Agency and on the capability of the Agency to make more effective use of this additional information, as well as existing information.

  3. Integrated safeguards & security for material protection, accounting, and control.

    SciTech Connect (OSTI)

    Duran, Felicia Angelica; Cipiti, Benjamin B.

    2009-10-01

    Traditional safeguards and security design for fuel cycle facilities is done separately and after the facility design is near completion. This can result in higher costs due to retrofits and redundant use of data. Future facilities will incorporate safeguards and security early in the design process and integrate the systems to make better use of plant data and strengthen both systems. The purpose of this project was to evaluate the integration of materials control and accounting (MC&A) measurements with physical security design for a nuclear reprocessing plant. Locations throughout the plant where data overlap occurs or where MC&A data could be a benefit were identified. This mapping is presented along with the methodology for including the additional data in existing probabilistic assessments to evaluate safeguards and security systems designs.

  4. Safeguards Approaches for Black Box Processes or Facilities

    SciTech Connect (OSTI)

    Diaz-Marcano, Helly; Gitau, Ernest TN; Hockert, John; Miller, Erin; Wylie, Joann

    2013-09-25

    The objective of this study is to determine whether a safeguards approach can be developed for “black box” processes or facilities. These are facilities where a State or operator may limit IAEA access to specific processes or portions of a facility; in other cases, the IAEA may be prohibited access to the entire facility. The determination of whether a black box process or facility is safeguardable is dependent upon the details of the process type, design, and layout; the specific limitations on inspector access; and the restrictions placed upon the design information that can be provided to the IAEA. This analysis identified the necessary conditions for safeguardability of black box processes and facilities.

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

    SciTech Connect (OSTI)

    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 first 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.

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

    SciTech Connect (OSTI)

    Henry, C.N.

    1981-11-01

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

  7. U.S. and Tunisia to Cooperate on Nuclear Safeguards, Nonproliferation...

    National Nuclear Security Administration (NNSA)

    Tunisia to Cooperate on Nuclear Safeguards, Nonproliferation and Peaceful Nuclear Energy Infrastructure | National Nuclear Security Administration Facebook Twitter Youtube Flickr...

  8. An Inspector's Assessment of the New Model Safeguards Approach for Enrichment Plants

    SciTech Connect (OSTI)

    Curtis, Michael M.

    2007-07-31

    This conference paper assesses the changes that are being made to the Model Safeguards Approach for Gas Centrifuge Enrichment Plants.

  9. Application of the sources code in nuclear safeguards

    SciTech Connect (OSTI)

    Beddingfield, D. H.

    2002-01-01

    The Sources Code System provides a greatly expanded calculational capacity in the field of nuclear safeguards. It is becoming more common that we are called upon to perform assays on materials for which no standards exist. These materials tend to be mixtures of nuclear materials and low-Z compounds (spent fuels in a variety of matrices, in-process compounds such as UF6, MOX with varying water content). We will present soma applications of the Sources Code and discuss the application calculated (a,n) source terms in neutron coincidence counting for nuclear safeguards.

  10. Continuous remote unattended monitoring for safeguards data collection systems

    SciTech Connect (OSTI)

    Klosterbuer, S.F.; Halbig, J.K.; Harker, W.C.; Menlove, H.O.; Painter, J.A.; Stewart, J.E.

    1994-02-01

    To meet increased inspection requirements, unattended and remote monitoring systems have been developed and installed in several large facilities to perform safeguards functions. These unattended monitoring systems are based on instruments originally developed for traditional safeguards and the domestic nuclear industry to nondestructively assay nuclear materials. Through specialized measurement procedures, these instruments have been adapted to be unattended monitors. This paper defines the parts of these unattended monitoring systems, describes the systems that have been installed in the field and their status, and discusses future trends for unattended systems.

  11. The IAEA and the International Safeguards System (Technical Report) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect The IAEA and the International Safeguards System Citation Details In-Document Search Title: The IAEA and the International Safeguards System Authors: Boyer, Brian D. [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2013-05-08 OSTI Identifier: 1079563 Report Number(s): LA-UR-13-23355 DOE Contract Number: AC52-06NA25396 Resource Type: Technical Report Research Org: Los Alamos National Laboratory (LANL) Sponsoring Org: DOE/LANL Country of

  12. Biodiversity Research Institute Mid-Atlantic Baseline Study Webinar

    Broader source: Energy.gov [DOE]

    Carried out by the Biodiversity Research Institute (BRI) and funded by the U.S. Department of Energy Wind and Water Power Technology Office and other partners, the goal of the Mid-Atlantic Baseline...

  13. The Little Biodiversity Finance Book | Open Energy Information

    Open Energy Info (EERE)

    global biodiversity and ecosystem services. To address these gaps we aim to build on the work of this study and encourage you to send us your feedback so that we can continue to...

  14. The Exiguobacterium genus: biodiversity and biogeography (Journal Article)

    Office of Scientific and Technical Information (OSTI)

    | SciTech Connect The Exiguobacterium genus: biodiversity and biogeography Citation Details In-Document Search Title: The Exiguobacterium genus: biodiversity and biogeography Abstract. Bacteria of the genus Exiguobacterium are low G + C, Gram-positive facultative anaerobes that have been repeatedly isolated from ancient Siberian permafrost. In addition, Exiguobacterium spp. have been isolated from markedly diverse sources, including Greenland Glacial ice, hot springs at Yellowstone National

  15. INSTITUTIONALIZING SAFEGUARDS-BY-DESIGN: HIGH-LEVEL FRAMEWORK

    SciTech Connect (OSTI)

    Trond Bjornard PhD; Joseph Alexander; Robert Bean; Brian Castle; Scott DeMuth, Ph.D.; Phillip Durst; Michael Ehinger; Prof. Michael Golay, Ph.D.; Kevin Hase, Ph.D.; David J. Hebditch, DPhil; John Hockert, Ph.D.; Bruce Meppen; James Morgan; Jerry Phillips, Ph.D., PE

    2009-02-01

    The application of a Safeguards-by-Design (SBD) process for new nuclear facilities can reduce proliferation risks. A multi-laboratory team was sponsored in Fiscal Year (FY) 2008 to define a SBD process and determine how it could be incorporated into existing facility design and construction processes. The possibility to significantly influence major design features, such as process selection and plant layout, largely ends with the conceptual design step. Therefore SBD’s principal focus must be on the early inclusion of safeguards requirements and the early identification of beneficial design features. The result could help form the basis for a new international norm for integrating safeguards into facility design. This is an interim report describing progress and project status as of the end of FY08. In this effort, SBD is defined as a structured approach to ensure the timely, efficient, and cost-effective integration of international and national safeguards, physical security, and other nonproliferation objectives into the overall design process for a nuclear facility. A key objective is to ensure that security and nonproliferation issues are considered when weighing facility design alternatives. Central to the work completed in FY08 was a study in which a SBD process was developed in the context of the current DOE facility acquisition process. The DOE study enabled the development of a “SBD design loop” that is suitable for use in any facility design process. It is a graded, iterative process that incorporates safeguards concerns throughout the conceptual, preliminary and final design processes. Additionally, a set of proposed design principles for SBD was developed. A “Generic SBD Process” was then developed. Key features of the process include the initiation of safeguards design activities in the pre-conceptual planning phase, early incorporation of safeguards requirements into the project requirements, early appointment of an SBD team, and participation in facility design options analysis in the conceptual design phase to enhance intrinsic features, among others. The SBD process is unlikely to be broadly applied in the absence of formal requirements to do so, or compelling evidence of its value. Neither exists today. A formal instrument to require the application of SBD is needed and would vary according to both the national and regulatory environment. Several possible approaches to implementation of the requirements within the DOE framework are explored in this report. Finally, there are numerous barriers to the implementation of SBD, including the lack of a strong safeguards culture, intellectual property concerns, the sensitive nature of safeguards information, and the potentially divergent or conflicting interests of participants in the process. In terms of SBD implementation in the United States, there are no commercial nuclear facilities that are under IAEA safeguards. Efforts to institutionalize SBD must address these issues. Specific work in FY09 could focus on the following: finalizing the proposed SBD process for use by DOE and performing a pilot application on a DOE project in the planning phase; developing regulatory options for mandating SBD; further development of safeguards-related design guidance, principles and requirements; development of a specific SBD process tailored to the NRC environment; and development of an engagement strategy for the IAEA and other international partners.

  16. Next Generation Safeguards Initiative: Analysis of Probability of Detection of Plausible Diversion Scenarios at Gas Centrifuge Enrichment Plants Using Advanced Safeguards

    SciTech Connect (OSTI)

    Hase, Kevin R.; Hawkins Erpenbeck, Heather; Boyer, Brian D.

    2012-07-10

    Over the last decade, efforts by the safeguards community, including inspectorates, governments, operators and owners of centrifuge facilities, have given rise to new possibilities for safeguards approaches in enrichment plants. Many of these efforts have involved development of new instrumentation to measure uranium mass and uranium-235 enrichment and inspection schemes using unannounced and random site inspections. We have chosen select diversion scenarios and put together a reasonable system of safeguards equipment and safeguards approaches and analyzed the effectiveness and efficiency of the proposed safeguards approach by predicting the probability of detection of diversion in the chosen safeguards approaches. We analyzed the effect of redundancy in instrumentation, cross verification of operator instrumentation by inspector instrumentation, and the effects of failures or anomalous readings on verification data. Armed with these esults we were able to quantify the technical cost benefit of the addition of certain instrument suites and show the promise of these new systems.

  17. Project Report on Development of a Safeguards Approach for Pyroprocessing

    SciTech Connect (OSTI)

    Robert Bean

    2010-09-01

    The Idaho National Laboratory has undertaken an effort to develop a standard safeguards approach for international commercial pyroprocessing facilities. This report details progress for the fiscal year 2010 effort. A component by component diversion pathway analysis has been performed, and has led to insight on the mitigation needs and equipment development needed for a valid safeguards approach. The effort to develop an in-hot cell detection capability led to the digital cloud chamber, and more importantly, the significant potential scientific breakthrough of the inverse spectroscopy algorithm, including the ability to identify energy and spatial location of gamma ray emitting sources with a single, non-complex, stationary radiation detector system. Curium measurements were performed on historical and current samples at the FCF to attempt to determine the utility of using gross neutron counting for accountancy measurements. A solid cost estimate of equipment installation at FCF has been developed to guide proposals and cost allocations to use FCF as a test bed for safeguards measurement demonstrations. A combined MATLAB and MCNPX model has been developed to perform detector placement calculations around the electrorefiner. Early harvesting has occurred wherein the project team has been requested to provide pyroprocessing technology and safeguards short courses.

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

    SciTech Connect (OSTI)

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

    1994-04-01

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

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

    SciTech Connect (OSTI)

    Keisch, B.; Auerbach, C.; Fainberg, A.; Fiarman, S.; Fishbone, L.G.; Higinbotham, W.A.; Lemley, J.R.; O'Brien, J.

    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 which 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.

  20. Nuclear Materials Management and Safeguards System Reporting and Data Submission

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

    1998-02-10

    The manual provides clear and detailed instructions and procedures for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE 5633.3B. Canceled by DOE M 474.1-2A.

  1. Safeguards Agreement and Protocol with the International Atomic Energy Agency

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

    2004-01-07

    To ensure that DOE complies with the Agreement Between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States, the Protocol to the Agreement, and the subsidiary arrangements to the Agreement. Canceled by DOE O 142.2A. Cancels DOE 1270.2B.

  2. The U.S. Support Program to IAEA Safeguards - How It Works

    SciTech Connect (OSTI)

    Nock,C.; Hoffheins,B.

    2008-07-13

    The U.S. Support Program to International Atomic Energy Agency (IAEA) Safeguards (USSP) was established in 1977 to transfer US technology and expertise to assist the IAEA Department of Safeguards because its limited budget and scope would not allow for R&D activities and the procurement of specialized or customized equipment. Over the years, the USSP and the Department of Safeguards have worked together continuously to develop and improve processes for requesting, selecting, and managing projects that support the Safeguards verification mission. This paper will discuss the main USSP processes for accepting and processing Safeguards requests, and managing and reporting task progress.

  3. Safeguards instrumentation: a computer-based catalog. Second edition

    SciTech Connect (OSTI)

    Auerbach, C.

    1985-04-01

    This catalog contains entries on new developments and on items listed in BNL 51450, which have either been carried over unchanged or been updated. More than 70 entries were deleted because of either obsolescence, insufficient interest in terms of safeguards, or lack of documentable development activities in recent years. Some old listings as well as new material was consolidated into more generic entries. As in the earlier document, the emphasis is on devices and instruments that are either in field use at this time or under active development. A few items such as NDA reference materials, instrument vans and certain shipping containers are included because they are important adjuncts to optimum utilization of safeguards instrumentation. This catalog does not include devices for physical protection. As was the case with its predecessor, most of the material in this catalog originated in the US and Canada; a few contributions came from member states of the European Community.

  4. CLASSIFICATION OF THE MGR SAFEGUARDS AND SECURITY SYSTEM

    SciTech Connect (OSTI)

    J.A. Ziegler

    1999-08-31

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) safeguards and security system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

  5. UNCLASSIFIED UNCLASSIFIED Nuclear Materials Management & Safeguards System

    National Nuclear Security Administration (NNSA)

    UNCLASSIFIED Nuclear Materials Management & Safeguards System CONTACT INFORMATION UPDATE REPORTING IDENTIFICATION SYMBOL (RIS) RIS: Address: Facility Name: CONTACTS Name Email: Phone/Fax Name Email: Phone/Fax Name Email: Phone/Fax Name Email: Phone/Fax Return Via Mail To: U.S Department Of Energy ATTN: NMMSS Staff NA-73, GTN 1000 Independence Avenue, SW Washington, DC 20585-1290 Return Via Fax To: 301-903-1998 Return Via E-Mail To: NMMSS@nnsa.doe.gov

  6. Nuclear Materials Safeguards and Security Upgrade Project | National

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

    Nuclear Security Administration Nuclear Materials Safeguards and Security Upgrade Project NNSA Announces 2014 Security Professional of the Year Awards WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA) today announced the recipients of the 2014 Bradley A. Peterson Federal and Contractor Security Professional of the Year Awards. Pamela Valdez from the Los Alamos Field Office will receive the federal award and Randy Fraser from

  7. Safeguards and Security General Technical Base Qualification Standard

    Energy Savers [EERE]

    23-2009 July 2009 DOE STANDARD SAFEGUARDS AND SECURITY GENERAL TECHNICAL BASE QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1123-2009 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1123-2009 iii APPROVAL The

  8. Protection and Control of Safeguards and Security Interests

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

    1994-07-15

    To establish policy, responsibilities, and authorities for the protection and control of safeguards and security interests. Cancels DOE O 5632.1B, DOE O 5632.2A, DOE O 5632.5, DOE O 5632.6, DOE O 5632.9A, DOE O 5632.11, DOE O 5635.1A, DOE O 5635.2B, DOE O 5635.3. Canceled by DOE O 473.1

  9. Current Status of Helium-3 Alternative Technologies for Nuclear Safeguards

    SciTech Connect (OSTI)

    Henzlova, Daniela; Kouzes, R.; McElroy, R.; Peerani, P.; Aspinall, M.; Baird, K.; Bakel, A.; Borella, M.; Bourne, M.; Bourva, L.; Cave, F.; Chandra, R.; Chernikova, D.; Croft, S.; Dermody, G.; Dougan, A.; Ely, J.; Fanchini, E.; Finocchiaro, P.; Gavron, Victor; Kureta, M.; Ianakiev, Kiril Dimitrov; Ishiyama, K.; Lee, T.; Martin, Ch.; McKinny, K.; Menlove, Howard Olsen; Orton, Ch.; Pappalardo, A.; Pedersen, B.; Peranteau, D.; Plenteda, R.; Pozzi, S.; Schear, M.; Seya, M.; Siciliano, E.; Stave, S.; Sun, L.; Swinhoe, Martyn Thomas; Tagziria, H.; Vaccaro, S.; Takamine, J.; Weber, A. -L.; Yamaguchi, T.; Zhu, H.

    2015-12-01

    International safeguards inspectorates (e.g., International Atomic Energy Agency {IAEA}, or Euratom) rely heavily on neutron assay techniques, and in particular, on coincidence counters for the verification of declared nuclear materials under safeguards and for monitoring purposes. While 3He was readily available, the reliability, safety, ease of use, gamma-ray insensitivity, and high intrinsic thermal neutron detection efficiency of 3He-based detectors obviated the need for alternative detector technologies. However, the recent decline of the 3He gas supply has triggered international efforts to develop and field neutron detectors that make use of alternative materials. In response to this global effort, the U.S. Department of Energy’s (DOE) National Nuclear Security Administration (NNSA) and Euratom launched a joint effort aimed at bringing together international experts, technology users and developers in the field of nuclear safeguards to discuss and evaluate the proposed 3He alternative materials and technologies. The effort involved a series of two workshops focused on detailed overviews and viability assessments of various 3He alternative technologies for use in nuclear safeguards applications. The key objective was to provide a platform for collaborative discussions and technical presentations organized in a compact, workshop-like format to stimulate interactions among the participants. The meetings culminated in a benchmark exercise providing a unique opportunity for the first inter-comparison of several available alternative technologies. This report provides an overview of the alternative technology efforts presented during the two workshops along with a summary of the benchmarking activities and results. The workshop recommendations and key consensus observations are discussed in the report, and used to outline a proposed path forward and future needs foreseeable in the area of 3He-alternative technologies.

  10. Developing the digital safeguard that protects the National Spherical Torus

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

    Experiment-Upgrade at PPPL | Princeton Plasma Physics Lab Developing the digital safeguard that protects the National Spherical Torus Experiment-Upgrade at PPPL By John Greenwald February 22, 2016 Tweet Widget Google Plus One Share on Facebook Members of the team that developed the DCPS, from left: Gretchen Zimmer, Kevin Lamb, Greg Tchillingarian, Paul Sichta, John Lawson, Tim Stevenson, Stefan Gerhardt and Roman Rozenblat. Not shown: Vince Mastrocola, John Dong, Gary Gibilisco. (Photo by

  11. Safeguards Guidance for Independent Spent Fuel Storage Installations (ISFSI)

    National Nuclear Security Administration (NNSA)

    1) May 2012 Guidance for Independent Spent Fuel Dry Storage Installations Safeguards-by-Design: Guidance for Independent Spent Fuel Dry Storage Installations (ISFSI) Philip Casey Durst (INL Consultant) DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy,

  12. Framework for fuel-cycle approaches to IAEA safeguards

    SciTech Connect (OSTI)

    Fishbone, L.G.

    1986-10-01

    In order to compare several nuclear-safeguards verification approaches to one another and to the conventional facility-oriented approach, we establish a framework of the classes of information routinely verifiable by IAEA safeguards inspections. For each facility type within a State nuclear fuel cycle, the classes include flow data, inventory data, and shipper and receiver data. By showing which classes of information are verified for each facility type within three fuel cycles of different complexity, we distinguish the inspection approaches from one anoter and exhibit their fuel-cycle dependence, i.e., their need for sets of safeguards inspection activities different from those required under the facility-oriented approach at similar facilities in fuel cycles of differing complexity. Tables V-1, V-2, and V-3 graphically depict these relations and give a qualitative summary of the relative effectiveness and effort requirements of the approaches classified. The zone, information-correlation, diversion-assumption-change, and randomization-over-facilities approaches depend intrinsically on the complexity of the fuel cycle: their very definition implies fuel-cycle dependence. The approaches involving randomization over activities and goal relaxations do not have such dependence.

  13. Feasibility of x ray fluorescence for spent fuel safeguards

    SciTech Connect (OSTI)

    Freeman, Corey Ross; Mozin, Vladimir; Tobin, Stephen J; Fensin, Michael L; White, Julia M; Croft, Stephen; Stafford, Alissa; Charlton, William

    2010-01-01

    Quantifying the Pu content in spent nuclear fuel is necessary for many reasons, in particular to verify that diversion or other illicit activities have not occurred. Therefore, safeguarding the world's nuclear fuel is paramount to responsible nuclear regulation and public acceptance, but achieving this goal presents many difficulties from both a technical and economic perspective. The Next Generation Safeguards Initiative (NGSI) of NA-24 is funding a large collaborative effort between multiple laboratories and universities to improve spent nuclear fuel safeguards methods and equipment. This effort involves the current work of modeling several different nondestructive assay (NDA) techniques. Several are being researched, because no single NDA technique, in isolation, has the potential to properly characterize fuel assemblies and offer a robust safeguards measure. The insights gained from this research, will be used to down-select from the original set a few of the most promising techniques that complement each other. The goal is to integrate the selected instruments to create an accurate measurement system for fuel verification that is also robust enough to detect diversions. These instruments will be fabricated and tested under realistic conditions. This work examines one of the NDA techniques; the feasibility of using x ray emission peaks from Pu and U to gather information about their relative quantities in the spent fuel. X Ray Fluorescence (XRF), is unique compared to the investigated techniques in that it is the only one able to give the elemental ratio of Pu to U, allowing the possibility of a Pu gram quantity for the assembly to be calculated. XRF also presents many challenges, mainly its low penetration, since the low energy x rays of interest are effectively shielded by the first few millimeters of a fuel pin. This paper will explore the results of Monte Carlo N-Particle eXtended (MCNPX) transport code calculations of spent fuel x ray peaks. The MCNPX simulations will be benchmarked against measurements taken at Oak Ridge. Analysis of the feasibility of XRFs role in spent nuclear fuel safeguards efforts, particularly in the context of the overall NGSI effort will be discussed.

  14. Safeguards & Security (S&S) Program | U.S. DOE Office of Science (SC)

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

    Safeguards & Security (S&S) Program Operations Program Management (OPM) OPM Home About Science Laboratories Infrastructure (SLI) Program Safeguards & Security (S&S) Program Sustainability Contact Information Operations Program Management U.S. Department of Energy SC-33/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-8429 F: (301) 903-7047 More Information » Safeguards & Security (S&S) Program Print Text Size: A A A FeedbackShare Page

  15. DOE-STD-1171-2003; Safeguards and Security Functional Area Standard

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

    ... a familiarity level knowledge of contract management and administration sufficient to appraise contractor organizations participating in the safeguards and security programs. ...

  16. A Mock UF6 Feed and Withdrawal System for Testing Safeguards...

    Office of Scientific and Technical Information (OSTI)

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

  17. A Mock UF6 Feed and Withdrawal System for Testing Safeguards...

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Search Results Technical Report: A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment ...

  18. Overview of the US Department of Energy Master Safeguards and Security Agreement program

    SciTech Connect (OSTI)

    Billings, M.P.; Duncan, M.R.; Craig, J.R.

    1988-06-01

    The Master Safeguards and Security Agreement establishes a contract between the US Department of Energy-Headquarters and a US Department of Energy regional Operations Office regarding protection strategies, protection system performance, and acceptability of risks for US Department of Energy Safeguards and Security interests at a facility or site. An approved Master Safeguards and Security Agreement defines the protection system performance baseline for evaluations, inspections, and audits, and can introduce exceptions to US Department of Energy orders. Responsibilities and authorities for development and approval of a Master Safeguards and Security Agreement are outlined in US Department of Energy Order 5630.13, ''Master Safeguards and Security Agreement'' and US Department of Energy Order 5630.xx, ''Safeguards and Security Planning Program'' (draft). To date, 14 Master Safeguards and Security Agreements have been approved by the US Department of Energy-Headquarters and about 34 are in preparation or review. A total of approximately 50 are anticipated before completion of the program. The Master Safeguards and Security agreement program has been positively received by both the US Department of Energy-Headquarters and the US Department of Energy Operations Offices, because it provides visibility as to the effectiveness of Safeguards and Security protection systems and affords a sensible foundation for security planning based on risk. 6 refs., 3 figs., 6 tabs.

  19. Safeguards and Security Glossary - DOE M 470.4-7 | Department...

    Office of Environmental Management (EM)

    in most dictionaries have been intentionally omitted from the Glossary. Although a Manual including the Safeguards and Security Glossary would be considered a requirements...

  20. Defining the needs for gas centrifuge enrichment plants advanced safeguards

    SciTech Connect (OSTI)

    Boyer, Brian David; Erpenbeck, Heather H; Miller, Karen A; Swinhoe, Martyn T; Ianakiev, Kiril; Marlow, Johnna B

    2010-04-05

    Current safeguards approaches used by the International Atomic Energy Agency (IAEA) at gas centrifuge enrichment plants (GCEPs) need enhancement in order to verify declared low-enriched (LEU) production, detect undeclared LEU production and detect highly enriched uranium (HEU) production with adequate detection probability using nondestructive 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 UF{sub 6} containers used in the process of enrichment at GCEPs. In verifying declared LEU production, the inspectors also take samples for off-site destructive assay (DA) which provide accurate data, with 0.1% to 0.5% measurement uncertainty, on the enrichment of the UF{sub 6} feed, tails, and product. However, taking samples of UF{sub 6} for off-site analysis is a much more labor and resource intensive exercise for the operator and inspector. Furthermore, the operator must ship the samples off-site to the IAEA laboratory which delays the timeliness of results and interruptions to the continuity of knowledge (CofK) of the samples during their storage and transit. This paper contains an analysis of possible improvements in unattended and attended NDA systems such as process monitoring and possible on-site analysis of DA samples that could reduce the uncertainty of the inspector's measurements and provide more effective and efficient IAEA GCEPs safeguards. We also introduce examples advanced safeguards systems that could be assembled for unattended operation.

  1. Advanced Process Monitoring Techniques for Safeguarding Reprocessing Facilities

    SciTech Connect (OSTI)

    Orton, Christopher R.; Bryan, Samuel A.; Schwantes, Jon M.; Levitskaia, Tatiana G.; Fraga, Carlos G.; Peper, Shane M.

    2010-11-30

    The International Atomic Energy Agency (IAEA) has established international safeguards standards for fissionable material at spent fuel reprocessing plants to ensure that significant quantities of weapons-grade nuclear material are not diverted from these facilities. For large throughput nuclear facilities, it is difficult to satisfy the IAEA safeguards accountancy goal for detection of abrupt diversion. Currently, methods to verify material control and accountancy (MC&A) at these facilities require time-consuming and resource-intensive destructive assay (DA). Leveraging new on-line non destructive assay (NDA) process monitoring techniques in conjunction with the traditional and highly precise DA methods may provide an additional measure to nuclear material accountancy which would potentially result in a more timely, cost-effective and resource efficient means for safeguards verification at such facilities. By monitoring process control measurements (e.g. flowrates, temperatures, or concentrations of reagents, products or wastes), abnormal plant operations can be detected. Pacific Northwest National Laboratory (PNNL) is developing on-line NDA process monitoring technologies, including both the Multi-Isotope Process (MIP) Monitor and a spectroscopy-based monitoring system, to potentially reduce the time and resource burden associated with current techniques. The MIP Monitor uses gamma spectroscopy and multivariate analysis to identify off-normal conditions in process streams. The spectroscopic monitor continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major cold flowsheet chemicals using UV-Vis, Near IR and Raman spectroscopy. This paper will provide an overview of our methods and report our on-going efforts to develop and demonstrate the technologies.

  2. Nuclear Safeguards Considerations For The Pebble Bed Modular Reactor (PBMR)

    SciTech Connect (OSTI)

    Phillip Casey Durst; David Beddingfield; Brian Boyer; Robert Bean; Michael Collins; Michael Ehinger; David Hanks; David L. Moses; Lee Refalo

    2009-10-01

    High temperature reactors (HTRs) have been considered since the 1940s, and have been constructed and demonstrated in the United Kingdom (Dragon), United States (Peach Bottom and Fort Saint Vrain), Japan (HTTR), Germany (AVR and THTR-300), and have been the subject of conceptual studies in Russia (VGM). The attraction to these reactors is that they can use a variety of reactor fuels, including abundant thorium, which upon reprocessing of the spent fuel can produce fissile U-233. Hence, they could extend the stocks of available uranium, provided the fuel is reprocessed. Another attractive attribute is that HTRs typically operate at a much higher temperature than conventional light water reactors (LWRs), because of the use of pyrolytic carbon and silicon carbide coated (TRISO) fuel particles embedded in ceramic graphite. Rather than simply discharge most of the unused heat from the working fluid in the power plant to the environment, engineers have been designing reactors for 40 years to recover this heat and make it available for district heating or chemical conversion plants. Demonstrating high-temperature nuclear energy conversion was the purpose behind Fort Saint Vrain in the United States, THTR-300 in Germany, HTTR in Japan, and HTR-10 and HTR-PM, being built in China. This resulted in nuclear reactors at least 30% or more thermodynamically efficient than conventional LWRs, especially if the waste heat can be effectively utilized in chemical processing plants. A modern variant of high temperature reactors is the Pebble Bed Modular Reactor (PBMR). Originally developed in the United States and Germany, it is now being redesigned and marketed by the Republic of South Africa and China. The team examined historical high temperature and high temperature gas reactors (HTR and HTGR) and reviewed safeguards considerations for this reactor. The following is a preliminary report on this topic prepared under the ASA-100 Advanced Safeguards Project in support of the NNSA Next Generation Safeguards Initiative (NGSI).

  3. Safeguards applied to the design of recovery processing

    SciTech Connect (OSTI)

    Hawke, A.C. )

    1988-01-01

    A project to redesign and modify portions of the Rocky Flats plutonium reprocessing facility is currently underway. Essential to the project is a design concept using modular construction methods to allow actual processing to occur concomitant with ongoing process operations. Although the design concept must be and is responsive to numerous Department of Energy and Rockwell requirements governing the design and operation of plutonium process systems, the purpose of this paper is to singularly focus on and review those safeguards requirements, concerns, and criteria which must be addressed in recovery processing design to ensure the protection and accountability of Special Nuclear Materials.

  4. Radiation detectors as surveillance monitors for IAEA safeguards

    SciTech Connect (OSTI)

    Fehlau, P.E.; Dowdy, E.J.

    1980-10-01

    Radiation detectors used for personnel dosimetry are examined for use under IAEA Safeguards as monitors to confirm the passage or nonpassage (YES/NO) of plutonium-bearing nuclear material at barrier penetrations declared closed. In this application where backgrounds are ill defined, no advantage is found for a particular detector type because of intrinsic efficiency. Secondary considerations such as complexity, ease of tamper-proofing, and ease of readout are used to recommend specific detector types for routine monitoring and for data-base measurements. Recommendations are made for applications, data acquisition, and instrument development.

  5. Safeguards Guidance for Prismatic Fueled High Temperature Gas Reactors (HTGR)

    National Nuclear Security Administration (NNSA)

    5) August 2012 Guidance for High Temperature Gas Reactors (HTGRs) with Prismatic Fuel INL/CON-12-26130 Revision 0 Safeguards-by-Design: Guidance for High Temperature Gas Reactors (HTGRs) With Prismatic Fuel Philip Casey Durst (INL Consultant) August 2012 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes

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

    SciTech Connect (OSTI)

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

    1997-03-01

    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 IV 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.

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

    SciTech Connect (OSTI)

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

    2011-09-30

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

  8. Notice of Intent to Develop an Information Sharing and Safeguarding Program Notice

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

    2014-08-07

    This memorandum provides justification for establishing a Directive that sets forth requirements and responsibilities for the Department of Energy's (DOE) Information Sharing and Safeguarding (ISS) Program for the responsible sharing and safeguarding of Agency information to enhance national security, protect the safety of the American people, and encourage sustained collaboration between Federal, state, local, tribal, territorial, private sector, and foreign partners,

  9. A parameter study to optimizing scintillator characteristics for increased sensitivity in nuclear nonproliferation, safeguards, and security based applications

    SciTech Connect (OSTI)

    Shy, Daniel

    2014-08-01

    A parameter study to optimizing scintillator characteristics for increased sensitivity in nuclear nonproliferation, safeguards, and security based applications

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

    SciTech Connect (OSTI)

    Kollar, Lenka; Mathews, Caroline E.

    2009-07-01

    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 order 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.

  11. Oak Ridge National Laboratory Next-Generation Safeguards Initiative: Human Capital Development

    SciTech Connect (OSTI)

    Gilligan, Kimberly

    2014-01-01

    In 2007, the US Department of Energy National Nuclear Security Administration (DOE/NNSA) Office of Nonproliferation and International Security (NA-24) completed a comprehensive review of the current and potential future challenges facing the international safeguards system. The review examined: trends and events that have an effect on the mission of international safeguards; the implications of expanding and evolving mission requirements of the legal authorities and institutions that serve as the foundation of the international safeguards system; and, the technological, financial, and human resources required for effective safeguards implementation. The review’s findings and recommendations were summarized in the report International Safeguards: Challenges and Opportunities for the 21st Century (October 2007). The executive summary is available at the following link: http://nnsa.energy.gov/sites/default/files/nnsa/inlinefiles/NGSI_Report.pdf.

  12. Advanced Safeguards Technology Demonstration at Pacific Northwest National Laboratory

    SciTech Connect (OSTI)

    Orton, Christopher R.; Schwantes, Jon M.; Bryan, Samuel A.; Levitskaia, Tatiana G.; Duckworth, Douglas C.; Douglas, Matthew; Farmer, O. T.; Fraga, Carlos G.; Lehn, Scott A.; Liezers, Martin; Peper, Shane M.; Christensen, Richard

    2008-10-01

    The IAEA has established international safeguards standards for fissionable materials at spent fuel reprocessing plants to ensure that significant quantities of weapons-grade nuclear material are not diverted over a specified time frame. It is, therefore, necessary to confirm proper operational performance to verify facilities operate under adequate safeguard-declared conditions. This verification can be achieved by employing monitoring equipment. Online real time monitoring of the flowsheet radiochemical streams provides a unique capability to rapidly identify deviations from normal operating conditions. Flowsheet monitoring technologies being developed at PNNL include three integrated systems: Multi-Isotope Process (MIP) Monitor, spectroscopy-based monitor (UV-vis-NIR and Raman spectrometers), and Electrochemically Modulated Separations (EMS). The MIP Monitor is designed to identify off-normal conditions in process streams using gamma spectroscopy and pattern recognition software. The spectroscopic monitoring continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major cold flowsheet chemicals. EMS provides an on-line means for pre-separating and pre-concentrating elements of interest out of complex matrices prior to detection. PNNL is preparing to test these multi-parametric technologies using different samples of dissolved spent fuel and aqueous and organic phases of the PUREX and UREX flowsheets. We will report our on-going efforts with specific focus given to quantifying sensitivity of the MIP Monitor and UV-Vis and Raman spectrometers to detect minor changes in major process variables.

  13. New Measures to Safeguard Gas Centrifuge Enrichment Plants

    SciTech Connect (OSTI)

    Whitaker, Jr., James; Garner, James R; Whitaker, Michael; Lockwood, Dunbar; Gilligan, Kimberly V; Younkin, James R; Hooper, David A; Henkel, James J; Krichinsky, Alan M

    2011-01-01

    As Gas Centrifuge Enrichment Plants (GCEPs) increase in separative work unit (SWU) capacity, the current International Atomic Energy Agency (IAEA) model safeguards approach needs to be strengthened. New measures to increase the effectiveness of the safeguards approach are being investigated that will be mutually beneficial to the facility operators and the IAEA. One of the key concepts being studied for application at future GCEPs is embracing joint use equipment for process monitoring of load cells at feed and withdrawal (F/W) stations. A mock F/W system was built at Oak Ridge National Laboratory (ORNL) to generate and collect F/W data from an analogous system. The ORNL system has been used to collect data representing several realistic normal process and off-normal (including diversion) scenarios. Emphasis is placed on the novelty of the analysis of data from the sensors as well as the ability to build information out of raw data, which facilitates a more effective and efficient verification process. This paper will provide a progress report on recent accomplishments and next steps.

  14. Fully integrated safeguards and security for reprocessing plant monitoring.

    SciTech Connect (OSTI)

    Duran, Felicia Angelica; Ward, Rebecca; Cipiti, Benjamin B.; Middleton, Bobby D.

    2011-10-01

    Nuclear fuel reprocessing plants contain a wealth of plant monitoring data including material measurements, process monitoring, administrative procedures, and physical protection elements. Future facilities are moving in the direction of highly-integrated plant monitoring systems that make efficient use of the plant data to improve monitoring and reduce costs. The Separations and Safeguards Performance Model (SSPM) is an analysis tool that is used for modeling advanced monitoring systems and to determine system response under diversion scenarios. This report both describes the architecture for such a future monitoring system and present results under various diversion scenarios. Improvements made in the past year include the development of statistical tests for detecting material loss, the integration of material balance alarms to improve physical protection, and the integration of administrative procedures. The SSPM has been used to demonstrate how advanced instrumentation (as developed in the Material Protection, Accounting, and Control Technologies campaign) can benefit the overall safeguards system as well as how all instrumentation is tied into the physical protection system. This concept has the potential to greatly improve the probability of detection for both abrupt and protracted diversion of nuclear material.

  15. Assessing Lanthanum-Bromide Detectors for Safeguards Applications

    SciTech Connect (OSTI)

    Gariazzo, Claudio Andres; Saavedra, Steven F; Smith, Steven E; Solodov, Alexander A

    2008-01-01

    Major detector technologies currently being used for gamma-ray spectroscopy in safeguards applications include systems based on sodium iodide (NaI), cadmium-zinc-telluride (CZT), cadmium-telluride (CdTe), and high-purity germanium (HPGe) crystals. Recently, a new scintillation detector based on a lanthanum bromide (LaBr3) crystal has become commercially available. The declared benefits of this new detector technology include higher resolution and improved efficiency compared with similarly configured NaI-based systems. Both detector systems offer the advantage of room-temperature operation. This paper describes the results of a study assessing the safeguards applicability and advantages for isotopic and quantitative analyses of uranium using the LaBr3-based detector, as well as an investigation into the general operating characteristics of the LaBr3-based detector. The results are compared with those from a widely used NaI-based detector system (Canberra's Inspector-1000 multichannel analyzer) operated under similar environmental conditions and hardware configuration, using commercially available software packages (NaIGEM and Genie-2000).

  16. The New Brunswick Laboratory Safeguards Measurement Evaluation Program

    SciTech Connect (OSTI)

    Cacic, C.G.; Trahey, N.M.; Zook, A.C.

    1987-07-01

    The New Brunswick Laboratory (NBL) has been tasked by the U.S. Department of Energy (DOE) Office of Safeguards and Security (OSS) to assess and evaluate the adequacy of measurement technology as applied to materials accounting in DOE nuclear facilities. The Safeguards Measurement Evaluation (SME) Program was developed as a means to monitor and evaluate the quality and effectiveness of accounting measurements by site, material balance area (MBA), or unit process. Phase I of the SME Program, initiated during 1985, involved evaluation of the primary accountability measurement methods at six DOE Defense Programs facilities: Savannah River Plant, Portsmouth Gaseous Diffusion Plant, Y-12 Plant, Rocky Flats Plant, Rockwell Hanford Operations, and NBL. Samples of uranyl nitrate solution, dried plutonium nitrates, and plutonium oxides were shipped to the participants for assay and isotopic abundance measurements. Resulting data are presented and evaluated as indicators of current state-of-the-practice accountability measurement methodology, deficiencies in materials accounting practices, and areas for possible assistance in upgrading measurement capabilities. Continuing expansion of the SME Program to include materials which are representative of specific accountability measurement points within the DOE complex is discussed.

  17. Safeguards and security by design (SSBD) for the domestic threat - theft and sabotage

    SciTech Connect (OSTI)

    Demuth, Scott F; Mullen, Mark

    2011-10-05

    Safeguards by Design (SBD) is receiving significant interest with respect to international safeguards objectives. However, less attention has been focused on the equally important topic of domestic Safeguards and Security by Design (SSBD), which addresses requirements such as those of the Nuclear Regulatory Commission (NRC) in the United States. While international safeguards are concerned with detecting State diversion of nuclear material from peaceful to nuclear explosives purposes, domestic Material Protection, Control and Accounting measures (MPC&A) are focused on non-State theft and sabotage. The International Atomic Energy Agency (IAEA) has described the Safeguards by Design (SBD) concept as an approach in which 'international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and decommissioning.' This same concept is equally applicable to SSBD for domestic requirements. The United States Department of Energy (DOE) has initiated a project through its Office of Nuclear Energy (NE) and more specifically its Fuel Cycle Research and Development (FCRD) program, to develop a domestic SSBD discipline and methodology in parallel with similar efforts sponsored by the DOE Next Generation Safeguards Initiative (NGSI) and the IAEA for international safeguards. This activity includes the participation of industry (through DOE-sponsored contracts) and DOE National Laboratories. This paper will identify the key domestic safeguards and security requirements (i.e. MC&A and physical protection) and explain how and why Safeguards and Security by Design (SSBD) is important and beneficial for the design of future US nuclear energy systems.

  18. Los Alamos National Laboratory Facilities, Security and Safeguards Division, Safeguards and Security Program Office, Protective Force Oversight Program

    SciTech Connect (OSTI)

    1995-11-30

    The purpose of this document is to identify and describe the duties and responsibilities of Facility Security and Safeguards (FSS) Safeguards and Security (SS) organizations (groups/offices) with oversight functions over the Protection Force (PF) subcontractor. Responsible organizations will continue their present PF oversight functions under the Cost Plus Award Fee (CPAF) assessment, but now will be required to also coordinate, integrate, and interface with other FSS S and S organizations and with the PF subcontractor to measure performance, assess Department of Energy (DOE) compliance, reduce costs, and minimize duplication of effort. The role of the PF subcontractor is to provide the Laboratory with effective and efficient protective force services. PF services include providing protection for the special nuclear material, government property and classified or sensitive information developed and/or consigned to the Laboratory, as well as protection for personnel who work or participate in laboratory activities. FSS S and S oversight of both performance and compliance standards/metrics is essential for these PF objectives to be met.

  19. A Monte Carlo based spent fuel analysis safeguards strategy assessment

    SciTech Connect (OSTI)

    Fensin, Michael L; Tobin, Stephen J; Swinhoe, Martyn T; Menlove, Howard O; Sandoval, Nathan P

    2009-01-01

    Safeguarding nuclear material involves the detection of diversions of significant quantities of nuclear materials, and the deterrence of such diversions by the risk of early detection. There are a variety of motivations for quantifying plutonium in spent fuel assemblies by means of nondestructive assay (NDA) including the following: strengthening the capabilities of the International Atomic Energy Agencies ability to safeguards nuclear facilities, shipper/receiver difference, input accountability at reprocessing facilities and burnup credit at repositories. Many NDA techniques exist for measuring signatures from spent fuel; however, no single NDA technique can, in isolation, quantify elemental plutonium and other actinides of interest in spent fuel. A study has been undertaken to determine the best integrated combination of cost effective techniques for quantifying plutonium mass in spent fuel for nuclear safeguards. A standardized assessment process was developed to compare the effective merits and faults of 12 different detection techniques in order to integrate a few techniques and to down-select among the techniques in preparation for experiments. The process involves generating a basis burnup/enrichment/cooling time dependent spent fuel assembly library, creating diversion scenarios, developing detector models and quantifying the capability of each NDA technique. Because hundreds of input and output files must be managed in the couplings of data transitions for the different facets of the assessment process, a graphical user interface (GUI) was development that automates the process. This GUI allows users to visually create diversion scenarios with varied replacement materials, and generate a MCNPX fixed source detector assessment input file. The end result of the assembly library assessment is to select a set of common source terms and diversion scenarios for quantifying the capability of each of the 12 NDA techniques. We present here the generalized assessment process, the techniques employed to automate the coupled facets of the assessment process, and the standard burnup/enrichment/cooling time dependent spent fuel assembly library. We also clearly define the diversion scenarios that will be analyzed during the standardized assessments. Though this study is currently limited to generic PWR assemblies, it is expected that the results of the assessment will yield an adequate spent fuel analysis strategy knowledge that will help the down-select process for other reactor types.

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

    SciTech Connect (OSTI)

    Michael Holzemer; Alan Carvo

    2012-04-01

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

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

    SciTech Connect (OSTI)

    Pepper, Susan E.; Pickett, Chris A.; Queirolo, Al; Bachner, Katherine M.; Worrall, Louise G.

    2015-04-07

    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 optimal 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.

  2. Framework for fuel-cycle approaches to IAEA safeguards

    SciTech Connect (OSTI)

    Fishbone, L.G.; Higinbotham, W.

    1986-01-01

    A framework is presented for comparing various safeguards verification approaches which have been proposed for consideration. Each inventory change, inventory, and material balance for each nuclear facility, reported by a state, may be verified. Verification approaches are compared by listing which of these reports would be verified and to what degree for each approach as they might be applied to a state with a closed fuel cycle. The comparison indicates that the extended-material-balance-area (or zone), the information-correlation, and the randomization-over-facilities approaches make more efficient use of Agency resources than the facility-oriented approach for states with large nuclear power programs. In contrast, any advantages of randomizing inspections over inspection activities within facilities are, percentagewise, relatively independent of the size of a state's nuclear program.

  3. Perimeter safeguards techniques for uranium-enrichment plants

    SciTech Connect (OSTI)

    Fehlau, P.E.; Chamber, W.H.

    1981-09-01

    In 1972, a working group of the International Atomic Energy Agency identified a goal to develop and evaluate perimeter safeguards for uranium isotope enrichment plants. As part of the United State's response to that goal, Los Alamos Detection and Verification personnel studied gamma-ray and neutron emissions from uranium hexafluoride. They developed instruments that use the emissions to verify uranium enrichment and to monitor perimeter personnel and shipping portals. Unattended perimeter monitors and hand-held verification instruments were evaluated in field measurements and, when possible, were loaned to enrichment facilities for trials. None of the seven package monitoring techniques that were investigated proved entirely satisfactory for an unattended monitor. They either revealed proprietary information about centrifuge design or were subject to interference by shielding materials that could be present in a package. Further evaluation in a centrifuge facility may help in developing an acceptable attended package monitor. 34 figures, 9 tables.

  4. Next Generations Safeguards Initiative: The Life of a Cylinder

    SciTech Connect (OSTI)

    Morgan, James B; White-Horton, Jessica L

    2012-01-01

    The U.S. Department of Energy/National Nuclear Security Administration Office of Nonproliferation and International Security's Next Generation Safeguards Initiative (NGSI) has begun a program based on a five-year plan to investigate the concept of a global monitoring scheme that uniquely identifies uranium hexafluoride (UF6) cylinders and their locations throughout the life cycle. A key initial activity in the NGSI program is to understand and document the 'life of a UF6 cylinder' from cradle to grave. This document describes the life of a UF6 cylinder and includes cylinder manufacture and procurement processes as well as cylinder-handling and operational practices at conversion, enrichment, fuel fabrication, and depleted UF6 conversion facilities. The NGSI multiple-laboratory team is using this document as a building block for subsequent tasks in the five-year plan, including development of the functional requirements for cylinder-tagging and tracking devices.

  5. The uranium cylinder assay system for enrichment plant safeguards

    SciTech Connect (OSTI)

    Miller, Karen A; Swinhoe, Martyn T; Marlow, Johnna B; Menlove, Howard O; Rael, Carlos D; Iwamoto, Tomonori; Tamura, Takayuki; Aiuchi, Syun

    2010-01-01

    Safeguarding sensitive fuel cycle technology such as uranium enrichment is a critical component in preventing the spread of nuclear weapons. A useful tool for the nuclear materials accountancy of such a plant would be an instrument that measured the uranium content of UF{sub 6} cylinders. The Uranium Cylinder Assay System (UCAS) was designed for Japan Nuclear Fuel Limited (JNFL) for use in the Rokkasho Enrichment Plant in Japan for this purpose. It uses total neutron counting to determine uranium mass in UF{sub 6} cylinders given a known enrichment. This paper describes the design of UCAS, which includes features to allow for unattended operation. It can be used on 30B and 48Y cylinders to measure depleted, natural, and enriched uranium. It can also be used to assess the amount of uranium in decommissioned equipment and waste containers. Experimental measurements have been carried out in the laboratory and these are in good agreement with the Monte Carlo modeling results.

  6. Department of energy defense programs perspectives on safeguards, security, and classification

    SciTech Connect (OSTI)

    Eyck, E.Q.T. )

    1989-07-01

    This paper discusses why national and international safeguards and the protection of sensitive information are important to the United States and to other nations. It demonstrates that while the opposite consequence appears logical these functions will probably become even more important if the major powers agree on further arms reductions. Some of the steps taken by the U.S. Department of Energy to improve the effectiveness of its safeguards, security, and classification programs are reviewed. The valuable contributions in these areas since 1968 and 1976, respectively by the Technical Support Organization and the International Safeguards Project Offoce at Brookhaven are noted.

  7. Advanced Safeguards Technology Demonstration at Pacific Northwest National Laboratory

    SciTech Connect (OSTI)

    Arrigo, Leah M.; Bryan, Samuel A.; Christensen, Richard; Douglas, Matthew; Duckworth, Douglas C.; Fraga, Carlos G.; Levitskaia, Tatiana G.; Liezers, Martin; Orton, Christopher R.; Peper, Shane M.; Schwantes, Jon M.

    2010-05-21

    The International Atomic Energy Agency (IAEA) has established international safeguards standards for fissionable material at spent fuel reprocessing plants to ensure that significant quantities of weapons-grade nuclear material are not diverted over a specified time frame. Currently, methods to verify that the facilities are operating under adequate safeguard-declared conditions require time consuming sampling and expensive, destructive analysis. The time delay between sampling and subsequent analysis provides a potential opportunity to divert the material out of the appropriate chemical stream. One way to avoid this problem is to use process monitoring equipment that is capable of on-line and in near-real time monitoring of the flowsheet radiochemical streams to rapidly identify deviations from normal operating conditions. Three integrated systems for flowsheet monitoring are currently being developed at PNNL including: 1) Multi-Isotope Process Monitor (MIP), 2) a spectroscopy-based monitor utilizing UV-Vis-NIR (Ultra Violet-Visible-Near Infrared) and Raman spectrometers, and 3) Electrochemically Modulated Separations (EMS). MIP uses gamma spectroscopy and pattern recognition software to identify off-normal conditions in process streams. The UV-Vis-NIR and Raman spectroscopic monitoring continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major cold flowsheet chemicals. EMS provides an on-line means for pre-separating and preconcentrating elements of interest out of complex matrices prior to detection via non-destructive assay by gamma spectroscopy or destructive analysis with mass spectrometry. PNNL previously reported some of its initial modeling work as proof of principle. Here we will provide a general overview of the technologies and the ongoing demonstrations that utilize actual spent fuel.

  8. Strengthened IAEA Safeguards-Imagery Analysis: Geospatial Tools for Nonproliferation Analysis

    SciTech Connect (OSTI)

    Pabian, Frank V

    2012-08-14

    This slide presentation focuses on the growing role and importance of imagery analysis for IAEA safeguards applications and how commercial satellite imagery, together with the newly available geospatial tools, can be used to promote 'all-source synergy.' As additional sources of openly available information, satellite imagery in conjunction with the geospatial tools can be used to significantly augment and enhance existing information gathering techniques, procedures, and analyses in the remote detection and assessment of nonproliferation relevant activities, facilities, and programs. Foremost of the geospatial tools are the 'Digital Virtual Globes' (i.e., GoogleEarth, Virtual Earth, etc.) that are far better than previously used simple 2-D plan-view line drawings for visualization of known and suspected facilities of interest which can be critical to: (1) Site familiarization and true geospatial context awareness; (2) Pre-inspection planning; (3) Onsite orientation and navigation; (4) Post-inspection reporting; (5) Site monitoring over time for changes; (6) Verification of states site declarations and for input to State Evaluation reports; and (7) A common basis for discussions among all interested parties (Member States). Additionally, as an 'open-source', such virtual globes can also provide a new, essentially free, means to conduct broad area search for undeclared nuclear sites and activities - either alleged through open source leads; identified on internet BLOGS and WIKI Layers, with input from a 'free' cadre of global browsers and/or by knowledgeable local citizens (a.k.a.: 'crowdsourcing'), that can include ground photos and maps; or by other initiatives based on existing information and in-house country knowledge. They also provide a means to acquire ground photography taken by locals, hobbyists, and tourists of the surrounding locales that can be useful in identifying and discriminating between relevant and non-relevant facilities and their associated infrastructure. The digital globes also provide highly accurate terrain mapping for better geospatial context and allow detailed 3-D perspectives of all sites or areas of interest. 3-D modeling software (i.e., Google's SketchUp6 newly available in 2007) when used in conjunction with these digital globes can significantly enhance individual building characterization and visualization (including interiors), allowing for better assessments including walk-arounds or fly-arounds and perhaps better decision making on multiple levels (e.g., the best placement for International Atomic Energy Agency (IAEA) video monitoring cameras).

  9. Evaluation of a Business Case for Safeguards by Design in Nuclear Power Reactors

    SciTech Connect (OSTI)

    Wood, Thomas W.; Seward, Amy M.; Lewis, Valerie A.; Gitau, Ernest TN; Zentner, Michael D.

    2012-12-01

    Safeguards by Design (SbD) is a well-known paradigm for consideration and incorporation of safeguards approaches and associated design features early in the nuclear facility development process. This paradigm has been developed as part of the Next Generation Safeguards Initiative (NGSI), and has been accepted as beneficial in many discussions and papers on NGSI or specific technologies under development within NGSI. The Office of Nuclear Safeguards and Security funded the Pacific Northwest National Laboratory to examine the business case justification of SbD for nuclear power reactors. Ultimately, the implementation of SbD will rely on the designers of nuclear facilities. Therefore, it is important to assess the incentives which will lead designers to adopt SbD as a standard practice for nuclear facility design. This report details the extent to which designers will have compelling economic incentives to adopt SbD.

  10. Feasibility Study of Implementing a Mobile Collaborative Information Platform for International Safeguards Inspections

    SciTech Connect (OSTI)

    Gastelum, Zoe N.; Gitau, Ernest TN; Doehle, Joel R.; Toomey, Christopher M.

    2014-09-30

    In response to the growing pervasiveness of mobile technologies such as tablets and smartphones, the International Atomic Energy Agency and the U.S. Department of Energy National Laboratories have been exploring the potential use of these platforms for international safeguards activities. Specifically of interest are information systems (software, and accompanying servers and architecture) deployed on mobile devices to increase the situational awareness and productivity of an IAEA safeguards inspector in the field, while simultaneously reducing paperwork and pack weight of safeguards equipment. Exploratory development in this area has been met with skepticism regarding the ability to overcome technology deployment challenges for IAEA safeguards equipment. This report documents research conducted to identify potential challenges for the deployment of a mobile collaborative information system to the IAEA, and proposes strategies to mitigate those challenges.

  11. Processing large sensor data sets for safeguards : the knowledge generation system.

    SciTech Connect (OSTI)

    Thomas, Maikel A.; Smartt, Heidi Anne; Matthews, Robert F.

    2012-04-01

    Modern nuclear facilities, such as reprocessing plants, present inspectors with significant challenges due in part to the sheer amount of equipment that must be safeguarded. The Sandia-developed and patented Knowledge Generation system was designed to automatically analyze large amounts of safeguards data to identify anomalous events of interest by comparing sensor readings with those expected from a process of interest and operator declarations. This paper describes a demonstration of the Knowledge Generation system using simulated accountability tank sensor data to represent part of a reprocessing plant. The demonstration indicated that Knowledge Generation has the potential to address several problems critical to the future of safeguards. It could be extended to facilitate remote inspections and trigger random inspections. Knowledge Generation could analyze data to establish trust hierarchies, to facilitate safeguards use of operator-owned sensors.

  12. US statutes of general interest to safeguards and security officers. Revision 12/95

    SciTech Connect (OSTI)

    Cadwell, J.J.; Ruger, C.J.

    1995-12-01

    This document is one of a three volume set. This document, BNL 52202, it titled, ``US Statutes of General Interest to Safeguards and Security Officers``, and is intended for use by officers.

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

    SciTech Connect (OSTI)

    Philip Casey Durst; Mark Schanfein

    2012-08-01

    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) time, money, and resources and be mutually beneficial. This particular safeguards guidance document focuses on pebble 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 IAEA Design Information Questionnaire (DIQ), prepared by the facility operator, typically with the support of the facility designer. The IAEA will verify design information over the life of the project. This design information is an important IAEA safeguards tool. Since the main interlocutor with the IAEA in each country is the State Regulatory Authority/SSAC (or Regional Regulatory Authority, e.g. EURATOM), the responsibility for conveying this design information to the IAEA falls to the State Regulatory Authority/SSAC.

  14. A Brief History of International Safeguards (Technical Report) | SciTech

    Office of Scientific and Technical Information (OSTI)

    Connect A Brief History of International Safeguards Citation Details In-Document Search Title: A Brief History of International Safeguards Authors: Boyer, Brian D. [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2013-08-05 OSTI Identifier: 1089462 Report Number(s): LA-UR-13-26172 DOE Contract Number: AC52-06NA25396 Resource Type: Technical Report Research Org: Los Alamos National Laboratory (LANL) Sponsoring Org: DOE/LANL Country of Publication: United States

  15. DOE to Provide Nearly $8 Million to Safeguard the Nation's Energy

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

    Infrastructure from Cyber Attacks | Department of Energy 8 Million to Safeguard the Nation's Energy Infrastructure from Cyber Attacks DOE to Provide Nearly $8 Million to Safeguard the Nation's Energy Infrastructure from Cyber Attacks October 18, 2007 - 3:21pm Addthis WASHINGTON, DC - U.S. Department of Energy (DOE) Assistant Secretary for Electricity Delivery and Energy Reliability Kevin M. Kolevar today announced five projects that have been selected for negotiation of awards of up to $7.9

  16. DOE to Provide Nearly $8 Million to Safeguard the Nation's Energy

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

    Infrastructure from Cyber Attacks | Department of Energy to Provide Nearly $8 Million to Safeguard the Nation's Energy Infrastructure from Cyber Attacks DOE to Provide Nearly $8 Million to Safeguard the Nation's Energy Infrastructure from Cyber Attacks October 18, 2007 - 4:39pm Addthis U.S. Department of Energy (DOE) Assistant Secretary for Electricity Delivery and Energy Reliability Kevin M. Kolevar today announced five projects that have been selected for negotiation of awards of up to

  17. DOE to Provide Nearly $8 Million to Safeguard the Nation's Energy

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

    Infrastructure from Cyber Attacks | Department of Energy to Provide Nearly $8 Million to Safeguard the Nation's Energy Infrastructure from Cyber Attacks DOE to Provide Nearly $8 Million to Safeguard the Nation's Energy Infrastructure from Cyber Attacks U.S. Department of Energy (DOE) Assistant Secretary for Electricity Delivery and Energy Reliability Kevin M. Kolevar today announced five projects that have been selected for negotiation of awards of up to $7.9 million in DOE funding to

  18. A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring

    Office of Scientific and Technical Information (OSTI)

    Systems and Strategies Intended for Nuclear Fuel Enrichment and Processing Plants (Technical Report) | SciTech Connect SciTech Connect Search Results Technical Report: A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment and Processing Plants Citation Details In-Document Search Title: A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment

  19. Success Through Safety, Security, and Safeguards by Design (3SBD): From

    Office of Scientific and Technical Information (OSTI)

    Concept to Application Workshop (Conference) | SciTech Connect Success Through Safety, Security, and Safeguards by Design (3SBD): From Concept to Application Workshop Citation Details In-Document Search Title: Success Through Safety, Security, and Safeguards by Design (3SBD): From Concept to Application Workshop Authors: Murphy, Chantell L. [1] ; Blandford, Edward [2] ; Arthur, Edward [2] + Show Author Affiliations Los Alamos National Laboratory University of New Mexico Publication Date:

  20. Microsoft PowerPoint - IAEA Safeguards Reporting Requirements for U.S. Facilities_Peter Habighorst

    National Nuclear Security Administration (NNSA)

    IAEA Safeguards Reporting Requirements for U.S. Facilities Peter Habighorst, MC&A Branch Chief U.S. Nuclear Regulatory Commission IAEA Nuclear Material Reporting to the IAEA BACKGROUND - Overview of Governing Requirements Reporting Requirements  IAEA Information Circular (INFCIRC)/207, Notification to the Agency of Exports and Imports of Nuclear Material, July 1974  IAEA INFCIRC/288, Agreement between the United States of America and the Agency for Safeguards in the United States,

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

    SciTech Connect (OSTI)

    Boyer, Brian David; Erpenbeck, Heather H; Miller, Karen A; Ianakiev, Kiril D; Reimold, Benjamin A; Ward, Steven L; Howell, John

    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 NDA 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.

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

    SciTech Connect (OSTI)

    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 usability 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.

  3. Incorporating Biodiversity Considerations Into Environmental Impact Analysis Under NEPA (CEQ, 1993)

    Broader source: Energy.gov [DOE]

    This Council on Environmental Quality (CEQ) report is intended to provide background on the emerging, complex subject of biodiversity, outline some general concepts that underlie biological diversity analysis and management, describe how the issue is currently addressed in NEPA analyses, and provide options for agencies undertaking NEPA analyses that consider biodiversity.

  4. Enhanced AFCI Sampling, Analysis, and Safeguards Technology Review

    SciTech Connect (OSTI)

    John Svoboda

    2009-09-01

    The focus of this study includes the investigation of sampling technologies used in industry and their potential application to nuclear fuel processing. The goal is to identify innovative sampling methods using state of the art techniques that could evolve into the next generation sampling and analysis system for metallic elements. Sampling and analysis of nuclear fuel recycling plant processes is required both to monitor the operations and ensure Safeguards and Security goals are met. In addition, environmental regulations lead to additional samples and analysis to meet licensing requirements. The volume of samples taken by conventional means, can restrain productivity while results samples are analyzed, require process holding tanks that are sized to meet analytical issues rather than process issues (and that create a larger facility footprint), or, in some cases, simply overwhelm analytical laboratory capabilities. These issues only grow when process flowsheets propose new separations systems and new byproduct material for transmutation purposes. Novel means of streamlining both sampling and analysis are being evaluated to increase the efficiency while meeting all requirements for information. This report addresses just a part of the effort to develop and study novel methods by focusing on the sampling and analysis of aqueous samples for metallic elements. It presents an overview of the sampling requirements, including frequency, sensitivity, accuracy, and programmatic drivers, to demonstrate the magnitude of the task. The sampling and analysis system needed for metallic element measurements is then discussed, and novel options being applied to other industrial analytical needs are presented. Inductively coupled mass spectrometry instruments are the most versatile for metallic element analyses and are thus chosen as the focus for the study. Candidate novel means of process sampling, as well as modifications that are necessary to couple such instruments to introduce these samples, are discussed. A suggested path forward based on an automated microchip capillary based sampling system interfaced to the analysis spectrometer is presented. The ability to obtain micro liter volume samples coupled with remote automated means of sample tracking and transport to the instrument would greatly improve analytical efficiency while reducing both personnel exposure and radioactive waste. Application of this sampling technique to new types of mass spectrometers for selective elemental isotopic analysis could also provide significant improvements in safeguards and security analyses.

  5. Application of Telepresence Technologies to Nuclear Material Safeguards

    SciTech Connect (OSTI)

    Wright, M.C.; Rome, J.A.

    1999-09-20

    Implementation of remote monitoring systems has become a priority area for the International Atomic Energy Agency and other international inspection regimes. For the past three years, DOE2000 has been the US Department of Energy's (DOE's) initiative to develop innovative applications to exploit the capabilities of broadband networks and media integration. The aim is to enhance scientific collaboration by merging computing and communications technologies. These Internet-based telepresence technologies could be easily extended to provide remote monitoring and control for confidence building and transparency systems at nuclear facilities around the world. One of the original DOE2000 projects, the Materials Microcharacterization Collaboratory is an interactive virtual laboratory, linking seven DOE user facilities located across the US. At these facilities, external collaborators have access to scientists, data, and instrumentation, all of which are available to varying degrees using the Internet. Remote operation of the instruments varies between passive (observational) to active (direct control), in many cases requiring no software at the remote site beyond a Web browser. Live video streams are continuously available on the Web so that participants can see what is happening at a particular location. An X.509 certificate system provides strong authentication, The hardware and software are commercially available and are easily adaptable to safeguards applications.

  6. PROCESS MONITORING FOR SAFEGUARDS VIA EVENT GENERATION, INTEGRATION, AND INTERPRETATION

    SciTech Connect (OSTI)

    Humberto E. Garcia; Wen-Chiao Lin; Tae-Sic Yoo

    2010-07-01

    There is a recognized safeguards benefit from using process monitoring (PM) on nuclear facilities to complement nuclear materials accountancy. We introduce a model-based approach for PM in which the assessment regarding the state of the monitored system is conducted at a system-centric level. The proposed architecture integrates both time-driven and event-driven data integration and analysis for decision-making. While the time-driven layers of the proposed architecture encompass more traditional PM methods based on time series data and analysis, the event-driven layers encompass operation monitoring methods based on discrete event data integration and analysis. By integrating process- and operation-related information and methodologies within an unified modeling and monitoring framework that includes not only current but also past plant behaviors, the task of anomaly detection is greatly improved because this decision-making approach can benefit from not only known time-series relationships among measured signals but also from known event sequence relationships among generated events. Building from the proposed system-centric PM architecture, we briefly introduce methods that can be used to implement its different components. The application of the proposed approach is then demonstrated via simulation experiments.

  7. Evaluation of the International Atomic Energy Agency (IAEA) Safeguards Analytical Laboratory quality assurance program

    SciTech Connect (OSTI)

    Pietri, C.E.; Bracey, J.T.

    1985-02-01

    Destructive analysis is used by the International Atomic Energy Agency (IAEA) through its Safeguards Analytical Laboratory (SAL) to verify, in part, the inventory of nuclear materials at nuclear facilities. The reliability and quality of these meassurements must be assured in a systematic manner. The Division of Safeguards Evaluation, IAEA, required assistance in developing and implementing the quality assurance measures for the analytical procedures used in the destructive analysis of these safeguards samples. To meet these needs an ISPO POTAS Task D.53 was instituted in which consultants would review with IAEA staff the procedures used (or proposed) at SAL for the destructive analysis of safeguards samples and the statistical evaluation of the resulting measurement data at Headquarters. The procedures included analytical methods, qualtiy control measures, and the treatment of data from these activities. Based on this review, modifications to the system, if required, would be recommended which would provide routine assurance to management that these procedures are functioning properly to achieve safeguards objectives. In the course of this review, the sample handling procedures, measurement control activities, analytical methods, reference materials, calibration procedures, statistical analysis of data, and data management system were studied and evaluated. The degree to which SAL (as a total system) achieved laboratory quality assurance was assessed by comparison to accepted standards of quality assurance. 22 refs., 1 fig.

  8. Lessons Learned from the Development of an Example Precision Information Environment for International Safeguards

    SciTech Connect (OSTI)

    Gastelum, Zoe N.; Henry, Michael J.; Burtner, IV, E. R.; Doehle, J. R.; Hampton, S. D.; La Mothe, R. R.; Nordquist, P. L.; Zarzhitsky, D. V.

    2014-12-01

    The International Atomic Energy Agency (IAEA) is interested in increasing capabilities of IAEA safeguards inspectors to access information that would improve their situational awareness on the job. A mobile information platform could potentially provide access to information, analytics, and technical and logistical support to inspectors in the field, as well as providing regular updates to analysts at IAEA Headquarters in Vienna or at satellite offices. To demonstrate the potential capability of such a system, Pacific Northwest National Laboratory (PNNL) implemented a number of example capabilities within a PNNL-developed precision information environment (PIE), and using a tablet as a mobile information platform. PNNL’s safeguards proof-of-concept PIE intends to; demonstrate novel applications of mobile information platforms to international safeguards use cases; demonstrate proof-of-principle capability implementation; and provide “vision” for capabilities that could be implemented. This report documents the lessons learned from this two-year development activity for the Precision Information Environment for International Safeguards (PIE-IS), describing the developed capabilities, technical challenges, and considerations for future development, so that developers working to develop a similar system for the IAEA or other safeguards agencies might benefit from our work.

  9. Safeguards by design - industry engagement for new uranium enrichment facilities in the United States

    SciTech Connect (OSTI)

    Demuth, Scott F; Grice, Thomas; Lockwood, Dunbar

    2010-01-01

    The United States Department of Energy's (DOE's) Office of Nonproliferation and International Security (NA-24) has initiated a Safeguards by Design (SBD) effort to encourage the incorporation of international (IAEA) safeguards features early in the design phase of a new nuclear facility in order to avoid the need to redesign or retrofit the facility at a later date. The main goals of Safeguards by Design are to (1) make the implementation of international safeguards at new civil nuclear facilities more effective and efficient, (2) avoid costly and time-consuming re-design work or retrofits at such facilities and (3) design such facilities in a way that makes proliferation as technically difficult, as time-consuming, and as detectable as possible. The U.S. Nuclear Regulatory Commission (NRC) has recently hosted efforts to facilitate the use of Safeguards by Design for new uranium enrichment facilities currently being planned for construction in the U.S. While SBD is not a NRC requirement, the NRC is aiding the implementation of SBD by coordinating discussions between DOE's NA-24 and industry's facility design teams. More specifically, during their normal course of licensing discussions the NRC has offered industry the opportunity to engage with NA-24 regarding SBD.

  10. Behavior of 241Am in fast reactor systems - a safeguards perspective

    SciTech Connect (OSTI)

    Beddingfield, David H; Lafleur, Adrienne M

    2009-01-01

    Advanced fuel-cycle developments around the world currently under development are exploring the possibility of disposing of {sup 241}Am from spent fuel recycle processes by burning this material in fast reactors. For safeguards practitioners, this approach could potentially complicate both fresh- and spent-fuel safeguards measurements. The increased ({alpha},n) production in oxide fuels from the {sup 241}Am increases the uncertainty in coincidence assay of Pu in MOX assemblies and will require additional information to make use of totals-based neutron assay of these assemblies. We have studied the behavior of {sup 241}Am-bearing MOX fuel in the fast reactor system and the effect on neutron and gamma-ray source-terms for safeguards measurements. In this paper, we will present the results of simulations of the behavior of {sup 241}Am in a fast breeder reactor system. Because of the increased use of MOX fuel in thermal reactors and advances in fuel-cycle designs aimed at americium disposal in fast reactors, we have undertaken a brief study of the behavior of americium in these systems to better understand the safeguards impacts of these new approaches. In this paper we will examine the behavior of {sup 241}Am in a variety of nuclear systems to provide insight into the safeguards implications of proposed Am disposition schemes.

  11. Coupling a transient solvent extraction module with the separations and safeguards performance model.

    SciTech Connect (OSTI)

    DePaoli, David W.; Birdwell, Joseph F.; Gauld, Ian C.; Cipiti, Benjamin B.; de Almeida, Valmor F.

    2009-10-01

    A number of codes have been developed in the past for safeguards analysis, but many are dated, and no single code is able to cover all aspects of materials accountancy, process monitoring, and diversion scenario analysis. The purpose of this work was to integrate a transient solvent extraction simulation module developed at Oak Ridge National Laboratory, with the Separations and Safeguards Performance Model (SSPM), developed at Sandia National Laboratory, as a first step toward creating a more versatile design and evaluation tool. The SSPM was designed for materials accountancy and process monitoring analyses, but previous versions of the code have included limited detail on the chemical processes, including chemical separations. The transient solvent extraction model is based on the ORNL SEPHIS code approach to consider solute build up in a bank of contactors in the PUREX process. Combined, these capabilities yield a more robust transient separations and safeguards model for evaluating safeguards system design. This coupling and initial results are presented. In addition, some observations toward further enhancement of separations and safeguards modeling based on this effort are provided, including: items to be addressed in integrating legacy codes, additional improvements needed for a fully functional solvent extraction module, and recommendations for future integration of other chemical process modules.

  12. Alternative materials to cadmium for neutron absorbers in safeguards applications

    SciTech Connect (OSTI)

    Freeman, Corey R [Los Alamos National Laboratory; Geist, William H [Los Alamos National Laboratory; West, James D [Los Alamos National Laboratory

    2009-01-01

    Cadmium is increasingly difficult to use in safeguards applications because of rising cost and increased safety regulations. This work examines the properties of two materials produced by Ceradyne, inc. that present alternatives to cadmium for neutron shielding. The first is an aluminum metal doped with boron and the second is a boron carbide powder, compressed into a ceramic. Both are enriched in the {sup 10}B isotope. Two sheets of boron doped aluminum (1.1 mm and 5.2mm thick) and one sheet of boron carbide (8.5mm thick) were provided by Ceradyne for testing. An experiment was designed to test the neutron absorption capabilities of these three sheets against two different thicknesses of cadmium (0.6mm and 1.6mm thick). The thinner piece of aluminum boron alloy (1.1mm) performed as well as the cadmium pieces at absorbing neutrons. The thicker aluminum-boron plate provided more shielding than the cadmium sheets and the boron carbide performed best by a relatively large margin. Monte Carlo N-Particle eXtended (MCNPX) transport code modeling of the experiment was performed to provide validaLed computational tools for predicting the behavior of systems in which these materials may be incorporated as alternatives to cadmium. MCNPX calculations predict that approximately 0.17mm of the boron carbide is equivalent to 0.6mm of cadmium. There are drawbacks to these materials that need to be noted when considering using them as replacements for cadmium. Notably, they may need to be thicker than cadmium, and are not malleable, requiring machining to fit any curved forms.

  13. Safeguards summary event list (SSEL), January 1, 1990--December 31, 1995

    SciTech Connect (OSTI)

    1996-07-01

    The Safeguards Summary Event List (SSEL), Vol. 2, Rev. 4, provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the U.S. Nuclear Regulatory Commission (NRC) which occurred and were reported from January 1, 1990, rough December 31, 1995. Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of Bomb-related, Intrusion, Missing and/or Allegedly Stolen, Transportation-related, Tampering/Vandalism, Arson, Firearms, Radiological Sabotage, Nonradiological Sabotage, and Miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels.

  14. Safeguards Summary Event List (SSEL), January 1, 1990--December 31, 1996, Vol. 2, Rev. 5

    SciTech Connect (OSTI)

    1997-07-01

    The Safeguards Summary Event List (SSEL), Vol. 2, Rev. 5, provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC) which occurred and were reported from January 1, 1990, through December 31, 1996. Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of Bomb-related, Intrusion, Missing and/or Allegedly Stolen, Transportation-related, Tampering/Vandalism, Arson, Firearms, Radiological Sabotage, Nonradiological Sabotage, and Miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels.

  15. Safeguards Measurement Evaluation Program nuclear materials measurement data: Phase 1: Final report, 1985 through 1986

    SciTech Connect (OSTI)

    Cacic, C.G.

    1988-08-01

    The New Brunswick Laboratory has been tasked by the US Department of Energy Office of Safeguards and Security to assess and evaluate the adequacy of measurement technology as applied to materials accounting in US Department of Energy nuclear facilities. The Safeguards Measurement Evaluation Program was developed as a means to monitor and evaluate the quality and effectiveness of accounting measurements by site, material balance area, or unit process. Phase 1 of the Safeguards Measurement Evaluation Program, initiated during 1985, involved evaluation of the primary accountability measurement methods at six US Department of Energy Defense Programs facilities. Resulting data are presented and evaluated as indicators of current state-of-the-practice accountability measurement methodology, deficiencies in materials accounting practices, and areas for possible assistance in upgrading measurement capabilities. 22 figs., 5 tabs.

  16. Implementation of IAEA safeguards at the Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    Giacomini, J.J.; Finleon, C.A.; Larsen, R.K.; Lucas, M.; Langner, D.

    1995-07-01

    When President Clinton spoke to the United Nations General Assembly in September 1993, he offered to place US excess defense nuclear material under International Atomic Energy Agency (IAEA) safeguards, before the next Nuclear Nonproliferation Treaty (NPT) Extension Conference. This set in motion a flurry of activities at three DOE facilities, including Rocky Flats Environmental Technology Site (Site). With general guidance from DOE Headquarters, the facility selected a suitable storage area, identified appropriate materials, and acquired the necessary instrumentation to implement full-scale IAEA safeguards on excess plutonium oxide.

  17. Safeguards at Gas Centrifuge Enrichment Plants: Why is Iran a Threat?

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Technical Report: Safeguards at Gas Centrifuge Enrichment Plants: Why is Iran a Threat? Citation Details In-Document Search Title: Safeguards at Gas Centrifuge Enrichment Plants: Why is Iran a Threat? Authors: Boyer, Brian D. [1] + Show Author Affiliations Los Alamos National Laboratory [Los Alamos National Laboratory Publication Date: 2014-06-25 OSTI Identifier: 1136096 Report Number(s): LA-UR-14-24695 DOE Contract Number: AC52-06NA25396 Resource Type:

  18. Safeguards on uranium ore concentrate? the impact of modern mining and milling process

    SciTech Connect (OSTI)

    Francis, Stephen

    2013-07-01

    Increased purity in uranium ore concentrate not only raises the question as to whether Safeguards should be applied to the entirety of uranium conversion facilities, but also as to whether some degree of coverage should be moved back to uranium ore concentrate production at uranium mining and milling facilities. This paper looks at uranium ore concentrate production across the globe and explores the extent to which increased purity is evident and the underlying reasons. Potential issues this increase in purity raises for IAEA's strategy on the Starting Point of Safeguards are also discussed.

  19. Initial Evaluation of a New Electromechanical Cooler for Safeguards Applications

    SciTech Connect (OSTI)

    Coleman, RL

    2002-10-21

    The use of liquid nitrogen (LN{sub 2}) constitutes the current state of the art in cryogenic cooling for high-purity germanium (HPGe) detectors, which are widely used for {gamma}-ray and characteristic X-ray spectroscopy because of their excellent energy discrimination. Use of LN{sub 2} requires a liquid nitrogen supply, cumbersome storage tanks and plumbing, and the frequent attention of personnel to be sure that nitrogen levels are sufficient to maintain the detectors at a sufficiently low operating temperature. Safety hazards also are associated with the use of LN{sub 2}, both because of the potential for severe frostbite on exposure to skin and because it displaces ambient oxygen when it evaporates in closed spaces. Existing electromechanical coolers have, until now, been more expensive to procure and maintain than LN{sub 2} systems. Performance and reliability have also been serious issues because of microphonic degradation of photon energy peak resolution and cooler failures due to compressor oil becoming entrained in the refrigerant. This report describes the results of tests of a new HPGe detector cooling technology, the PerkinElmer ORTEC{reg_sign} Products X-Cooler{trademark} that, according to the manufacturer, significantly reduces the lifetime cost of the cooling system without degradation of the output signal. The manufacturer claims to have overcome cost, performance and reliability problems of older-generation electromechanical coolers, but the product has no significant history of use, and this project is the first independent evaluation of its performance for Total cost savings for the DOE and other agencies that use HPGe systems extensively for safeguards monitoring is expected to be quite significant if the new electromechanical cooler technology is shown to be reliable and if performance characteristics indicate its usefulness for this application. The technology also promises to make HPGe monitoring, characterization and detection available for unattended or covert operation and in remote or inaccessible locations where the unavailability of LN{sub 2} and signal degradation from existing mechanical coolers prevent its use at the present time.

  20. DEVELOPMENT OF AN ADHESIVE CANDLE FILTER SAFEGUARD DEVICE

    SciTech Connect (OSTI)

    John P. Hurley; Ann K. Henderson; Jan W. Nowok; Michael L. Swanson

    2002-01-01

    In order to reach the highest possible efficiencies in a coal-fired turbine-based power system, the turbine should be directly fired with the products of coal conversion. Two main types of systems employ these turbines: those based on pressurized fluidized-bed combustors and those based on integrated gasification combined cycles. In both systems, suspended particulates must be cleaned from the gas stream before it enters the turbine so as to prevent fouling and erosion of the turbine blades. To produce the cleanest gas, barrier filters are being developed and are in use in several facilities. Barrier filters are composed of porous, high-temperature materials that allow the hot gas to pass but collect the particulates on the surface. The three main configurations of the barrier filters are candle, cross-flow, and tube filters. Both candle and tube filters have been tested extensively. They are composed of coarsely porous ceramic that serves as a structural support, overlain with a thin, microporous ceramic layer on the dirty gas side that serves as the primary filter surface. They are highly efficient at removing particulate matter from the gas stream and, because of their ceramic construction, are resistant to gas and ash corrosion. However, ceramics are brittle and individual elements can fail, allowing particulates to pass through the hole left by the filter element and erode the turbine. Preventing all failure of individual ceramic filter elements is not possible at the present state of development of the technology. Therefore, safeguard devices (SGDs) must be employed to prevent the particulates streaming through occasional broken filters from reaching the turbine. However, the SGD must allow for the free passage of gas when it is not activated. Upon breaking of a filter, the SGD must either mechanically close or quickly plug with filter dust to prevent additional dust from reaching the turbine. Production of a dependable rapidly closing autonomous mechanical device at high temperatures in a dusty gas stream is difficult because of problems with materials corrosion, dust leakage, and detection of filter failure. Therefore, the Energy & Environmental Research Center is using its knowledge of the factors that make filter dust sticky at gas filtration temperatures to make a simple and inexpensive SGD that employs an adhesive yet thermodynamically stable coating on a highly porous ceramic substrate. The SGDs are placed on top of individual candle filters at the filtered gas exit. Upon failure of the filter, the dirty gas flows through the SGD where the adhesive surface rapidly and permanently traps dust particles, causing the device to plug and prevent the dust from reaching the turbine.

  1. Integrated Safeguards and Security Management Self-Assessment 2004

    SciTech Connect (OSTI)

    Lunford, Dan; Ramsey, Dwayne

    2005-04-01

    In 2002 Ernest Orlando Lawrence Berkeley National Laboratory deployed the first Integrated Safeguards and Security Management (ISSM) Self-Assessment process, designed to measure the effect of the Laboratory's ISSM efforts. This process was recognized by DOE as a best practice and model program for self-assessment and training. In 2004, the second Self-Assessment was launched. The cornerstone of this process was an employee survey that was designed to meet several objectives: (1) Ensure that Laboratory assets are protected. (2) Provide a measurement of the Laboratory's current security status that can be compared against the 2002 Self-Assessment baseline. (3) Educate all Laboratory staff about security responsibilities, tools, and practices. (4) Provide security staff with feedback on the effectiveness of security programs. (5) Provide line management with the information they need to make informed decisions about security. This 2004 Self Assessment process began in July 2004 with every employee receiving an information packet and instructions for completing the ISSM survey. The Laboratory-wide survey contained questions designed to measure awareness and conformance to policy and best practices. The survey response was excellent--90% of Berkeley Lab employees completed the questionnaire. ISSM liaisons from each division followed up on the initial survey results with individual employees to improve awareness and resolve ambiguities uncovered by the questionnaire. As with the 2002 survey, the Self-Assessment produced immediate positive results for the ISSM program and revealed opportunities for longer-term corrective actions. Results of the questionnaire provided information for organizational profiles and an institutional summary. The overall level of security protection and awareness was very high--often above 90%. Post-survey work by the ISSM liaisons and line management consistently led to improved awareness and metrics, as shown by a comparison of profiles at the end of phase one (August 6, 2004) and phase two (November 1, 2004). The Self-Assessment confirmed that classified information is not held or processed at Berkeley Lab. The survey results also identified areas where increased employee knowledge and awareness of Laboratory policy would be beneficial, the two most prominent being password usage and wireless network service. Line management will be able to determine additional corrective actions based on the results of the Self-Assessment. Future assessments will raise the ratings bar for some existing program elements and add new elements to stimulate further improvements in Laboratory security.

  2. Manual for Nuclear Materials Management and Safeguards System Reporting and Data Submission

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

    2003-08-19

    The manual provides detailed instructions for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE M 474.1-2. Canceled by DOE M 470.4-6.

  3. Analysis of the effectiveness of gas centrifuge enrichment plants advanced safeguards

    SciTech Connect (OSTI)

    Boyer, Brian David; Erpenbeck, Heather H; Miller, Karen A; Swinjoe, Martyn T; Ianakiev, Kiril D; Marlow, Johnna B

    2010-01-01

    Current safeguards approaches used by the International Atomic Energy Agency (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 highly enriched uranium (HEU) production with adequate detection 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 235U enrichment of declared UF6 containers used in the process of enrichment at GCEPs. This paper contains an analysis of possible improvements in unattended and attended NDA systems including process monitoring and possible on-site destructive assay (DA) of samples that could reduce the uncertainty of the inspector's measurements. These improvements could reduce the difference between the operator's and inspector's measurements providing more effective and efficient IAEA GCEPs safeguards. We also explore how a few advanced safeguards systems could be assembled for unattended operation. The analysis will focus on how unannounced inspections (UIs), and the concept of information-driven inspections (IDS) can affect probability of detection of the diversion of nuclear materials when coupled to new GCEPs safeguards regimes augmented with unattended systems.

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

    ScienceCinema (OSTI)

    Thomas D'Agostino

    2010-09-01

    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.

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

    SciTech Connect (OSTI)

    Pepper S. E.; .; Worrall, L.; Pickett, C.; Bachner, K.; Queirolo, A.

    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 participants 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.

  6. The U.S. Support Program to IAEA Safeguards - Destructive Analysis

    SciTech Connect (OSTI)

    Hoffheins,B.

    2008-07-13

    The U.S. Support Program (USSP) to IAEA Safeguards priority of destructive analysis is aimed at strengthening the IAEA's ability to use destructive analysis as a safeguards tool. IAEA inspectors bring back nuclear and environmental samples from inspections, which are first cataloged by the IAEA and then analyzed by a network of laboratories located in many Member States and the IAEA's own Safeguards Analytical Laboratory in Seibersdorf, Austria. Historically, the USSP was instrumental in introducing environmental sampling techniques to the IAEA in order to enhance its understanding of material processing activities conducted at nuclear facilities. The USSP has also worked with the IAEA to improve understanding of measurement uncertainty and measurement quality, incorporate new and improved analytical methods, and purchase analytical and computer equipment. Recent activities include a temporary increase in analysis of environmental samples using secondary ion mass spectrometry and provision of a cost-free expert to restore secondary ion mass spectroscopy laboratory functionality and to modernize the IAEA's Safeguards Analytical Laboratory Information System.

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

    SciTech Connect (OSTI)

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

    2015-02-23

    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 fully 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 approach may lead to more proliferation resistant and physically secure design features for SMRs.

  8. Performance, Market and Manufacturing Constraints relevant to...

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

    Performance, Market and Manufacturing Constraints relevant to the Industrialization of Thermoelectric Devices Market pricing of thermoelectric raw materials and processing, cost of ...

  9. Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426

    SciTech Connect (OSTI)

    Hayes, Timothy; Nelson, Roger

    2012-07-01

    The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an over-pack container, similar to the pipe component, called the criticality control over-pack, which will significantly enhance the efficiency of disposal. Hundreds of shipments of transuranic SNM, suitably packaged to meet WIPP waste acceptance criteria and with safeguards terminated have been successfully emplaced at WIPP (primarily from the Rocky Flats site clean-up) since WIPP opened. DOE expects that thousands more may eventually result from SNM consolidation efforts throughout the weapons complex. (authors)

  10. Microsoft Word - Final Nuclear Materials Management and Safeguards System Users Guide 2 4-3-13.docx

    National Nuclear Security Administration (NNSA)

    Nuclear Materials Management and Safeguards Users Guide National Nuclear Security Administration Office of Nuclear Materials Integration Office of Nuclear Materials Integration Nuclear Materials Management and Safeguards System (NMMSS) Users Guide-Rev. 2.0 Prepared by: Department of Energy National Nuclear Security Administration Nuclear Materials Integration - NA-73 April 2013 Xavier Ascanio Office of Nuclear Materials Integration Nuclear Materials Management and 73 NMMSS User Guide 2.0 April

  11. Next Generation Safeguards Initiative Efforts at Los Alamos National Laboratory: Developing Our Human Capital FY2015

    SciTech Connect (OSTI)

    Stevens, Rebecca S.; Hawkins Erpenbeck, Heather

    2015-10-13

    This report documents the accomplishments of the Safeguards HCD Fiscal Year 2015 (FY15) Project Work Plan, highlighting LANL’s work as well as the accomplishments of our NGSI-sponsored students, graduate and postdoctoral fellows, and mid-career professionals during this past year. While fiscal year 2015 has been a year of transition in the Human Capital Development area for LANL, we are working to revitalize our efforts to promote and develop Human Capital in Safeguards and Non-proliferation and are looking forward to implementing new initiatives in the coming fiscal year and continuing to transition the knowledge of staff who have been on assignment at IAEA and Headquarters to improve our support to HCD.

  12. New Prototype Safeguards Technology Offers Improved Confidence and Automation for Uranium Enrichment Facilities

    SciTech Connect (OSTI)

    Brim, Cornelia P.

    2013-04-01

    An important requirement for the international safeguards community is the ability to determine the enrichment level of uranium in gas centrifuge enrichment plants and nuclear fuel fabrication facilities. This is essential to ensure that countries with nuclear nonproliferation commitments, such as States Party to the Nuclear Nonproliferation Treaty, are adhering to their obligations. However, current technologies to verify the uranium enrichment level in gas centrifuge enrichment plants or nuclear fuel fabrication facilities are technically challenging and resource-intensive. NNSA’s Office of Nonproliferation and International Security (NIS) supports the development, testing, and evaluation of future systems that will strengthen and sustain U.S. safeguards and security capabilities—in this case, by automating the monitoring of uranium enrichment in the entire inventory of a fuel fabrication facility. One such system is HEVA—hybrid enrichment verification array. This prototype was developed to provide an automated, nondestructive assay verification technology for uranium hexafluoride (UF6) cylinders at enrichment plants.

  13. Safeguard By Design Lessons Learned from DOE Experience Integrating Safety into Design

    SciTech Connect (OSTI)

    Hockert, John; Burbank, Roberta L.

    2010-04-13

    This paper identifies the lessons to be learned for the institutionalization of Safeguards by Design (SBD) from the Department of Energy (DOE) experience developing and implementing DOE-STD-1189-2008, Integration of Safety into the Design Process. The experience is valuable because of the similarity of the challenges of integrating safety and safeguards into the design process. The paper reviews the content and development of DOE-STD-1189-2008 from its initial concept in January 2006 to its issuance in March 2008. Lessons learned are identified in the areas of the development and structure of requirements for the SBD process; the target audience for SBD requirements and guidance, the need for a graded approach to SBD, and a possible strategy for development and implementation of SBD within DOE.

  14. Safeguards and Security Survey and Self-Assessment Planning, Conduct, and Reporting

    Energy Savers [EERE]

    1217-2016 February 2016 DOE STANDARD SAFEGUARDS AND SECURITY SURVEY AND SELF-ASSESSMENT PLANNING, CONDUCT, AND REPORTING U.S. Department of Energy Washington, D.C. 20585 AREA SANS DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1217-2016 ii This Page Intentionally Left Blank DOE-STD-1217-2016 iii TABLE OF CONTENTS FOREWORD........................................................................................................................... vi 1.

  15. Voluntary Offer Safeguards Agreement and Additional Protocol with the International Atomic Energy Agency

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

    2006-12-15

    The Order defines requirements for Department of Energy (DOE) compliance with the Agreement between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States, the Protocol to the Agreement, the Additional Protocol to the Agreement, and the Subsidiary Arrangements to the Agreement and Additional Protocol. Supersedes DOE O 142.2. Admin Chg 1, dated 6-27-13, Supersedes DOE O 142.1A. Certified 12-3-14.

  16. Safeguard Application Options for the Laser-Based Item Monitoring System (LBIMS)

    SciTech Connect (OSTI)

    Laughter, Mark D

    2008-10-01

    Researchers at Oak Ridge National Laboratory (ORNL) are developing a Laser-Based Item Monitoring System (LBIMS) for advanced safeguards at nuclear facilities. LBIMS uses a low-power laser transceiver to monitor the presence and position of items with retroreflective tags. The primary advantages of LBIMS are its scalability to continuously monitor a wide range of items, its ability to operate unattended, its low cost of implementation, and its inherent information security due to its line-of-sight and non-broadcasting operation. The primary proposed safeguard application of LBIMS is described in its name: item monitoring. LBIMS could be implemented in a storage area to continuously monitor containers of nuclear material and the area in which they are stored. The system could be configured to provide off-site notification if any of the containers are moved or removed or if the area is accessed. Individual tags would be used to monitor storage containers, and additional tags could be used to record information regarding secondary storage units and room access. The capability to register small changes in tag position opens up the possibility of several other uses. These include continuously monitoring piping arrangements for design information verification or recording equipment positions for other safeguards systems, such as tracking the opening and closing of autoclaves as part of a cylinder tracking system or opening and closing valves on a sample or product take-off line. Combined with attribute tags, which transmit information from any kind of sensor by modulating the laser signal, LBIMS provides the capability to wirelessly and securely collect safeguards data, even in areas where radio-frequency or other wireless communication methods are not practicable. Four application types are described in this report: static item monitoring, in-process item monitoring with trigger tags, multi-layered integration with trigger tags, and line-of-sight data transfer with attribute tags. Field trials for each of these applications are described.

  17. Plutonium Measurements with a Fast-Neutron Multiplicity Counter for Nuclear Safeguards Applications

    SciTech Connect (OSTI)

    Jennifer L. Dolan; Marek Flaska; Alexis Poitrasson-Riviere; Andreas Enqvist; Paolo Peerani; David L. Chichester; Sara A. Pozzi

    2014-11-01

    Measurements were performed at the Joint Research Centre in Ispra, Italy to field test a fast-neutron multiplicity counter developed at the University of Michigan. The measurements allowed the illustration of the system’s photon discrimination abilities, efficiency when measuring neutron multiplicity, ability to characterize 240Pueff mass, and performance relative to a currently deployed neutron coincidence counter. This work is motivated by the need to replace and improve upon 3He neutron detection systems for nuclear safeguards applications.

  18. Voluntary Offer Safeguards Agreement and Additional Protocol with the International Atomic Energy Agency

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

    2006-12-15

    The Order defines requirements for Department of Energy (DOE) compliance with the Agreement between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States, the Protocol to the Agreement, the Additional Protocol to the Agreement, and the Subsidiary Arrangements to the Agreement and Additional Protocol. Cancels DOE O 142.2. Admin Chg 1, 6-27-13.

  19. Next GeNeratioN SafeGuardS iNitiative

    National Nuclear Security Administration (NNSA)

    Next GeNeratioN SafeGuardS iNitiative 2 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor Battelle Memorial Institute, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use

  20. Commission. The Nuclear Materials Management and Safeguards System (NMMSS) 2014 Annual Users

    National Nuclear Security Administration (NNSA)

    April 2014 NMMSS News is sponsored by the Department of Energy and the Nuclear Regulatory Commission. The Nuclear Materials Management and Safeguards System (NMMSS) 2014 Annual Users Training Meeting will be held May 12-15, 2014, in Denver, Colorado. NMMSS is the U.S. Government's official information system containing current and historical accounting data and other related nuclear material information collected from both government and commercial nuclear facilities. The data serve a critical

  1. Under-sodium viewing technology for improvement of fast-reactor safeguards

    SciTech Connect (OSTI)

    Beddingfield, David H; Gerhart, Jeremy J; Kawakubo, Yoko

    2009-01-01

    The current safeguards approach for fast reactors relies exclusively on maintenance of continuity of knowledge to track the movement of fuel assemblies through these facilities. The remote handling of fuel assemblies, the visual opacity of the liquid metal coolant. and the chemical reactivity of sodium all combine and result in significant limitations on the available options to verify fuel assembly identification numbers or the integrity of these assemblies. These limitations also serve to frustrate attempts to restore the continuity-of-knowledge in instances where the information is under a variety of scenarios. The technology of ultrasonic under-sodium viewing offers new options to the safeguards community for recovering continuity-of-knowledge and applying more traditional item accountancy to fast reactor facilities. We have performed a literature review to investigate the development of under-sodium viewing technologies. In this paper we will summarize our findings and report the state of development of this technology and we will present possible applications to the fast reactor system to improve the existing safeguards approach at these reactors and in future fast reactors.

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

    SciTech Connect (OSTI)

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

    2009-11-01

    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 Agency 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.

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

    SciTech Connect (OSTI)

    Ku, J.H.; Choung, W.M.; You, G.S.; Moon, S.I.; Park, S.H.; Kim, H.D.

    2013-07-01

    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 evaluation 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.

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

    SciTech Connect (OSTI)

    Kovacic, Don N.; Stewart, Scott; Erickson, Alexa R.; Ford, Kerrie D.; Mladineo, Stephen V.

    2015-07-15

    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 need 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, or planning to implement, safety, security, and safeguards in their programs. The idea is to capture current knowledge and thinking on this topic and to identify common themes in organizations and management. It will also document the most commonly held ideas and perception (and misperceptions) of what it means to manage interfaces and take advantage of synergies for operating nuclear facilities and those that are building their infrastructures. It is desired that the results of this paper will inform the current discourse on this topic with some quantitative data and identify any general trends in understanding.

  5. Gamma-Ray Library and Uncertainty Analysis: Passively Emitted Gamma Rays Used in Safeguards Technology

    SciTech Connect (OSTI)

    Parker, W

    2009-09-18

    Non-destructive gamma-ray analysis is a fundamental part of nuclear safeguards, including nuclear energy safeguards technology. Developing safeguards capabilities for nuclear energy will certainly benefit from the advanced use of gamma-ray spectroscopy as well as the ability to model various reactor scenarios. There is currently a wide variety of nuclear data that could be used in computer modeling and gamma-ray spectroscopy analysis. The data can be discrepant (with varying uncertainties), and it may difficult for a modeler or software developer to determine the best nuclear data set for a particular situation. To use gamma-ray spectroscopy to determine the relative isotopic composition of nuclear materials, the gamma-ray energies and the branching ratios or intensities of the gamma-rays emitted from the nuclides in the material must be well known. A variety of computer simulation codes will be used during the development of the nuclear energy safeguards, and, to compare the results of various codes, it will be essential to have all the {gamma}-ray libraries agree. Assessing our nuclear data needs allows us to create a prioritized list of desired measurements, and provides uncertainties for energies and especially for branching intensities. Of interest are actinides, fission products, and activation products, and most particularly mixtures of all of these radioactive isotopes, including mixtures of actinides and other products. Recent work includes the development of new detectors with increased energy resolution, and studies of gamma-rays and their lines used in simulation codes. Because new detectors are being developed, there is an increased need for well known nuclear data for radioactive isotopes of some elements. Safeguards technology should take advantage of all types of gamma-ray detectors, including new super cooled detectors, germanium detectors and cadmium zinc telluride detectors. Mixed isotopes, particularly mixed actinides found in nuclear reactor streams can be especially challenging to identify. The super cooled detectors have a marked improvement in energy resolution, allowing the possibility of deconvolution of mixtures of gamma rays that was unavailable with high purity germanium detectors. Isotopic analysis codes require libraries of gamma rays. In certain situations, isotope identification can be made in the field, sometimes with a short turnaround time, depending on the choice of detector and software analysis package. Sodium iodide and high purity germanium detectors have been successfully used in field scenarios. The newer super cooled detectors offer dramatically increased resolution, but they have lower efficiency and so can require longer collection times. The different peak shapes require software development for the specific detector type and field application. Libraries can be tailored to specific scenarios; by eliminating isotopes that are certainly not present, the analysis time may be shortened and the accuracy may be increased. The intent of this project was to create one accurate library of gamma rays emitted from isotopes of interest to be used as a reliable reference in safeguards work. All simulation and spectroscopy analysis codes can draw upon this best library to improve accuracy and cross-code consistency. Modeling codes may include MCNP and COG. Gamma-ray spectroscopy analysis codes may include MGA, MGAU, U235 and FRAM. The intent is to give developers and users the tools to use in nuclear energy safeguards work. In this project, the library created was limited to a selection of actinide isotopes of immediate interest to reactor technology. These isotopes included {sup 234-238}U, {sup 237}Np, {sup 238-242}Pu, {sup 241,243}Am and {sup 244}Cm. These isotopes were examined, and the best of gamma-ray data, including line energies and relative strengths were selected.

  6. Report on the US Program of Technical Assistance to Safeguards of the International Atomic Energy Agency (POTAS)

    SciTech Connect (OSTI)

    Not Available

    1981-05-01

    This document summarizes the work done under the US Program of Technical Assistance to IAEA Safeguards (POTAS), providing the US Government, IAEA, and others with a short review of the progress made in the program since its inception. Becaue of the size and complexity of the program, only major accomplishments are presented. These are grouped under the following categories: (1) equipment and standard which cover assay of irradiated and unirradiated nuclear materials, automatic data processing, and physical standards; (2) experts who are involved in technology transfer, training, system design, and safeguard information processing and analysis; (3) system studies which cover diversion hazard analysis, safeguards approaches and application, and inspection effort planning and forecasting; (4) techniques, procedures, and equipment evaluation; (5) training of IAEA inspectors and safeguards specialists from member states. The major achievement has been the provisions of safeguards equipment designed to be reliable, and tamper resistant, some of which have already been in use in the field by inspector or by IAEA staff members in Vienna. These are listed in a table. (AT)

  7. Evaluating Safeguards Benefits of Process Monitoring as compared with Nuclear Material Accountancy

    SciTech Connect (OSTI)

    Humberto Garcia; Wen-Chiao Lin; Reed Carlson

    2014-07-01

    This paper illustrates potential safeguards benefits that process monitoring (PM) may have as a diversion deterrent and as a complementary safeguards measure to nuclear material accountancy (NMA). This benefit is illustrated by quantifying the standard deviation associated with detecting a considered material diversion scenario using either an NMA-based method or a PM-based approach. To illustrate the benefits of PM for effective safeguards, we consider a reprocessing facility. We assume that the diversion of interest for detection manifests itself as a loss of Pu caused by abnormally operating a dissolver for an extended period to accomplish protracted diversion (or misdirection) of Pu to a retained (unconditioned) waste stream. For detecting the occurrence of this diversion (which involves anomalous operation of the dissolver), we consider two different data evaluation and integration (DEI) approaches, one based on NMA and the other based on PM. The approach based on PM does not directly do mass balance calculations, but rather monitors for the possible occurrence of anomaly patterns related to potential loss of nuclear material. It is thus assumed that the loss of a given mass amount of nuclear material can be directly associated with the execution of proliferation-driven activities that trigger the occurrence of an anomaly pattern consisting of series of events or signatures occurring at different unit operations and time instances. By effectively assessing these events over time and space, the PM-based DEI approach tries to infer whether this specific pattern of events has occurred and how many times within a given time period. To evaluate the goodness of PM, the 3 Sigma of the estimated mass loss is computed under both DEI approaches as function of the number of input batches processed. Simulation results are discussed.

  8. Monitoring, Controlling and Safeguarding Radiochemical Streams at Spent Fuel Reprocessing Facilities, Part 1: Optical Spectroscopic Methods

    SciTech Connect (OSTI)

    Bryan, Samuel A.; Levitskaia, Tatiana G.; Schwantes, Jon M.; Orton, Christopher R.; Peterson, James M.; Casella, Amanda J.

    2012-02-07

    Abstract: The International Atomic Energy Agency (IAEA) has established international safeguards standards for fissionable material at spent fuel reprocessing plants to ensure that significant quantities of weapons-useable nuclear material are not diverted from these facilities. For large throughput nuclear facilities, it is difficult to satisfy the IAEA safeguards accountancy goal for detection of abrupt diversion. Currently, methods to verify material control and accountancy (MC&A) at these facilities require time-consuming and resource-intensive destructive assay (DA). Leveraging new on-line non-destructive assay (NDA) process monitoring techniques in conjunction with the traditional and highly precise DA methods may provide an additional measure to nuclear material accountancy which would potentially result in a more timely, cost-effective and resource efficient means for safeguards verification at such facilities. By monitoring process control measurements (e.g. flowrates, temperatures, or concentrations of reagents, products or wastes), abnormal plant operations can be detected. Pacific Northwest National Laboratory (PNNL) is developing on-line NDA process monitoring technologies based upon gamma-ray and optical spectroscopic measurements to potentially reduce the time and resource burden associated with current techniques. The Multi-Isotope Process (MIP) Monitor uses gamma spectroscopy and multivariate analysis to identify off-normal conditions in process streams. The spectroscopic monitor continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major stable flowsheet reagents using UV-Vis, Near IR and Raman spectroscopy. Multi-variate analysis is also applied to the optical measurements in order to quantify concentrations of analytes of interest within a complex array of radiochemical streams. This paper will provide an overview of these methods and reports on-going efforts to develop and demonstrate the technologies. This paper is Part 1 of a two part series, and focuses on the optical spectroscopy based process monitoring methods.

  9. Notice of Intent to Revise DOE O 470.4B, Safeguards and Security Program

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

    - DOE Directives, Delegations, and Requirements O 470.4B, Notice of Intent to Revise DOE O 470.4B, Safeguards and Security Program by Diane Johnson The directive is proposed for revision to reflect the establishment by the Secretary of Energy of the Office of Environment, Health, Safety and Security (AU), and the Office of Security Officer positions and the Security Committee. The responsibilities section of the Order will be revised to include the Chief Security Officers and the Security

  10. All Other Editions Are Obsolete U.S. DEPARTMENT OF ENERGY SAFEGUARDS AND SECURITY SURVEY REPORT

    Energy Savers [EERE]

    4.1 (05-94) All Other Editions Are Obsolete U.S. DEPARTMENT OF ENERGY SAFEGUARDS AND SECURITY SURVEY REPORT OMB Control No. 1910-1800 1. Survey Type: 3. Facility Name: 4. A. Facility Code: B. RIS Code: 5. Survey Date(s): 8. Previous Survey Date(s): 6. Findings: 9. Unresolved Findings: 7. Composite Rating: 10. Previous Rating: 11. Ratings: Rate Each Item: S = SATISFACTORY M = MARGINAL U = UNSATISFACTORY DNA = DOES NOT APPLY A) PROGRAM MANAGEMENT Program Management and Administration Program

  11. Integrated safeguards and security for the INEL Special Isotope Separation Plant

    SciTech Connect (OSTI)

    Warner, G.F.; Zack, N.R.

    1990-06-12

    This paper describes the approach that was taken in developing safeguards and security design criteria to be used for the Special Isotope Separation (SIS) Production Plant. The US Department of Energy has postponed the construction of the SIS Production Plant that was to be built at the Idaho National Engineering Laboratory (INEL) site located near Idaho Falls, Idaho. The SIS Plant planned to isotopically enrich plutonium utilizing the Atomic Vapor Laser Isotope Separation (AVLIS) process developed at the Lawrence Livermore National Laboratory. Westinghouse Idaho Nuclear Co., Inc. as a prime contractor to the DOE Idaho Operations Office, was to operate the Plant.

  12. Passive Measurement of Organic-Scintillator Neutron Signatures for Nuclear Safeguards Applications

    SciTech Connect (OSTI)

    Jennfier L. Dolan; Eric C. Miller; Alexis C. Kaplan; Andreas Enqvist; Marek Flaska; Alice Tomanin; Paolo Peerani; David L. Chichester; Sara A. Pozzi

    2012-10-01

    At nuclear facilities, domestically and internationally, most measurement systems used for nuclear materials’ control and accountability rely on He-3 detectors. Due to resource shortages, alternatives to He-3 systems are needed. This paper presents preliminary simulation and experimental efforts to develop a fast-neutron-multiplicity counter based on liquid organic scintillators. This mission also provides the opportunity to broaden the capabilities of such safeguards measurement systems to improve current neutron-multiplicity techniques and expand the scope to encompass advanced nuclear fuels.

  13. Safeguarding a NWS International Enrichment Center as an Enriched Uranium Store

    SciTech Connect (OSTI)

    Curtis, Michael M.

    2008-03-31

    The operational and regulatory singularities of a multilateral facility designed to provide enriched uranium to a consortium of members may engender a new sub-category of safeguard criteria for the International Atomic Energy Agency (IAEA). This paper introduces the contingency of monitoring such a facility as a uranium storage center with cylinders containing low-enriched uranium (LEU) as the principal, and perhaps only, material open to verification. Accountancy and verification techniques will be proffered together with disparate means for maintaining continuity of knowledge (CoK) on verified stock.

  14. Select Generic Dry-Storage Pilot Plant Design for Safeguards and Security by Design (SSBD) per Used Fuel Campaign

    SciTech Connect (OSTI)

    Demuth, Scott Francis; Sprinkle, James K.

    2015-05-26

    As preparation to the year-end deliverable (Provide SSBD Best Practices for Generic Dry-Storage Pilot Scale Plant) for the Work Package (FT-15LA040501–Safeguards and Security by Design for Extended Dry Storage), the initial step was to select a generic dry-storage pilot plant design for SSBD. To be consistent with other DOE-NE Fuel Cycle Research and Development (FCR&D) activities, the Used Fuel Campaign was engaged for the selection of a design for this deliverable. For the work Package FT-15LA040501–“Safeguards and Security by Design for Extended Dry Storage”, SSBD will be initiated for the Generic Dry-Storage Pilot Scale Plant described by the layout of Reference 2. SSBD will consider aspects of the design that are impacted by domestic material control and accounting (MC&A), domestic security, and international safeguards.

  15. Near Real-Time Nondestructive Active Inspection Technologies Utilizing Delayed Îł-Rays and Neutrons for Advanced Safeguards

    SciTech Connect (OSTI)

    Hunt, Alan; Reedy, E. T.E.; Mozin, V.; Tobin, S. J.

    2015-02-12

    In this two year project, the research team investigated how delayed Îł-rays from short-lived fission fragments detected in the short interval between irradiating pulses can be exploited for advanced safeguards technologies. This program contained experimental and modeling efforts. The experimental effort measured the emitted spectra, time histories and correlations of the delayed Îł-rays from aqueous solutions and solid targets containing fissionable isotopes. The modeling effort first developed and benchmarked a hybrid Monte Carlo simulation technique based on these experiments. The benchmarked simulations were then extended to other safeguards scenarios, allowing comparisons to other advanced safeguards technologies and to investigate combined techniques. Ultimately, the experiments demonstrated the possible utility of actively induced delayed Îł-ray spectroscopy for fissionable material assay.

  16. Manual for Implementation of the Voluntary Offer Safeguards Agreement and Additional Protocol with the International Atomic Energy Agency

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

    1998-06-12

    This Manual provides detailed information for implementing the requirements of DOE O 142.2A, dated 12-15-06; the Agreement Between the United States of America and the International Atomic Energy Agency (IAEA) for the Application of Safeguards in the United States; the Original Protocol to the Agreement; the Additional Protocol to the Agreement signed by the United States and the IAEA on June 12, 1998; and the Interagency Procedures for the Implementation of the U.S.-IAEA Safeguards Agreement. No cancellation. Admin Chg 1, dated 6-27-13, supersedes DOE M 142.2-1. Certified 12-3-14.

  17. Manual for Implementation of the Voluntary Offer Safeguards Agreement and Additional Protocol with the International Atomic Energy Agency

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

    1998-06-12

    This Manual provides detailed information for implementing the requirements of DOE O 142.2A, dated 12-15-06; the Agreement Between the United States of America and the International Atomic Energy Agency (IAEA) for the Application of Safeguards in the United States; the Original Protocol to the Agreement; the Additional Protocol to the Agreement signed by the United States and the IAEA on June 12, 1998; and the Interagency Procedures for the Implementation of the U.S.-IAEA Safeguards Agreement. No cancellation. Admin Chg 1, 6-27-13

  18. Laboratory quality assurance and its role in the safeguards analytical laboratory evaluation (SALE) program

    SciTech Connect (OSTI)

    Delvin, W. L.; Pietri, C. E.

    1981-07-01

    Since the late 1960's, strong emphasis has been given to quality assurance in the nuclear industry, particularly to that part involved in nuclear reactors. This emphasis has had impact on the analytical chemistry laboratory because of the importance of analytical measurements in the certification and acceptance of materials used in the fabrication and construction of reactor components. Laboratory quality assurance, in which the principles of quality assurance are applied to laboratory operations, has a significant role to play in processing, fabrication, and construction programs of the nuclear industry. That role impacts not only process control and material certification, but also safeguards and nuclear materials accountability. The implementation of laboratory quality assurance is done through a program plan that specifies how the principles of quality assurance are to be applied. Laboratory quality assurance identifies weaknesses and deficiencies in laboratory operations and provides confidence in the reliability of laboratory results. Such confidence in laboratory measurements is essential to the proper evaluation of laboratories participating in the Safeguards Analytical Laboratory Evaluation (SALE) Program.

  19. Technical Cross-Cutting Issues for the Next Generation Safeguards Initiative's Spent Fuel Nondestructive Assay Project

    SciTech Connect (OSTI)

    Tobin, S. J.; Menlove, H. O.; Swinhoe, Martyn T.; Blanc, P.; Burr, T.; Evans, L. G.; Favalli, A.; Fensin, M. L.; Freeman, C. R.; Galloway, J.; Gerhart, J.; Rajasingam, A.; Rauch, E.; Sandoval, N. P.; Trellue, H.; Ulrich, T. J.; Conlin, J. L.; Croft, S.; Hendricks, John; Henzl, V.; Henzlova, D.; Eigenbrodt, J. M.; Koehler, W. E.; Lee, D. W.; Lee, T. H.; Lafleur, A. M.; Schear, M. A.; Humphrey, M. A.; Smith, Leon E.; Anderson, Kevin K.; Campbell, Luke W.; Casella, Andrew M.; Gesh, Christopher J.; Shaver, Mark W.; Misner, Alex C.; Amber, S. D.; Ludewigt, Bernhard A.; Quiter, B.; Solodov, Alexander; Charlton, W.; Stafford, A.; Romano, C.; Cheatham, J.; Ehinger, Michael; Thompson, S. J.; Chichester, David; Sterbentz, James; Hu, Jianwei; Hunt, A.; Mozin, Vladimir V.; Richard, J. G.

    2012-03-01

    Ever since there has been spent fuel (SF), researchers have made nondestructive assay (NDA) measurements of that fuel to learn about its content. In general these measurements have focused on the simplest signatures (passive photon and total neutron emission) and the analysis has often focused on diversion detection and on determining properties such as burnup (BU) and cooling time (CT). Because of shortcomings in current analysis methods, inspectorates and policy makers are interested in improving the state-of-the-art in SF NDA. For this reason the U.S. Department of Energy, through the Next Generation Safeguards Initiative (NGSI), targeted the determination of elemental Pu mass in SF as a technical goal. As part of this research effort, 14 nondestructive assay techniques were studied . This wide range of techniques was selected to allow flexibility for the various needs of the safeguards inspectorates and to prepare for the likely integration of one or more techniques having complementary features. In the course of researching this broad range of NDA techniques, several cross-cutting issues were. This paper will describe some common issues and insights. In particular we will describe the following: (1) the role of neutron absorbers with emphasis on how these absorbers vary in SF as a function of initial enrichment, BU and CT; (2) the need to partition the measured signal among different isotopic sources; and (3) the importance of the “first generation” concept which indicates the spatial location from which the signal originates as well as the isotopic origins.

  20. The US Support Program to IAEA Safeguards Priority of Containment and Surveillance

    SciTech Connect (OSTI)

    Diaz,R.A.

    2008-06-13

    The United States Support Program (USSP) priority for containment and surveillance (US) focuses on maintaining or improving the reliability and cost-effectiveness of C/S systems for IAEA safeguards, expanding the number of systems that are unattended and remotely monitored, and developing verification methods that help streamline the on-site inspection process. Existing IAEA C/S systems have evolved to become complex, integrated systems, which may include active seals, nondestructive assay (NDA) instruments, video cameras, and other sensors. These systems operate autonomously. They send analytical data to IAEA headquarters where it can be reviewed. These systems present challenges to the goals of improved system performance, standardization, reliability, maintainability, documentation, and cost effectiveness. One critical lesson from past experiences is the need for cooperation and common objectives among the IAEA, the developer, and the facility operator, to create a successful, cost effective system. Recent USSP C/S activities include Rokkasho Reprocessing Plant safeguard systems, production of a new shift register, numerous vulnerability assessments of C/S systems, a conduit monitoring system which identifies tampering of IAEA conduit deployed in the field, fiber optic seal upgrades, unattended monitoring system software upgrades, next generation surveillance system which will upgrade existing camera systems, and support of the IAEA's development of the universal nondestructive assay data acquisition platform.

  1. AUTHENTICATED SENSOR INTERFACE DEVICE FOR JOINT USE SAFEGUARDS APPLICATIONS - CONCEPTS AND CHALLENGES

    SciTech Connect (OSTI)

    Poland, R.; Drayer, R.; Wilson, J.

    2013-08-12

    This paper will discuss the key features of the Authenticated Sensor Interface Device that collectively provide the ability to share data among a number of parties while ensuring the authentication of data and protecting both the operator’s and the IAEA’s interests. The paper will also discuss the development of the prototype, the initial testing with an accountancy scale, and future plans and challenges to implementation into the joint use and remote monitoring applications. As nuclear fuel cycle technology becomes more prevalent throughout the world and the capacity of plants increases, limited resources of the IAEA are being stretched near a breaking point. A strategy is to increase efficiency in safeguards monitoring using “joint use” equipment that will provide the facility operator process data while also providing the IAEA key safeguards data. The data, however, must be authenticated and validated to ensure the data have not been tampered with. The Authenticated Sensor Interface Device provides the capability to share data and can be a valuable component in the IAEA’s ability to collect accountancy data from scales in Uranium conversion and enrichment plants, as well as nuclear fuel fabrication plants. Likewise, the Authenticated Sensor Interface Device can be configured to accept a diverse array of input signals, ranging from analog voltage, to current, to digital interfaces and more. These modular capabilities provide the ability to collect authenticated, joint-use, data streams from various process monitoring sensors.

  2. BN-350 unattended safeguards system current status and initial fuel movement data

    SciTech Connect (OSTI)

    Williams, Richard Brady; Browne, Michael C; Parker, Robert F; Ingegneri, Maurizio

    2009-01-01

    The Unattended and Remote Monitoring (UNARM) system at the BN-350 fast breeder reactor facility in Aktau, Kazakhstan continues to provide safeguards monitoring data as the spent fuel disposition project transitions from wet fuel storage to dry storage casks. Qualitative data from the initial cask loading procedures has been released by the International Atomic Energy Agency (IAEA) and is presented here for the first time. The BN-350 fast breeder reactor in Aktau, Kazakhstan, operated as a plutonium-producing facility from 1973 W1til 1999. Kazakhstan signed the Nonproliferation Treaty (NPT) in February 1994, and shortly afterwards the IAEA began safeguarding the reactor facility and its nuclear material. Slnce the cessation of reactor operations ten years ago, the chief proliferation concern has been the spent fuel assemblies stored in the pond on-site. By 2002, all fuel assemblies in wet storage had been repackaged into proliferation-resistant canisters. From the beginning, the IAEA's safeguards campaign at the BN-350 included a constant unattended sensor presence in the form of UNARM which monitors nuclear material activities at the facility in the absence of inspector presence. The UNARM equipment at the BN-350 was designed to be modular and extensible, allowing the system to adapt as the safeguards requirements change. This has been particularly important at the BN-350 due to the prolonged wet storage phase of the project. The primary function of the BN-350 UNARM system is to provide the IAEA with an independent, radiation-centric Containment and Surveillance (C&S) layer in addition to the standard seals and video systems. The UNARM system has provided continuous Continuity of Knowledge (COK) data for the BN-350's nuclear material storage areas in order to ensure the validity of the attended measurements during the lifetime of the project. The first of these attended measurements was characterization of the spent fuel assemblies. This characterization utilized the Spent Fuel Coincidence Counter (SFCC) instrument [ref] to measure neutron multiplicity and calculate Pu mass. These calculated masses were then compared to modeling simulation of the assemblies as well as declarations from the facility in order to baseline the amount of material under IAEA safeguards [ref]. Once the baseline was established, bundles of four or six assemblies were repackaged into proliferati n-resistant canisters. This provided an additional physical barrier to material diversion and provided further protection by choosing assemblies for each canister so that the overall dose rate met self-protection requirements. Each of the canisters were then characterized using a similar technique to the SFCC, but with the Spent Fuel Attribute Monitor (SPAM) instnunent (ref). The data from these measurements were then used to calculate an attribute proportional to the total Pu mass in each canister. This attribute was then compared to the know Pu mass of each assembly in order to verify the accuracy of SPAM. In the event that COK is lost, the SPAM detector remains positioned to reverify Pu content of individual canisters without requiring the canister to be opened.

  3. Validation of gamma-ray detection techniques for safeguards monitoring at natural uranium conversion facilities

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

    Dewji, Shaheen A.; Lee, Denise L.; Croft, Stephen; Hertel, Nolan E.; Chapman, Jeffrey Allen; McElroy, Jr., Robert Dennis; Cleveland, S.

    2016-03-28

    Recent IAEA circulars and policy papers have sought to implement safeguards when any purified aqueous uranium solution or uranium oxides suitable for isotopic enrichment or fuel fabrication exists. Under the revised policy, IAEA Policy Paper 18, the starting point for nuclear material under safeguards was reinterpreted, suggesting that purified uranium compounds should be subject to safeguards procedures no later than the first point in the conversion process. In response to this technical need, a combination of simulation models and experimental measurements were employed to develop and validate concepts of nondestructive assay monitoring systems in a natural uranium conversion plant (NUCP).more » In particular, uranyl nitrate (UO2(NO3)2) solution exiting solvent extraction was identified as a key measurement point (KMP), where gamma-ray spectroscopy was selected as the process monitoring tool. The Uranyl Nitrate Calibration Loop Equipment (UNCLE) facility at Oak Ridge National Laboratory was employed to simulate the full-scale operating conditions of a purified uranium-bearing aqueous stream exiting the solvent extraction process in an NUCP. Nondestructive assay techniques using gamma-ray spectroscopy were evaluated to determine their viability as a technical means for drawing safeguards conclusions at NUCPs, and if the IAEA detection requirements of 1 significant quantity (SQ) can be met in a timely way. This work investigated gamma-ray signatures of uranyl nitrate circulating in the UNCLE facility and evaluated various gamma-ray detector sensitivities to uranyl nitrate. These detector validation activities include assessing detector responses to the uranyl nitrate gamma-ray signatures for spectrometers based on sodium iodide, lanthanum bromide, and high-purity germanium detectors. The results of measurements under static and dynamic operating conditions at concentrations ranging from 10–90 g U/L of natural uranyl nitrate are presented. A range of gamma-ray lines is examined, including attenuation for transmission measurement of density and concentration. It was determined that transmission-corrected gamma-ray spectra provide a reliable way to monitor the 235U concentration of uranyl nitrate solution in transfer pipes in NUCPs. Furthermore, existing predictive and analysis methods are adequate to design and realize practical designs. The 137Cs transmission source employed in this work is viable but not optimal for 235U densitometry determination. Validated simulations assessed the viability of 133Ba and 57Co as alternative densitometry sources. All three gamma-ray detectors are viable for monitoring natural uranium feed; although high-purity germanium is easiest to interpret, it is, however, the least attractive as an installation instrument. Overall, for monitoring throughput in a facility such as UNCLE, emulating the uranium concentration and pump speeds of the Springfields conversion facility in the United Kingdom, an uncertainty of less than 0.17% is required in order to detect the diversion of 1 SQ of uranyl nitrate through changes in uranium concentration over an accountancy period of one year with a detection probability of 50%. As a result, calibrated gamma-ray detection systems are capable of determining the concentration of uranium content in NUCPs, it is only in combination with verifiable operator declarations and supporting data, such as flow rate and enrichment, that safeguards conclusions can be drawn.« less

  4. Safeguards Transporter

    National Nuclear Security Administration (NNSA)

    Hernandez, Squad Commander; General Davis; Isaiah Bullock, Senior Federal Agent; Mark Jackson, OST Acting Deputy Assistant Deputy Administrator; Fred Roberts, Deputy Director...

  5. Influence of Mechanical Properties Relevant to Standoff Deflection...

    Office of Scientific and Technical Information (OSTI)

    Influence of Mechanical Properties Relevant to Standoff Deflection of Hazardous Asteroids Citation Details In-Document Search Title: Influence of Mechanical Properties Relevant to...

  6. American Indian Policy and Relevant DOE and Executive Orders...

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

    Tribal Programs American Indian Policy and Relevant DOE and Executive Orders American Indian Policy and Relevant DOE and Executive Orders Over the course of American history, ...

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

    SciTech Connect (OSTI)

    Humberto E. Garcia

    2014-07-01

    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 indicative 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-centric strategy that utilizes data collected from a system of sensors and that effectively exploits known characterizations of sensors and facility operations in order to significantly improve anomaly detection, reduce false alarm, and enhance assessment robustness under unreliable partial sensor information.

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

    SciTech Connect (OSTI)

    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) a 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 safeguards recommendations are made based on the assumption that the reactor is successfully commercialized and is widely deployed.

  9. Integrating Safety, Operations, Security, and Safeguards (ISOSS) into the design of small modular reactors : a handbook.

    SciTech Connect (OSTI)

    Middleton, Bobby D.; Mendez, Carmen Margarita

    2013-10-01

    The existing regulatory environment for nuclear reactors impacts both the facility design and the cost of operations once the facility is built. Delaying the consideration of regulatory requirements until late in the facility design - or worse, until after construction has begun - can result in costly retrofitting as well as increased operational costs to fulfill safety, security, safeguards, and emergency readiness requirements. Considering the scale and scope, as well as the latest design trends in the next generation of nuclear facilities, there is an opportunity to evaluate the regulatory requirements and optimize the design process for Small Modular Reactors (SMRs), as compared to current Light Water Reactors (LWRs). To this end, Sandia has embarked on an initiative to evaluate the interactions of regulations and operations as an approach to optimizing the design of SMR facilities, supporting operational efficiencies, as well as regulatory requirements. The early stages of this initiative consider two focus areas. The first focus area, reported by LaChance, et al. (2007), identifies the regulatory requirements established for the current fleet of LWR facilities regarding Safety, Security, Operations, Safeguards, and Emergency Planning, and evaluates the technical bases for these requirements. The second focus area, developed in this report, documents the foundations for an innovative approach that supports a design framework for SMR facilities that incorporates the regulatory environment, as well as the continued operation of the facility, into the early design stages, eliminating the need for costly retrofitting and additional operating personnel to fulfill regulatory requirements. The work considers a technique known as Integrated Safety, Operations, Security and Safeguards (ISOSS) (Darby, et al., 2007). In coordination with the best practices of industrial operations, the goal of this effort is to develop a design framework that outlines how ISOSS requirements can be incorporated into the pre-conceptual through early facility design stages, seeking a cost-effective design that meets both operational efficiencies and the regulatory environment. The larger scope of the project, i.e., in future stages, includes the identification of potentially conflicting requirements identified by the ISOSS framework, including an analysis of how regulatory requirements may be changed to account for the intrinsic features of SMRs.

  10. Integrated Information Technology Framework for Analysis of Data from Enrichment Plants to Support the Safeguards Mission

    SciTech Connect (OSTI)

    Marr, Clifton T.; Thurman, David A.; Jorgensen, Bruce V.

    2008-07-15

    ABSTRACT Many examples of software architectures exist that support process monitoring and analysis applications which could be applied to enrichment plants in a fashion that supports the Safeguards Mission. Pacific Northwest National Laboratory (PNNL) has developed mature solutions that will provide the framework to support online statistical analysis of enrichment plans and the entire nuclear fuel cycle. Most recently, PNNL has developed a refined architecture and supporting tools that address many of the common problems analysis and modeling environments experience: pipelining, handling large data volumes, and real-time performance. We propose the architecture and tools may be successfully used in furthering the goals of nuclear material control and accountability as both an aid to processing plant owners and as comprehensive monitoring for oversight teams.

  11. Considerations for Possible Light Impact of Spent Nuclear Fuel for Safeguards Measurements

    SciTech Connect (OSTI)

    Brian K. Castle; Kelly D. Ellis

    2012-09-01

    This effort is designed to be a preliminary study to determine the appropriateness of lightly contacting SNF with zirconium-based cladding, in wet storage, for the purpose of taking safeguards measurements. Contact will likely consist of an initial impact followed by a light tensile load on the exterior surface of the SNF cladding. In the past, concerns have been raised that contacting SNF cladding could result in a loss of long-term mechanical integrity due to crack initiation, uncontrolled crack propagation, and a mechanical exfoliation of the protective oxide layer. The mechanical integrity concerns are addressed with an analytic model that evaluates the threshold impact limits for degraded, but undamaged SNF cladding. Aqueous corrosion concerns, associated with exfoliation of the protective oxide layer, are addressed with a qualitative argument, focusing on the possible corrosion mechanisms of zirconium-based cladding.

  12. International and national security applications of cryogenic detectors - mostly nuclear safeguards

    SciTech Connect (OSTI)

    Rabin, Michael W

    2009-01-01

    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 invi sible 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.

  13. Baseline and optional bench-scale testing of a chemical candle filter safeguard device

    SciTech Connect (OSTI)

    Hurley, J.P.; Swanson, M.L.

    2000-11-01

    This project was undertaken by the Energy and Environmental Research Center (EERC) to design, construct, and test the feasibility of a hot-gas filter safeguard device (SGD) to prevent the release of dust in the event of candle filter failure under both pressurized fluidized-bed combustion (PFBC) (oxidizing) and integrated gasification combined cycle (IGCC) (reducing) operating conditions. The SGD must use existing filter system seals, gaskets, fixtures, and assemblies as much as possible. It must also activate quickly when a candle filter has failed, preferably preventing dust concentrations downstream of the SGD from exceeding 1 ppmw. In addition, the SGD must be able to operate in an inactive mode with minimal pressure drop, and its operation cannot be affected by repeated backpulse cleaning events of up to 3 psia and 1/2 second in duration.

  14. Probabilistic risk analysis toward cost-effective 3S (safety, safeguards, security) implementation

    SciTech Connect (OSTI)

    Suzuki, Mitsutoshi; Mochiji, Toshiro

    2014-09-30

    Probabilistic Risk Analysis (PRA) has been introduced for several decades in safety and nuclear advanced countries have already used this methodology in their own regulatory systems. However, PRA has not been developed in safeguards and security so far because of inherent difficulties in intentional and malicious acts. In this paper, probabilistic proliferation and risk analysis based on random process is applied to hypothetical reprocessing process and physical protection system in nuclear reactor with the Markov model that was originally developed by the Proliferation Resistance and Physical Protection Working Group (PRPPWG) in Generation IV International Framework (GIF). Through the challenge to quantify the security risk with a frequency in this model, integrated risk notion among 3S to pursue the cost-effective installation of those countermeasures is discussed in a heroic manner.

  15. Safeguards and Security FY 1996 Program Plan: WBS 6.6

    SciTech Connect (OSTI)

    Lee, F.D.

    1995-08-01

    The Safeguards and Security (SAS) Program is based upon integrity, competence and innovation in the protection of the public and Hanford resources through: (1) outstanding assistance, oversight, education, and counsel to their customers to ensure the protection of the public, site personnel, assets, and information; (2) value-added and cost-effective solutions to Hanford issues; and (3) risk management techniques to ensure effective asset protection, site accessibility, and the flexibility to adapt to changing customer needs. This plan is divided into two parts: overview and SAS WBS (work breakdown structure) dictionary sheets. The overview is divided into vision and mission, goals and objectives, assumptions and priorities, milestones, and a summary. The SAS WBS dictionary sheets are divided into department overhead, general and administrative, sitewide support, Hanford patrol, traffic safety, and locksmith services.

  16. Precision Information Environment (PIE) for International Safeguards: Pre-Demonstration Development Use Cases

    SciTech Connect (OSTI)

    Gastelum, Zoe N.; Henry, Michael J.

    2013-11-13

    In FY2013, the PIE International Safeguards team demonstrated our development progress to U.S. Department of Energy (DOE) staff from the Office of Nonproliferation and International Security (NA-24, our client) and the Office of Defense Nuclear Nonproliferation Research and Development (NA-22). Following the demonstration, the team was asked by our client to complete additional development prior to a planned demonstration at the International Atomic Energy Agency (IAEA), scheduled tentatively for January or spring of 2014. The team discussed four potential areas for development (in priority order), and will develop them as time and funding permit prior to an IAEA demonstration. The four capability areas are: 1. Addition of equipment manuals to PIE-accessible files 2. Optical character recognition (OCR) of photographed text 3. Barcode reader with information look-up from a database 4. Add Facilities to Data Model 5. Geospatial capabilities with information integration Each area will be described below in a use case.

  17. Safeguards design strategies: designing and constructing new uranium and plutonium processing facilities in the United States

    SciTech Connect (OSTI)

    Scherer, Carolynn P; Long, Jon D

    2010-09-28

    In the United States, the Department of Energy (DOE) is transforming its outdated and oversized complex of aging nuclear material facilities into a smaller, safer, and more secure National Security Enterprise (NSE). Environmental concerns, worker health and safety risks, material security, reducing the role of nuclear weapons in our national security strategy while maintaining the capability for an effective nuclear deterrence by the United States, are influencing this transformation. As part of the nation's Uranium Center of Excellence (UCE), the Uranium Processing Facility (UPF) at the Y-12 National Security Complex in Oak Ridge, Tennessee, will advance the U.S.'s capability to meet all concerns when processing uranium and is located adjacent to the Highly Enriched Uranium Materials Facility (HEUMF), designed for consolidated storage of enriched uranium. The HEUMF became operational in March 2010, and the UPF is currently entering its final design phase. The designs of both facilities are for meeting anticipated security challenges for the 21st century. For plutonium research, development, and manufacturing, the Chemistry and Metallurgy Research Replacement (CMRR) building at the Los Alamos National Laboratory (LANL) in Los Alamos, New Mexico is now under construction. The first phase of the CMRR Project is the design and construction of a Radiological Laboratory/Utility/Office Building. The second phase consists of the design and construction of the Nuclear Facility (NF). The National Nuclear Security Administration (NNSA) selected these two sites as part of the national plan to consolidate nuclear materials, provide for nuclear deterrence, and nonproliferation mission requirements. This work examines these two projects independent approaches to design requirements, and objectives for safeguards, security, and safety (3S) systems as well as the subsequent construction of these modern processing facilities. Emphasis is on the use of Safeguards-by-Design (SBD), incorporating Systems Engineering (SE) principles for these two projects.

  18. Risks to global biodiversity from fossil-fuel production exceed those from biofuel production

    SciTech Connect (OSTI)

    Dale, Virginia H; Parish, Esther S; Kline, Keith L

    2015-01-01

    Potential global biodiversity impacts from near-term gasoline production are compared to biofuel, a renewable liquid transportation fuel expected to substitute for gasoline in the near term (i.e., from now until c. 2030). Petroleum exploration activities are projected to extend across more than 5.8 billion ha of land and ocean worldwide (of which 3.1 billion is on land), much of which is in remote, fragile terrestrial ecosystems or off-shore oil fields that would remain relatively undisturbed if not for interest in fossil fuel production. Future biomass production for biofuels is projected to fall within 2.0 billion ha of land, most of which is located in areas already impacted by human activities. A comparison of likely fuel-source areas to the geospatial distribution of species reveals that both energy sources overlap with areas with high species richness and large numbers of threatened species. At the global scale, future petroleum production areas intersect more than double the area and higher total number of threatened species than future biofuel production. Energy options should be developed to optimize provisioning of ecosystem services while minimizing negative effects, which requires information about potential impacts on critical resources. Energy conservation and identifying and effectively protecting habitats with high-conservation value are critical first steps toward protecting biodiversity under any fuel production scenario.

  19. Risks to global biodiversity from fossil-fuel production exceed those from biofuel production

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

    Dale, Virginia H; Parish, Esther S; Kline, Keith L

    2015-01-01

    Potential global biodiversity impacts from near-term gasoline production are compared to biofuel, a renewable liquid transportation fuel expected to substitute for gasoline in the near term (i.e., from now until c. 2030). Petroleum exploration activities are projected to extend across more than 5.8 billion ha of land and ocean worldwide (of which 3.1 billion is on land), much of which is in remote, fragile terrestrial ecosystems or off-shore oil fields that would remain relatively undisturbed if not for interest in fossil fuel production. Future biomass production for biofuels is projected to fall within 2.0 billion ha of land, most ofmore » which is located in areas already impacted by human activities. A comparison of likely fuel-source areas to the geospatial distribution of species reveals that both energy sources overlap with areas with high species richness and large numbers of threatened species. At the global scale, future petroleum production areas intersect more than double the area and higher total number of threatened species than future biofuel production. Energy options should be developed to optimize provisioning of ecosystem services while minimizing negative effects, which requires information about potential impacts on critical resources. Energy conservation and identifying and effectively protecting habitats with high-conservation value are critical first steps toward protecting biodiversity under any fuel production scenario.« less

  20. Protocol Additional to the Agreement between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States of America

    National Nuclear Security Administration (NNSA)

    Information Circular INFCIRC/288/Add.1 Date: 9 March 2009 General Distribution Original: English Protocol Additional to the Agreement between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States of America 1. The text of the Protocol Additional to the Agreement between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States of America 1 is reproduced in

  1. Neutron Resonance Transmission Analysis (NRTA): A Nondestructive Assay Technique for the Next Generation Safeguards Initiative’s Plutonium Assay Challenge

    SciTech Connect (OSTI)

    J. W. Sterbentz; D. L. Chichester

    2010-12-01

    This is an end-of-year report for a project funded by the National Nuclear Security Administration's Office of Nuclear Safeguards (NA-241). The goal of this project is to investigate the feasibility of using Neutron Resonance Transmission Analysis (NRTA) to assay plutonium in commercial light-water-reactor spent fuel. This project is part of a larger research effort within the Next-Generation Safeguards Initiative (NGSI) to evaluate methods for assaying plutonium in spent fuel, the Plutonium Assay Challenge. The first-year goals for this project were modest and included: 1) developing a zero-order MCNP model for the NRTA technique, simulating data results presented in the literature, 2) completing a preliminary set of studies investigating important design and performance characteristics for the NRTA measurement technique, and 3) documentation of this work in an end of the year report (this report). Research teams at Los Alamos National Laboratory (LANL), Lawrence Berkeley National Laboratory (LBNL), Pacific Northwest National Laboratory (PNNL), and at several universities are also working to investigate plutonium assay methods for spent-fuel safeguards. While the NRTA technique is well proven in the scientific literature for assaying individual spent fuel pins, it is a newcomer to the current NGSI efforts studying Pu assay method techniques having just started in March 2010; several analytical techniques have been under investigation within this program for two to three years or more. This report summarizes a nine month period of work.

  2. FEMO, A FLOW AND ENRICHMENT MONITOR FOR VERIFYING COMPLIANCE WITH INTERNATIONAL SAFEGUARDS REQUIREMENTS AT A GAS CENTRIFUGE ENRICHMENT FACILITY

    SciTech Connect (OSTI)

    Gunning, John E; Laughter, Mark D; March-Leuba, Jose A

    2008-01-01

    A number of countries have received construction licenses or are contemplating the construction of large-capacity gas centrifuge enrichment plants (GCEPs). The capability to independently verify nuclear material flows is a key component of international safeguards approaches, and the IAEA does not currently have an approved method to continuously monitor the mass flow of 235U in uranium hexafluoride (UF6) gas streams. Oak Ridge National Laboratory is investigating the development of a flow and enrichment monitor, or FEMO, based on an existing blend-down monitoring system (BDMS). The BDMS was designed to continuously monitor both 235U mass flow and enrichment of UF6 streams at the low pressures similar to those which exists at GCEPs. BDMSs have been installed at three sites-the first unit has operated successfully in an unattended environment for approximately 10 years. To be acceptable to GCEP operators, it is essential that the instrument be installed and maintained without interrupting operations. A means to continuously verify flow as is proposed by FEMO will likely be needed to monitor safeguards at large-capacity plants. This will enable the safeguards effectiveness that currently exists at smaller plants to be maintained at the larger facilities and also has the potential to reduce labor costs associated with inspections at current and future plants. This paper describes the FEMO design requirements, operating capabilities, and development work required before field demonstration.

  3. Interim Update: Global Automotive Power Electronics R&D Relevant...

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

    Interim Update: Global Automotive Power Electronics R&D Relevant To DOE 2015 and 2020 Cost Targets Interim Update: Global Automotive Power Electronics R&D Relevant To DOE 2015 and ...

  4. EERE QC Workshop: Overview of Relevant Processes | Department of Energy

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

    Relevant Processes EERE QC Workshop: Overview of Relevant Processes Overview of relevant QC process by Michael Ulsh, National Renewable Energy Laboratory, at the EERE QC Workshop held December 9-10, 2013, at the National Renewable Energy Laboratory in Golden, Colorado. PDF icon EERE QC Workshop: Overview of Relevant Processes More Documents & Publications EERE QC Workshop: Overview of Quality Control Techniques EERE Quality Control Workshop Agenda DOE's Hydrogen and Fuel Cell Technologies

  5. The Pacific Northwest National Laboratory library of bacterial and archaeal proteomic biodiversity

    SciTech Connect (OSTI)

    Payne, Samuel H.; Monroe, Matthew E.; Overall, Christopher C.; Kiebel, Gary R.; Degan, Michael G.; Gibbons, Bryson C.; Fujimoto, Grant M.; Purvine, Samuel O.; Adkins, Joshua N.; Lipton, Mary S.; Smith, Richard D.

    2015-08-18

    This dataset deposition announces the submission to public repositories of the PNNL Biodiversity Library, a large collection of global proteomics data for 112 bacterial and archaeal organisms. The data comprises 35,162 tandem mass spectrometry (MS/MS) datasets from ~10 years of research. All data has been searched, annotated and organized in a consistent manner to promote reuse by the community. Protein identifications were cross-referenced with KEGG functional annotations which allows for pathway oriented investigation. We present the data as a freely available community resource. A variety of data re-use options are described for computational modeling, proteomics assay design and bioengineering. Instrument data and analysis files are available at ProteomeXchange via the MassIVE partner repository under the identifiers PXD001860 and MSV000079053.

  6. The Pacific Northwest National Laboratory library of bacterial and archaeal proteomic biodiversity

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

    Payne, Samuel H.; Monroe, Matthew E.; Overall, Christopher C.; Kiebel, Gary R.; Degan, Michael G.; Gibbons, Bryson C.; Fujimoto, Grant M.; Purvine, Samuel O.; Adkins, Joshua N.; Lipton, Mary S.; et al

    2015-08-18

    This dataset deposition announces the submission to public repositories of the PNNL Biodiversity Library, a large collection of global proteomics data for 112 bacterial and archaeal organisms. The data comprises 35,162 tandem mass spectrometry (MS/MS) datasets from ~10 years of research. All data has been searched, annotated and organized in a consistent manner to promote reuse by the community. Protein identifications were cross-referenced with KEGG functional annotations which allows for pathway oriented investigation. We present the data as a freely available community resource. A variety of data re-use options are described for computational modeling, proteomics assay design and bioengineering. Instrumentmore » data and analysis files are available at ProteomeXchange via the MassIVE partner repository under the identifiers PXD001860 and MSV000079053.« less

  7. Nucifer: A small electron-antineutrino detector for fundamental and safeguard studies

    SciTech Connect (OSTI)

    Letourneau, A.; Bui, V. M.; Fallot, M.; Giot, L.; Martino, J.; Porta, A.; Varignon, C.; Yermia, F.

    2011-07-01

    The Nucifer detector will be deployed in the next few months at the Osiris research reactor in France. Nucifer is a 1-ton Gd-doped liquid scintillator detector devoted to reactor antineutrino studies. It will be installed 7 m away from the compact core of the Osiris reactor. The design of such small volume detector has been focused on high detection efficiency and good background rejection. Over the last decades, our understanding of the neutrino properties has been improved and allows today the possibility to apply the detection of antineutrinos to automatic and to non intrusively survey nuclear power plant. This has triggered the interest of the International Atomic Energy Agency (IAEA), which is interested by developing new safeguard techniques for next generation reactors. The sensitivity of such technique has to be proved and demonstrated. On the other hand there is still some issues in our understanding of the neutrino properties as the observed deficit in the antineutrino rate at short distances (< 100 m) that can not be explained by oscillations in the 3-flavors neutrino model. If a global systematic error is rejected, such anomaly opens the door to new physic that can be assessed with small detectors placed close to the core. Here we review the Nucifer detector in this context and the tests we are performing. (authors)

  8. AUTOMATED PROCESS MONITORING: APPLYING PROVEN AUTOMATION TECHNIQUES TO INTERNATIONAL SAFEGUARDS NEEDS

    SciTech Connect (OSTI)

    O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Devol, Timothy A.; Egorov, Oleg; Clements, John P.

    2008-07-13

    Identification and quantification of specific alpha- and beta-emitting radionuclides in complex liquid matrices is highly challenging, and is typically accomplished through laborious wet chemical sample preparation and separations followed by analysis using a variety of detection methodologies (e.g., liquid scintillation, gas proportional counting, alpha energy analysis, mass spectrometry). Analytical results may take days or weeks to report. Chains of custody and sample security measures may also complicate or slow the analytical process. When an industrial process-scale plant requires the monitoring of specific radionuclides as an indication of the composition of its feed stream or of plant performance, radiochemical measurements must be fast, accurate, and reliable. Scientists at Pacific Northwest National Laboratory have assembled a fully automated prototype Process Monitor instrument capable of a variety of tasks: automated sampling directly from a feed stream, sample digestion / analyte redox adjustment, chemical separations, radiochemical detection and data analysis / reporting. The system is compact, its components are fluidically inter-linked, and analytical results could be immediately transmitted to on- or off-site locations. The development of a rapid radiochemical Process Monitor for 99Tc in Hanford tank waste processing streams, capable of performing several measurements per hour, will be discussed in detail. More recently, the automated platform was modified to perform measurements of 90Sr in Hanford tank waste stimulant. The system exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs.

  9. The use of TI-208 gamma rays for safeguards, nondestructive-assay (NDA) measurements

    SciTech Connect (OSTI)

    Oberer, R. B.; Chiang, L. G.; Norris, M. J.; Gunn, C. A.; Adaline, B. C.

    2009-05-26

    This paper examines two cases where gamma rays from Tl-208, including the 2614keV gamma ray, were used to detect anomalies in waste material. In addition to the characterization of waste for waste acceptance, and compliance with environmental and transportation laws, there is a safeguards element as well. The more sophisticated method of NDA at Y-12 includes a means to detect shielded special nuclear material (SNM). Excess count rates in the 2614keV gamma ray from Tl-208 are an indication of potential shielded HEU in waste as well as other containers. The 2614keV gamma ray is easy to monitor routinely. When a large 2614keV peak is detected, further investigation can be conducted from the gamma spectrum. This paper describes this further investigation in two cases. In one case self-shielded HEU was detected. In the other case the Tl-208 gamma rays came from a piece of Th-232 metal.

  10. Safeguards Verification Measurements using Laser Ablation, Absorbance Ratio Spectrometry in Gaseous Centrifuge Enrichment Plants

    SciTech Connect (OSTI)

    Anheier, Norman C.; Cannon, Bret D.; Kulkarni, Gourihar R.; Munley, John T.; Nelson, Danny A.; Qiao, Hong; Phillips, Jon R.

    2012-07-17

    Laser Ablation Absorbance Ratio Spectrometry (LAARS) is a new verification measurement technology under development at the US Department of Energy (DOE) Pacific Northwest National Laboratory (PNNL). LAARS uses three lasers to ablate and then measure the relative isotopic abundance of uranium compounds. An ablation laser is tightly focused on uranium-bearing solids, producing a small atomic uranium vapor plume. Two collinear wavelength-tuned spectrometry lasers transit through the plume and the absorbance of U-235 and U-238 isotopes are measured to determine U-235 enrichment. The measurement is independent of chemical form and degree of dilution with nuisance dust and other materials. LAARS has high relative precision and detection limits approaching the femtogram range for U-235. The sample is scanned and assayed point-by-point at rates reaching 1 million measurements/hour, enabling LAARS to detect and analyze uranium in trace samples. The spectrometer is assembled using primarily commercially available components and features a compact design and automated analysis.Two specific gaseous centrifuge enrichment plant (GCEP) applications of the spectrometer are currently under development: 1) LAARS-Environmental Sampling (ES), which collects and analyzes aerosol particles for GCEP misuse detection and 2) LAARS-Destructive Assay (DA), which enables onsite enrichment DA sample collection and analysis for protracted diversion detection. The two applications propose game-changing technological advances in GCEP safeguards verification.

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

    SciTech Connect (OSTI)

    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 the 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.

  12. Advances Towards Readily Deployable Antineutrino Detectors for Reactor Monitoring and Safeguards

    SciTech Connect (OSTI)

    Bowden, N S; Bernstein, A; Dazeley, S; Lund, J; Reyna, D; Sadler, L; Svoboda, R

    2008-06-05

    Nuclear reactors have served as the neutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these very weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Our LLNL/SNL collaboration has demonstrated that such antineutrino based monitoring is feasible using a relatively small cubic meter scale detector at tens of meters standoff from a commercial PWR. With little or no burden on the plant operator we have been able to remotely and automatically monitor the reactor operational status (on/off), power level, and fuel burnup. Recently, we have investigated several technology paths that could allow such devices to be more readily deployed in the field. In particular, we have developed and fielded two new detectors; a low cost, non- flammable water based design; and a robust solid-state design based upon plastic scintillator. Here we will describe the tradeoffs inherent in these designs, and present results from their field deployments.

  13. 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)

    SciTech Connect (OSTI)

    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 of 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.

  14. Advances toward a transportable antineutrino detector system for reactor monitoring and safeguards

    SciTech Connect (OSTI)

    Reyna, D.; Bernstein, A.; Lund, J.; Kiff, S.; Cabrera-Palmer, B.; Bowden, N. S.; Dazeley, S.; Keefer, G.

    2011-07-01

    Nuclear reactors have served as the neutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these very weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Our SNL/LLNL collaboration has demonstrated that such antineutrino based monitoring is feasible using a relatively small cubic meter scale liquid scintillator detector at tens of meters standoff from a commercial Pressurized Water Reactor (PWR). With little or no burden on the plant operator we have been able to remotely and automatically monitor the reactor operational status (on/off), power level, and fuel burnup. The initial detector was deployed in an underground gallery that lies directly under the containment dome of an operating PWR. The gallery is 25 meters from the reactor core center, is rarely accessed by plant personnel, and provides a muon-screening effect of some 20-30 meters of water equivalent earth and concrete overburden. Unfortunately, many reactor facilities do not contain an equivalent underground location. We have therefore attempted to construct a complete detector system which would be capable of operating in an aboveground location and could be transported to a reactor facility with relative ease. A standard 6-meter shipping container was used as our transportable laboratory - containing active and passive shielding components, the antineutrino detector and all electronics, as well as climate control systems. This aboveground system was deployed and tested at the San Onofre Nuclear Generating Station (SONGS) in southern California in 2010 and early 2011. We will first present an overview of the initial demonstrations of our below ground detector. Then we will describe the aboveground system and the technological developments of the two antineutrino detectors that were deployed. Finally, some preliminary results of our aboveground test will be shown. (authors)

  15. Next Generation Safeguards Initiative: Overview and Policy Context of UF6 Cylinder Tracking Program

    SciTech Connect (OSTI)

    Boyer, Brian D; Whitaker, J. Michael; White-Horton, Jessica L.; Durbin, Karyn R.

    2012-07-12

    Thousands of cylinders containing uranium hexafluoride (UF{sub 6}) move around the world from conversion plants to enrichment plants to fuel fabrication plants, and their contents could be very useful to a country intent on diverting uranium for clandestine use. Each of these large cylinders can contain close to a significant quantity of natural uranium (48Y cylinder) or low-enriched uranium (LEU) (30B cylinder) defined as 75 kg {sup 235}U which can be further clandestinely enriched to produce 1.5 to 2 significant quantities of high enriched uranium (HEU) within weeks or months depending on the scale of the clandestine facility. The National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) kicked off a 5-year plan in April 2011 to investigate the concept of a unique identification system for UF{sub 6} cylinders and potentially to develop a cylinder tracking system that could be used by facility operators and the International Atomic Energy Agency (IAEA). The goal is to design an integrated solution beneficial to both industry and inspectorates that would improve cylinder operations at the facilities and provide enhanced capabilities to deter and detect both diversion of low-enriched uranium and undeclared enriched uranium production. The 5-year plan consists of six separate incremental tasks: (1) define the problem and establish the requirements for a unique identification (UID) and monitoring system; (2) develop a concept of operations for the identification and monitoring system; (3) determine cylinder monitoring devices and technology; (4) develop a registry database to support proof-of-concept demonstration; (5) integrate that system for the demonstration; and (6) demonstrate proof-of-concept. Throughout NNSA's performance of the tasks outlined in this program, the multi-laboratory team emphasizes that extensive engagement with industry stakeholders, regulatory authorities and inspectorates is essential to its success.

  16. Modeling of UF{sub 6} enrichment with gas centrifuges for nuclear safeguards activities

    SciTech Connect (OSTI)

    Mercurio, G.; Peerani, P.; Richir, P.; Janssens, W.; Eklund, G.

    2012-09-26

    The physical modeling of uranium isotopes ({sup 235}U, {sup 238}U) separation process by centrifugation of is a key aspect for predicting the nuclear fuel enrichment plant performances under surveillance by the Nuclear Safeguards Authorities. In this paper are illustrated some aspects of the modeling of fast centrifuges for UF{sub 6} gas enrichment and of a typical cascade enrichment plant with the Theoretical Centrifuge and Cascade Simulator (TCCS). The background theory for reproducing the flow field characteristics of a centrifuge is derived from the work of Cohen where the separation parameters are calculated using the solution of a differential enrichment equation. In our case we chose to solve the hydrodynamic equations for the motion of a compressible fluid in a centrifugal field using the Berman - Olander vertical velocity radial distribution and the solution was obtained using the Matlab software tool. The importance of a correct estimation of the centrifuge separation parameters at different flow regimes, lies in the possibility to estimate in a reliable way the U enrichment plant performances, once the separation external parameters are set (feed flow rate and feed, product and tails assays). Using the separation parameters of a single centrifuge allow to determine the performances of an entire cascade and, for this purpose; the software Simulink was used. The outputs of the calculation are the concentrations (assays) and the flow rates of the enriched (product) and depleted (tails) gas mixture. These models represent a valid additional tool, in order to verify the compliance of the U enrichment plant operator declarations with the 'on site' inspectors' measurements.

  17. Quark-gluon correlation functions relevant to single transverse spin

    Office of Scientific and Technical Information (OSTI)

    asymmetries (Journal Article) | SciTech Connect Quark-gluon correlation functions relevant to single transverse spin asymmetries Citation Details In-Document Search Title: Quark-gluon correlation functions relevant to single transverse spin asymmetries We investigate the relative size of various twist-3 quark-gluon correlation functions relevant to single transverse spin asymmetries (SSAs) in a quark-diquark model of the nucleon. We calculate the quark-gluon correlation function T{sub

  18. Monitoring, Controlling and Safeguarding Radiochemical Streams at Spent Fuel Reprocessing Facilities, Part 2: Gamma-Ray Spectroscopic Methods

    SciTech Connect (OSTI)

    Schwantes, Jon M.; Bryan, Samuel A.; Orton, Christopher R.; Levitskaia, Tatiana G.; Fraga, Carlos G.

    2012-02-10

    The International Atomic Energy Agency (IAEA) has established international safeguards standards for fissionable material at spent fuel reprocessing plants to ensure that significant quantities of weapons-useable nuclear material are not diverted from these facilities. For large throughput nuclear facilities, it is difficult to satisfy the IAEA safeguards accountancy goal for detection of abrupt diversion. Currently, methods to verify material control and accountancy (MC&A) at these facilities require time-consuming and resource-intensive destructive assay (DA). Leveraging new on-line non-destructive assay (NDA) process monitoring techniques in conjunction with the traditional and highly precise DA methods may provide an additional measure to nuclear material accountancy which would potentially result in a more timely, cost-effective and resource efficient means for safeguards verification at such facilities. By monitoring process control measurements (e.g. flowrates, temperatures, or concentrations of reagents, products or wastes), abnormal plant operations can be detected. Pacific Northwest National Laboratory (PNNL) is developing on-line NDA process monitoring technologies based upon gamma-ray and optical spectroscopic measurements to potentially reduce the time and resource burden associated with current techniques. The Multi-Isotope Process (MIP) Monitor uses gamma spectroscopy and multivariate analysis to identify off-normal conditions in process streams. The spectroscopic monitor continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major stable flowsheet reagents using UV-Vis, Near IR and Raman spectroscopy. Multi-variate analysis is also applied to the optical measurements in order to quantify concentrations of analytes of interest within a complex array of radiochemical streams. This paper will provide an overview of these methods and reports on-going efforts to develop and demonstrate the technologies. This paper is Part 2 of a two part series, and focuses on the gamma spectroscopy based, Multi-Isotope Process (MIP) Monitor method.

  19. Monitoring, Controlling and Safeguarding Radiochemical Streams at Spent Fuel Reprocessing Facilities with Optical and Gamma-Ray Spectroscopic Methods

    SciTech Connect (OSTI)

    Schwantes, Jon M.; Bryan, Samuel A.; Orton, Christopher R.; Levitskaia, Tatiana G.; Fraga, Carlos G.

    2012-11-06

    The International Atomic Energy Agency (IAEA) has established international safeguards standards for fissionable material at spent fuel reprocessing plants to ensure that significant quantities of weapons-useable nuclear material are not diverted from these facilities. For large throughput nuclear facilities, it is difficult to satisfy the IAEA safeguards accountancy goal for detection of abrupt diversion. Currently, methods to verify material control and accountancy (MC&A) at these facilities require time-consuming and resourceintensive destructive assay (DA). Leveraging new on-line non-destructive assay (NDA) process monitoring techniques in conjunction with the traditional and highly precise DA methods may provide an additional measure to nuclear material accountancy which would potentially result in a more timely, cost-effective and resource efficient means for safeguards verification at such facilities. By monitoring process control measurements (e.g. flowrates, temperatures, or concentrations of reagents, products or wastes), abnormal plant operations can be detected. Pacific Northwest National Laboratory (PNNL) is developing on-line NDA process monitoring technologies based upon gamma-ray and optical spectroscopic measurements to potentially reduce the time and resource burden associated with current techniques. The Multi-Isotope Process (MIP) Monitor uses gamma spectroscopy and multivariate analysis to identify offnormal conditions in process streams. The spectroscopic monitor continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major stable flowsheet reagents using UV-Vis, Near IR and Raman spectroscopy. Multi-variate analysis is also applied to the optical measurements in order to quantify concentrations of analytes of interest within a complex array of radiochemical streams. This paper will provide an overview of these methods and reports on-going efforts to develop and demonstrate the technologies.

  20. Over 150 years of long-term fertilization alters spatial scaling of microbial biodiversity

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

    Liang, Yuting; Wu, Liyou; Clark, Ian M.; Xue, Kai; Yang, Yunfeng; Van Nostrand, Joy D.; Deng, Ye; He, Zhili; McGrath, Steve; Storkey, Jonathan; et al

    2015-04-07

    Spatial scaling is a critical issue in ecology, but how anthropogenic activities like fertilization affect spatial scaling is poorly understood, especially for microbial communities. Here, we determined the effects of long-term fertilization on the spatial scaling of microbial functional diversity and its relationships to plant diversity in the 150-year-old Park Grass Experiment, the oldest continuous grassland experiment in the world. Nested samples were taken from plots with contrasting inorganic fertilization regimes, and community DNAs were analyzed using the GeoChip-based functional gene array. The slopes of microbial gene-area relationships (GARs) and plant species-area relationships (SARs) were estimated in a plot receivingmore » nitrogen (N), phosphorus (P), and potassium (K) and a control plot without fertilization. Our results indicated that long-term inorganic fertilization significantly increased both microbial GARs and plant SARs. Microbial spatial turnover rates (i.e., z values) were less than 0.1 and were significantly higher in the fertilized plot (0.0583) than in the control plot (0.0449) (P < 0.0001). The z values also varied significantly with different functional genes involved in carbon (C), N, P, and sulfur (S) cycling and with various phylogenetic groups (archaea, bacteria, and fungi). Similarly, the plant SARs increased significantly (P < 0.0001), from 0.225 in the control plot to 0.419 in the fertilized plot. Soil fertilization, plant diversity, and spatial distance had roughly equal contributions in shaping the microbial functional community structure, while soil geochemical variables contributed less. Results indicated that long-term agricultural practice could alter the spatial scaling of microbial biodiversity. Determining the spatial scaling of microbial biodiversity and its response to human activities is important but challenging in microbial ecology. Most studies to date are based on different sites that may not be truly comparable or on short-term perturbations, and hence, the results observed could represent transient responses. This study examined the spatial patterns of microbial communities in response to different fertilization regimes at the Rothamsted Research Experimental Station, which has become an invaluable resource for ecologists, environmentalists, and soil scientists. The current study is the first showing that long-term fertilization has dramatic impacts on the spatial scaling of microbial communities. In addition, by identifying the spatial patterns in response to long-term fertilization and their underlying mechanisms, the study makes fundamental contributions to predictive understanding of microbial biogeography.« less

  1. Over 150 years of long-term fertilization alters spatial scaling of microbial biodiversity

    SciTech Connect (OSTI)

    Liang, Yuting; Wu, Liyou; Clark, Ian M.; Xue, Kai; Yang, Yunfeng; Van Nostrand, Joy D.; Deng, Ye; He, Zhili; McGrath, Steve; Storkey, Jonathan; Hirsch, Penny R.; Sun, Bo; Zhou, Jizhong

    2015-04-07

    Spatial scaling is a critical issue in ecology, but how anthropogenic activities like fertilization affect spatial scaling is poorly understood, especially for microbial communities. Here, we determined the effects of long-term fertilization on the spatial scaling of microbial functional diversity and its relationships to plant diversity in the 150-year-old Park Grass Experiment, the oldest continuous grassland experiment in the world. Nested samples were taken from plots with contrasting inorganic fertilization regimes, and community DNAs were analyzed using the GeoChip-based functional gene array. The slopes of microbial gene-area relationships (GARs) and plant species-area relationships (SARs) were estimated in a plot receiving nitrogen (N), phosphorus (P), and potassium (K) and a control plot without fertilization. Our results indicated that long-term inorganic fertilization significantly increased both microbial GARs and plant SARs. Microbial spatial turnover rates (i.e., z values) were less than 0.1 and were significantly higher in the fertilized plot (0.0583) than in the control plot (0.0449) (P < 0.0001). The z values also varied significantly with different functional genes involved in carbon (C), N, P, and sulfur (S) cycling and with various phylogenetic groups (archaea, bacteria, and fungi). Similarly, the plant SARs increased significantly (P < 0.0001), from 0.225 in the control plot to 0.419 in the fertilized plot. Soil fertilization, plant diversity, and spatial distance had roughly equal contributions in shaping the microbial functional community structure, while soil geochemical variables contributed less. Results indicated that long-term agricultural practice could alter the spatial scaling of microbial biodiversity. Determining the spatial scaling of microbial biodiversity and its response to human activities is important but challenging in microbial ecology. Most studies to date are based on different sites that may not be truly comparable or on short-term perturbations, and hence, the results observed could represent transient responses. This study examined the spatial patterns of microbial communities in response to different fertilization regimes at the Rothamsted Research Experimental Station, which has become an invaluable resource for ecologists, environmentalists, and soil scientists. The current study is the first showing that long-term fertilization has dramatic impacts on the spatial scaling of microbial communities. In addition, by identifying the spatial patterns in response to long-term fertilization and their underlying mechanisms, the study makes fundamental contributions to predictive understanding of microbial biogeography.

  2. Literature Survey of Crude Oil Properties Relevant to Handling...

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

    Relevant to Handling and Fire Safety in Transport - Sandia Energy Energy Search Icon ... Transportation Energy Co-Evolution of Biofuels Lignocellulosic Biomass Microalgae ...

  3. REVERSE RADIATIVE SHOCK LASER EXPERIMENTS RELEVANT TO ACCRETING...

    Office of Scientific and Technical Information (OSTI)

    REVERSE RADIATIVE SHOCK LASER EXPERIMENTS RELEVANT TO ACCRETING STREAM-DISK IMPACT IN INTERACTING BINARIES Citation Details In-Document Search Title: REVERSE RADIATIVE SHOCK LASER ...

  4. Literature Survey of Crude Oil Properties Relevant to Handling...

    Office of Scientific and Technical Information (OSTI)

    Literature Survey of Crude Oil Properties Relevant to Handling and Fire Safety in Transport. Citation Details In-Document Search Title: Literature Survey of Crude Oil Properties ...

  5. Simulation and Theory of Ions at Atmospherically Relevant Aqueous...

    Office of Scientific and Technical Information (OSTI)

    Simulation and Theory of Ions at Atmospherically Relevant Aqueous Liquid-Air Interfaces Citation Details In-Document Search Title: Simulation and Theory of Ions at Atmospherically...

  6. Implications of Export/Import Reporting Requirements in the United States - International Atomic Energy Agency Safeguards Additional Protocol

    SciTech Connect (OSTI)

    Killinger, Mark H.; Benjamin, Eugene L.; McNair, Gary W.

    2001-02-20

    The United States has signed but not ratified the US/IAEA Safeguards Additional Protocol. If ratified, the Additional Protocol will require the US to report to the IAEA certain nuclear-related exports and imports to the IAEA. This document identifies and assesses the issues associated with the US making those reports. For example, some regulatory changes appear to be necessary. The document also attempts to predict the impact on the DOE Complex by assessing the historical flow of exports and imports that would be reportable if the Additional Protocol were in force.

  7. Microsoft PowerPoint - Effective Use of the Safeguards Management Software (SAMS)_John Ballard [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    Effective Use of the Safeguards Management Software (SAMS) John Ballard - NMMSS SAMS 2 What is SAMS? 3 Facility based version of the NMMSS software Functionality and look of the system are similar to NMMSS Benefits to Users Provides NMMSS user the ability to perform edit checks - Minimize errors Input transactions, material balance report, and inventory data - Simplifies reporting 4 Benefits to Users Enables NMMSS analyst to assist the user in real time while preparing facility

  8. Biodiversity Monitoring Using NGS Approaches on Unusual Substrates (2013 DOE JGI Genomics of Energy and Environment 8th Annual User Meeting)

    SciTech Connect (OSTI)

    Gilbert, Tom

    2013-03-01

    Tom Gilbert of the Natural History Museum of Denmark on "Biodiversity monitoring using NGS approaches on unusual substrates" at the 8th Annual Genomics of Energy & Environment Meeting in Walnut Creek, Calif.

  9. Hell and High Water: Practice-Relevant Adaptation Science

    SciTech Connect (OSTI)

    Moss, Richard H.; Meehl, G.; Lemos, Maria Carmen; Smith, J. B.; Arnold, J. R.; Arnott, J. C.; Behar, D.; Brasseur, Guy P.; Broomell, S. B.; Busalacchi, Antonio; Dessai, S.; Ebi, Kristie L.; Edmonds, James A.; Furlow, J.; Goddard, L.; Hartmann, Holly; Hurrell, Jim; Katzenberger, J. W.; Liverman, D. M.; Mote, Phil; Moser, S. C.; Kumar, A.; Pulwarty, Roger; Seyller, E. A.; Turner, B.L.; Washington, Warren M.; Wilbanks, Thomas

    2013-11-08

    Recent extreme weather such as Hurricane Sandy and the 2012 drought demonstrate the vulnerability of the United States to climate extremes in the present and point to the potential for increased future damages under a changing climate. They also provide lessons for reducing harm and realizing any potential benefits. Preparedness measures – also referred to as adaptation – can cost-effectively increase resilience today and in the future. The upfront costs will be more than offset by reductions in property damage, lives and livelihoods lost, and expensive post-disaster recovery processes. While others have addressed use of science for adaptation in specific sectors including biodiversity (Heller and Zavaleta, 2009) and freshwater ecosystem management (Wilby et al., 2010), or by simply taking a more pragmatic approach to adaptation under uncertainty (Hallegatte, 2009), here the authors make the case that a new, comprehensive approach is needed to create and use science to inform adaptations with applicable and sound knowledge (Kerr et al., 2011).

  10. Ultra-secure RF Tags for Safeguards and Security - SBIR Phase II Final Report

    SciTech Connect (OSTI)

    Twogood, Richard E

    2015-01-27

    This is the Final Report for the DOE Phase II SBIR project “Ultra-secure RF Tags for Safeguards and Security.” The topics covered herein include technical progress made, progress against the planned milestones and deliverables, project outcomes (results, collaborations, intellectual property, etc.), and a discussion on future expectations of deployment and impacts of the results of this work. In brief, all planned work for the project was successfully completed, on or ahead of schedule and on budget. The major accomplishment was the successful development of a very advanced passive ultra-secure RFID tag system with combined security features unmatched by any commercially available ones. These tags have high-level dynamic encrypted authentication, a novel tamper-proofing mechanism, system software including graphical user interfaces and networking, and integration with a fiber-optic seal mechanism. This is all accomplished passively (with no battery) by incorporating sophisticated hardware in the tag which harvests the energy from the RFID readers that are interrogating the tag. Based on initial feedback (and deployments) at DOE’s Lawrence Livermore National Laboratory (LLNL), it is anticipated these tags and their offspring will meet DOE and international community needs for highly secure RFID systems. Beyond the accomplishment of those original objectives for the ultra-secure RF tags, major new spin-off thrusts from the original work were identified and successfully pursued with the cognizance of the DOE sponsor office. In particular, new classes of less sophisticated RFID tags were developed whose lineage derives from the core R&D thrusts of this SBIR. These RF “tag variants” have some, but not necessarily all, of the advanced characteristics described above and can therefore be less expensive and meet far wider markets. With customer pull from the DOE and its national laboratories, new RFID tags and systems (including custom readers and software) for government needs in asset management and tracking were developed. These were tested at a national laboratory and other government facilities, and resulted in immediate procurement actions by the government and deployment of these new systems. Thus, commercialization of the results of this Phase II DOE SBIR was already underway before the end of the SBIR itself. More importantly, operations involving asset management at selected DoE and government sites are already being impacted favorably and could have much broader impacts in the near future.

  11. Toward a Fieldable Atomic Mass Spectrometer for Safeguards Applications: Sample Preparation and Ionization

    SciTech Connect (OSTI)

    Barinaga, Charles J.; Hager, George J.; Hart, Garret L.; Koppenaal, David W.; Marcus, R. Kenneth; Jones, Sarah MH; Manard, Benjamin T.

    2014-10-31

    The International Atomic Energy Agency’s (IAEA’s) long-term research and development plan calls for the development of new methods to detect misuse at nuclear fuel cycle facilities such as reprocessing and enrichment plants. At enrichment plants, for example, the IAEA’s contemporary safeguards approaches are based on a combination of routine and random inspections that include collection of UF6 samples from in-process material and selected cylinders for subsequent analyses. These analyses include destructive analysis (DA) in a laboratory (typically by mass spectrometry [MS]) for isotopic characterization, and environmental sampling (ES) for subsequent laboratory elemental and isotopic analysis (also both typically by MS). One area of new method development includes moving this kind of isotope ratio analytical capability for DA and ES activities into the field. Some of the reasons for these developments include timeliness of results, avoidance of hazardous material shipments, and guidance for additional sample collecting. However, this capability does not already exist for several reasons, such as that most lab-based chemical and instrumental methods rely on laboratory infrastructure (highly trained staff, power, space, hazardous material handling, etc.) and require significant amounts of consumables (power, compressed gases, etc.). In addition, there are no currently available, fieldable instruments for atomic or isotope ratio analysis. To address these issues, Pacific Northwest National Laboratory (PNNL) and collaborator, Clemson University, are studying key areas that limit the fieldability of isotope ratio mass spectrometry for atomic ions: sample preparation and ionization, and reducing the physical size of a fieldable mass spectrometer. PNNL is seeking simple and robust techniques that could be effectively used by inspectors who may have no expertise in analytical MS. In this report, we present and describe the preliminary findings for three candidate techniques: matrix-assisted laser desorption/ionization (MALDI) MS, liquid sampling-atmospheric pressure glow discharge (LS-APGD), and laser ablation/ionization (LAI) MS at atmospheric pressure. Potential performance metrics for these techniques will be presented, including detectability, response, isotope ratio accuracy and precision, and ease of use.

  12. Safeguards Verification Measurements using Laser Ablation, Absorbance Ratio Spectrometry in Gaseous Centrifuge Enrichment Plants

    SciTech Connect (OSTI)

    Anheier, Norman C.; Cannon, Bret D.; Qiao, Hong; Phillips, Jon R.

    2012-07-01

    Laser Ablation Absorbance Ratio Spectrometry (LAARS) is a new verification measurement technology under development at the US Department of Energy’s (DOE) Pacific Northwest National Laboratory (PNNL). LAARS uses three lasers to ablate and then measure the relative isotopic abundance of uranium compounds. An ablation laser is tightly focused on uranium-bearing solids producing a small plume containing uranium atoms. Two collinear wavelength-tuned spectrometry lasers transit through the plume and the absorbance of U-235 and U-238 isotopes are measured to determine U-235 enrichment. The measurement has high relative precision and detection limits approaching the femtogram range for uranium. It is independent of chemical form and degree of dilution with nuisance dust and other materials. High speed sample scanning and pinpoint characterization allow measurements on millions of particles/hour to detect and analyze the enrichment of trace uranium in samples. The spectrometer is assembled using commercially available components at comparatively low cost, and features a compact and low power design. Future designs can be engineered for reliable, autonomous deployment within an industrial plant environment. Two specific applications of the spectrometer are under development: 1) automated unattended aerosol sampling and analysis and 2) on-site small sample destructive assay measurement. The two applications propose game-changing technological advances in gaseous centrifuge enrichment plant (GCEP) safeguards verification. The aerosol measurement instrument, LAARS-environmental sampling (ES), collects aerosol particles from the plant environment in a purpose-built rotating drum impactor and then uses LAARS-ES to quickly scan the surface of the impactor to measure the enrichments of the captured particles. The current approach to plant misuse detection involves swipe sampling and offsite analysis. Though this approach is very robust it generally requires several months to obtain results from a given sample collection. The destructive assay instrument, LAARS-destructive assay (DA), uses a simple purpose-built fixture with a sampling planchet to collect adsorbed UF6 gas from a cylinder valve or from a process line tap or pigtail. A portable LAARS-DA instrument scans the microgram quantity of uranium collected on the planchet and the assay of the uranium is measured to ~0.15% relative precision. Currently, destructive assay samples for bias defect measurements are collected in small sample cylinders for offsite mass spectrometry measurement.

  13. Implementation of Unclassified Controlled Nuclear Information guidelines for fixed-site safeguards and security (FSSS) at Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Rood, P.L.

    1995-02-01

    Unclassified Controlled Nuclear Information (UCNI) is one type of sensitive information that DOE employees, including computer users, must now identify and protect. Guidelines to identify information as UCNI are gradually being put in place. The publication of Unclassified Controlled Nuclear Information Topical Guideline for Fixed-Site Safeguards and Security, TG-FSSS-1, is a major step in the development of UCNI guidelines. This DOE published guide cuts across and addresses many different programmatic areas including automated data processing. Our local guideline, Los Alamos National Laboratory Unclassified Controlled Nuclear Information Guideline for Fixed-Site Safeguards and Security, IG-LAFSSS-1, is based on TG-FSSS-1. In this paper, I plan to discuss the background of UCNI, the definition of UCNI, information that qualifies as UCNI, the consequences of information being UCNI, the development of UCNI guidelines, TG-FSSS-1 and IG-LAFSSS-1, the relationship of UCNI to classification, and the implementation of the IG-LAFSSS-1 at Los Alamos.

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

    SciTech Connect (OSTI)

    Bathke, Charles G; Wallace, Richard K; Ireland, John R; Johnson, M W; Hase, Kevin R; Jarvinen, Gordon D; Ebbinghaus, Bartley B; Sleaford, Brad W; Collins, Brian A; Robel, Martin; Bradley, Keith S; Prichard, Andrew W; Smith, Brian W

    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 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. The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.

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

    SciTech Connect (OSTI)

    Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

    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 to 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.

  16. Implementation of Tunneling Passivated Contacts into Industrially Relevant

    Office of Scientific and Technical Information (OSTI)

    n-Cz Si Solar Cells (Conference) | SciTech Connect Implementation of Tunneling Passivated Contacts into Industrially Relevant n-Cz Si Solar Cells Citation Details In-Document Search Title: Implementation of Tunneling Passivated Contacts into Industrially Relevant n-Cz Si Solar Cells We identify bottlenecks, and propose solutions, to implement a B-diffused front emitter and a backside pc-Si/SiO2 pasivated tunneling contact into high efficiency n-Cz Si cells in an industrially relevant way. We

  17. Relevance of the second law of thermodynamics to energy conservation

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    An analysis is presented of the potential relevance of the use of analytical tools based on the Second Law of thermodynamics to existing federal programs for energy conservation in the industrial, transportation, buildings, and utility sectors in the US. (LCL)

  18. Experimental demonstration of fusion-relevant conditions in magnetized

    Office of Scientific and Technical Information (OSTI)

    liner inertial fusion (Journal Article) | DOE PAGES Experimental demonstration of fusion-relevant conditions in magnetized liner inertial fusion « Prev Next » Title: Experimental demonstration of fusion-relevant conditions in magnetized liner inertial fusion This Letter presents results from the first fully integrated experiments testing the magnetized liner inertial fusion concept [S.A. Slutz et al., Phys. Plasmas 17, 056303 (2010)], in which a cylinder of deuterium gas with a preimposed

  19. Experimental demonstration of fusion-relevant conditions in magnetized

    Office of Scientific and Technical Information (OSTI)

    liner inertial fusion (Journal Article) | DOE PAGES Experimental demonstration of fusion-relevant conditions in magnetized liner inertial fusion « Prev Next » Title: Experimental demonstration of fusion-relevant conditions in magnetized liner inertial fusion × You are accessing a document from the Department of Energy's (DOE) Public Access Gateway for Energy & Science (PAGES). This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a

  20. Influence of Mechanical Properties Relevant to Standoff Deflection of

    Office of Scientific and Technical Information (OSTI)

    Hazardous Asteroids (Conference) | SciTech Connect Influence of Mechanical Properties Relevant to Standoff Deflection of Hazardous Asteroids Citation Details In-Document Search Title: Influence of Mechanical Properties Relevant to Standoff Deflection of Hazardous Asteroids Authors: Lomov, I ; Herbold, E B ; Antoun, T H ; Miller, P Publication Date: 2012-06-04 OSTI Identifier: 1077193 Report Number(s): LLNL-PROC-559642 DOE Contract Number: W-7405-ENG-48 Resource Type: Conference Resource

  1. American Indian Policy and Relevant DOE and Executive Orders | Department

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

    of Energy Tribal Programs » American Indian Policy and Relevant DOE and Executive Orders American Indian Policy and Relevant DOE and Executive Orders Over the course of American history, the Federal government's relationship with Indian Tribes has been defined and modified by treaties, executive orders, court decisions, specific legislation passed by Congress, and regulations. Important rights were guaranteed to Tribes by treaty, with many of these rights still enforceable today. Case law,

  2. Evolution of twist-3 multiparton correlation functions relevant to single

    Office of Scientific and Technical Information (OSTI)

    transverse-spin asymmetry (Journal Article) | SciTech Connect Evolution of twist-3 multiparton correlation functions relevant to single transverse-spin asymmetry Citation Details In-Document Search Title: Evolution of twist-3 multiparton correlation functions relevant to single transverse-spin asymmetry We construct two sets of twist-3 correlation functions that are responsible for generating the novel single transverse-spin asymmetry in the QCD collinear factorization approach. We derive

  3. Center for Gas Separations Relevant to Clean Energy Technologies (CGS) |

    Office of Science (SC) Website

    U.S. DOE Office of Science (SC) Gas Separations Relevant to Clean Energy Technologies (CGS) Energy Frontier Research Centers (EFRCs) EFRCs Home Centers EFRC External Websites Research Science Highlights News & Events Publications History Contact BES Home Centers Center for Gas Separations Relevant to Clean Energy Technologies (CGS) Print Text Size: A A A FeedbackShare Page CGS Header Director Jeffrey Long Lead Institution University of California, Berkeley Year Established 2009 Mission

  4. Theoretical and experimental studies of electrified interfaces relevant to

    Office of Scientific and Technical Information (OSTI)

    energy storage. (Technical Report) | SciTech Connect Technical Report: Theoretical and experimental studies of electrified interfaces relevant to energy storage. Citation Details In-Document Search Title: Theoretical and experimental studies of electrified interfaces relevant to energy storage. Advances in technology for electrochemical energy storage require increased understanding of electrolyte/electrode interfaces, including the electric double layer structure, and processes involved in

  5. UV-Vis Spectroscopy as a Tool for Safeguards; Instrumentation installation and fundamental data collection

    SciTech Connect (OSTI)

    Smith, Nicholas A.; Krebs, John F.; Hebden, Andrew S.

    2015-09-20

    Two spectrophotometric process monitors, one optimized for high concentration (approximately 10 g/L) and one for trace levels (approximately 10 ppm),were developed at Argonne and installed at the SRS H-Canyon facility for field testing. These systems were built of Commercial-Off-The-Shelf components utilizing a custom, facility-specific hardware interface. The systems directly provide a qualitative measurement of process chemistry (i.e. valence state). With appropriate calibrations the systems could provide quantitative data. Laboratory tests were performed to determine the spectrophotometric molar absorptivity coefficients for relevant actinide and transition metals of interest.

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

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

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

    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

  7. US-ROK Action Sheet 34: Safeguards Application of a Hand-held Mechanically Cooled Germanium Spectrometer

    SciTech Connect (OSTI)

    Dreyer, J.; Burks, M.; Ham, Y.; Kwak, S.

    2015-10-20

    This report summarizes results of Action Sheet 34 - for the cooperative efforts on the field testing and evaluation of a high-resolution, hand-held, gamma-ray spectrometer, known as SPG (Spectroscopic Planar Germanium), for safeguards application such as short notice inspections, UF6 analysis, enrichment determination, and other potential applications. The Spectroscopic Planar Germanium (SPG) has been demonstrated IAEA Physical Inventory Verification (PIV) in South Korea. This field test was a success and the feedback provided by KINAC, IAEA, and national laboratory staff was used to direct efforts to improve the instrument this year. Key points in this report include measurement results from PIV, analysis of spectra with commercially available Ortec U235 and PC-FRAM, and completion of tripod and tungsten collimator and integration of user feedback.

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

    SciTech Connect (OSTI)

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

    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 can 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.

  9. Racing with Relevance: Green Racing Redefines Sustainable Motorsports |

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

    Department of Energy Racing with Relevance: Green Racing Redefines Sustainable Motorsports Racing with Relevance: Green Racing Redefines Sustainable Motorsports October 16, 2014 - 7:40pm Addthis Known as the “race within the race,” the Green Racing initiative’s Green Challenge Award recognizes the teams and manufacturers of the TUDOR United SportsCar Championship that go the farthest and fastest with the smallest environmental footprint. | Photo credit: Rick Gillam. Known as

  10. A feasibility study for the application of radiation monitoring for international safeguards at an Atomic Vapor Laser Isotope Separation (AVLIS) facility

    SciTech Connect (OSTI)

    Miller, M.C.; Adams, E.L.; Li, T.K.; Strittmatter, R.B.

    1994-09-01

    The authors evaluated the feasibility of using radiation monitoring for international safeguards at an Atomic Vapor Laser Isotope Separation (AVLIS) uranium enrichment facility. Techniques employing neutron and gamma-ray detection were investigated and evaluated to determine their applicability for detecting highly enriched uranium. This task is complicated because classified information must not be revealed in the inspection activity. Within this constraint, the authors concluded that (1) neutron methods will not be a viable option for measurements at the separator module, (2) gamma-ray measurements at the separator module are possible but cannot be adequately verified, and (3) neutron and gamma-ray approaches are suitable for measurements of feed, product, and tails. If international safeguards are applied at an AVLIS facility, neutron and gamma-ray instruments will need to be designed and optimized.

  11. Shock-ignition relevant experiments with planar targets on OMEGA

    SciTech Connect (OSTI)

    Hohenberger, M.; Hu, S. X.; Anderson, K. S.; Boehly, T. R.; Sangster, T. C.; Seka, W.; Stoeckl, C.; Yaakobi, B.; Theobald, W.; Lafon, M.; Nora, R.; Fusion Science Center, University of Rochester, Rochester, New York 14623 ; Betti, R.; Meyerhofer, D. D.; Fusion Science Center, University of Rochester, Rochester, New York 14623; Departments of Mechanical Engineering and Physics, University of Rochester, Rochester, New York 14627 ; Casner, A.; Fratanduono, D. E.; Ribeyre, X.; Schurtz, G.

    2014-02-15

    We report on laser-driven, strong-shock generation and hot-electron production in planar targets in the presence of a pre-plasma at shock-ignition (SI) relevant laser and pre-plasma conditions. 2-D simulations reproduce the shock dynamics well, indicating ablator shocks of up to 75 Mbar have been generated. We observe hot-electron temperatures of ?70?keV at intensities of 1.4?×?10{sup 15}?W/cm{sup 2} with multiple overlapping beams driving the two-plasmon decay instability. When extrapolated to SI-relevant intensities of ?10{sup 16}?W/cm{sup 2}, the hot electron temperature will likely exceed 100?keV, suggesting that tightly focused beams without overlap are better suited for launching the ignitor shock.

  12. Environmental screening tools for assessment of infrastructure plans based on biodiversity preservation and global warming (PEIT, Spain)

    SciTech Connect (OSTI)

    Garcia-Montero, Luis G.

    2010-04-15

    Most Strategic Environmental Assessment (SEA) research has been concerned with SEA as a procedure, and there have been relatively few developments and tests of analytical methodologies. The first stage of the SEA is the 'screening', which is the process whereby a decision is taken on whether or not SEA is required for a particular programme or plan. The effectiveness of screening and SEA procedures will depend on how well the assessment fits into the planning from the early stages of the decision-making process. However, it is difficult to prepare the environmental screening for an infrastructure plan involving a whole country. To be useful, such methodologies must be fast and simple. We have developed two screening tools which would make it possible to estimate promptly the overall impact an infrastructure plan might have on biodiversity and global warming for a whole country, in order to generate planning alternatives, and to determine whether or not SEA is required for a particular infrastructure plan.

  13. The administrative record: What constitutes a relevant NEPA document?

    SciTech Connect (OSTI)

    Brennan, C.; Every, D.V.

    1997-08-01

    Neither the National Environmental Policy Act (NEPA) nor the Council on Environmental Quality (CEQ) Regulations for implementing NEPA address the contents of an administrative record (AR). The AR typically contains the documents and information used in the development of NEPA documents and supports the decisions defined in them. The AR also should include all records pertaining to public comments and all records demonstrating the project`s efforts to involve the public. This paper will attempt to establish comprehensive guidelines to be used in assembling an AR in support of a NEPA document. While the AR is created to support an agency`s decisions, its main purpose is to demonstrate that an agency has adhered to NEPA`s procedural requirements. The CEQ requires that relevant environmental documents, comments and responses be part of the record in formal rulemaking or adjudicatory proceedings. Other Federal agency NEPA implementing procedures generally do not provide additional guidance on the contents of an AR. The CEQ and DOE guidelines make reference to the inclusion of relevant NEPA documents. The guidelines established in this paper will aid the NEPA practitioner in determining what constitutes a relevant NEPA document.

  14. Status of the United States-Russian Federation safeguards, transparency and irreversibility (STI) initiative for nuclear arms reductions

    SciTech Connect (OSTI)

    Czajkowski, A.F.; Bieniawski, A.J.; Percival, C.M.

    1996-12-31

    The US-Russian Federation initiative to provide safeguards, transparency, and irreversibility (STI) of nuclear arms reductions has been emphasized by several Presidential Joint Summit Statements as well as various agreements between the two parties. Beginning with the US and Russian Federation agreement in March, 1994, to host reciprocal inspections to confirm the stockpiles of plutonium removed from nuclear weapons, the US and Russia have been negotiating an STI regime to increase the transparency and irreversibility of nuclear arms reduction. In December, 1994, the US presented a paper to the Russian Federation proposing a regime of specific transparency measures to provide broader transparency and irreversibility of nuclear arms reductions. Presently the US considers STI to consist of the following measures: (1) agreement for cooperation (AFC); (2) stockpile data exchange agreement (SDEA); (3) mutual reciprocal inspections (MRI); (4) spot checks to confirm data exchanges (SC); and (5) limited Chain of Custody of Warheads Being Dismantled (LCC). The US and Russian have begun negotiations, which are in various stages of progress, on the first three of these measures. This paper will present a brief historical background of STI and discuss the transparency measures including the status of negotiation for each of the measures.

  15. Emergency preparedness source term development for the Office of Nuclear Material Safety and Safeguards-Licensed Facilities

    SciTech Connect (OSTI)

    Sutter, S.L.; Mishima, J.; Ballinger, M.Y.; Lindsey, C.G.

    1984-08-01

    In order to establish requirements for emergency preparedness plans at facilities licensed by the Office of Nuclear Materials Safety and Safeguards, the Nuclear Regulatory Commission (NRC) needs to develop source terms (the amount of material made airborne) in accidents. These source terms are used to estimate the potential public doses from the events, which, in turn, will be used to judge whether emergency preparedness plans are needed for a particular type of facility. Pacific Northwest Laboratory is providing the NRC with source terms by developing several accident scenarios for eleven types of fuel cycle and by-product operations. Several scenarios are developed for each operation, leading to the identification of the maximum release considered for emergency preparedness planning (MREPP) scenario. The MREPP scenarios postulated were of three types: fire, tornado, and criticality. Fire was significant at oxide fuel fabrication, UF/sub 6/ production, radiopharmaceutical manufacturing, radiopharmacy, sealed source manufacturing, waste warehousing, and university research and development facilities. Tornadoes were MREPP events for uranium mills and plutonium contaminated facilities, and criticalities were significant at nonoxide fuel fabrication and nuclear research and development facilities. Techniques for adjusting the MREPP release to different facilities are also described.

  16. Attachment L-2a Relevant Corporate Experience Form

    National Nuclear Security Administration (NNSA)

    [Submit in Volume II, TAB 1] DE-SOL-0008449 Attachment L-2a Relevant Corporate Experience Form 1) Experience Submission Number: (Start with 1 and number consecutively) 2). Name and Address of Offeror or Team Member 3. Complete Name/Title of Contract and Location/Address of project/contract 3. Project Owner Name and Address 4. Contract Number and Type of Contract 5. Date of Contract Award 6. Date Work Commenced 7. Date Work Ended 8. Initial Contract Price/Cost and Fee 9. Final Amount

  17. Feasibility Study on the Use of On-line Multivariate Statistical Process Control for Safeguards Applications in Natural Uranium Conversion Plants

    SciTech Connect (OSTI)

    Ladd-Lively, Jennifer L

    2014-01-01

    The objective of this work was to determine the feasibility of using on-line multivariate statistical process control (MSPC) for safeguards applications in natural uranium conversion plants. Multivariate statistical process control is commonly used throughout industry for the detection of faults. For safeguards applications in uranium conversion plants, faults could include the diversion of intermediate products such as uranium dioxide, uranium tetrafluoride, and uranium hexafluoride. This study was limited to a 100 metric ton of uranium (MTU) per year natural uranium conversion plant (NUCP) using the wet solvent extraction method for the purification of uranium ore concentrate. A key component in the multivariate statistical methodology is the Principal Component Analysis (PCA) approach for the analysis of data, development of the base case model, and evaluation of future operations. The PCA approach was implemented through the use of singular value decomposition of the data matrix where the data matrix represents normal operation of the plant. Component mole balances were used to model each of the process units in the NUCP. However, this approach could be applied to any data set. The monitoring framework developed in this research could be used to determine whether or not a diversion of material has occurred at an NUCP as part of an International Atomic Energy Agency (IAEA) safeguards system. This approach can be used to identify the key monitoring locations, as well as locations where monitoring is unimportant. Detection limits at the key monitoring locations can also be established using this technique. Several faulty scenarios were developed to test the monitoring framework after the base case or normal operating conditions of the PCA model were established. In all of the scenarios, the monitoring framework was able to detect the fault. Overall this study was successful at meeting the stated objective.

  18. Chemical kinetic modeling of component mixtures relevant to gasoline

    SciTech Connect (OSTI)

    Mehl, M; Curran, H J; Pitz, W J; Westbrook, C K

    2009-02-13

    Real fuels are complex mixtures of thousands of hydrocarbon compounds including linear and branched paraffins, naphthenes, olefins and aromatics. It is generally agreed that their behavior can be effectively reproduced by simpler fuel surrogates containing a limited number of components. In this work, a recently revised version of the kinetic model by the authors is used to analyze the combustion behavior of several components relevant to gasoline surrogate formulation. Particular attention is devoted to linear and branched saturated hydrocarbons (PRF mixtures), olefins (1-hexene) and aromatics (toluene). Model predictions for pure components, binary mixtures and multi-component gasoline surrogates are compared with recent experimental information collected in rapid compression machine, shock tube and jet stirred reactors covering a wide range of conditions pertinent to internal combustion engines. Simulation results are discussed focusing attention on the mixing effects of the fuel components.

  19. Agreement Between The United States of America and The International Atomic Energy Agency for the Application of Safeguards in the United States

    National Nuclear Security Administration (NNSA)

    Agreement Between The United States of America and The International Atomic Energy Agency for the Application of Safeguards in the United States Signed at Vienna November 18, 1977 Ratification advised by U.S. Senate July 2, 1980 Ratified by U.S. President July 31, 1980 Entered into force December 9, 1980 Proclaimed by U.S. President December 31, 1980 Whereas the United States of America (hereinafter referred to as the "United States") is a Party to the Treaty on the Non-Proliferation

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

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

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

    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.

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

    SciTech Connect (OSTI)

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

    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.

  2. Chemical kinetic modeling of component mixtures relevant to gasoline

    SciTech Connect (OSTI)

    Mehl, M; Curran, H J; Pitz, W J; Dooley, S; Westbrook, C K

    2008-05-29

    Detailed kinetic models of pyrolysis and combustion of hydrocarbon fuels are nowadays widely used in the design of internal combustion engines and these models are effectively applied to help meet the increasingly stringent environmental and energetic standards. In previous studies by the combustion community, such models not only contributed to the understanding of pure component combustion, but also provided a deeper insight into the combustion behavior of complex mixtures. One of the major challenges in this field is now the definition and the development of appropriate surrogate models able to mimic the actual features of real fuels. Real fuels are complex mixtures of thousands of hydrocarbon compounds including linear and branched paraffins, naphthenes, olefins and aromatics. Their behavior can be effectively reproduced by simpler fuel surrogates containing a limited number of components. Aside the most commonly used surrogates containing iso-octane and n-heptane only, the so called Primary Reference Fuels (PRF), new mixtures have recently been suggested to extend the reference components in surrogate mixtures to also include alkenes and aromatics. It is generally agreed that, including representative species for all the main classes of hydrocarbons which can be found in real fuels, it is possible to reproduce very effectively in a wide range of operating conditions not just the auto-ignition propensity of gasoline or Diesel fuels, but also their physical properties and their combustion residuals [1]. In this work, the combustion behavior of several components relevant to gasoline surrogate formulation is computationally examined. The attention is focused on the autoignition of iso-octane, hexene and their mixtures. Some important issues relevant to the experimental and modeling investigation of such fuels are discussed with the help of rapid compression machine data and calculations. Following the model validation, the behavior of mixtures is discussed on the basis of computational results.

  3. INFCIRC/288 - The Text of the Agreement of 18 November 1977 Between the United States of America and the Agency for the Application of Safeguards in the United States of America

    National Nuclear Security Administration (NNSA)

    ичгоо INF -//f£#-lNFClRC/288 . , . . _ . December 1981 International Atomic Energy Agency GENERAL D i s t r . INFORMATION CIRCULAR O r i g i n a l : ENGLISH THE TEXT OF THE AGREEMENT OF 18 NOVEMBER 1977 BETWEEN THE UNITED STATES OF AMERICA AND THE AGENCY FOR THE APPLICATION OF SAFEGUARDS IN THE UNITED STATES OF AMERICA 1. The text [l] of the Agreement of 18 November 1977 and of the Protocol thereto between the United States of America and the Agency for the appli- cation of safeguards in

  4. Evaluation of MC&A Effectiveness and Its Contribution to the Safeguarding Of Nuclear Material with Assurance Assessments

    SciTech Connect (OSTI)

    Schlegel, Steven C.

    2007-07-10

    Safeguards and Security within the DOE complex has struggled with integrating MC&A and Physical Security together in a single model. Attempts were made to incorporate MC&A elements that provide detection into vulnerability assessments. While this approach has met with some success, it does not fully address the different contributions that each make to nuclear material protection. Protection measures that rely on the lack of alarms to imply all nuclear material is still present, in the correct location, and intended use are limited due to their passive nature. A highly effective system may provide confidence that all nuclear material is still present, but it does not provide assurance that it is there. MC&A, through active measures that confirm or verify the actual presence of nuclear material, provides assurance that all of the nuclear material is controlled and accounted for. This paper presents a model that combines the detection and assessment functions from vulnerability assessments with assurance activities provided by MC&A to provide an integrated model that can be used for evaluation of current systems, evaluation of system changes, and monitoring assurance in real time based upon operational activities. 1.0 OVERVIEW Material control and accounting (MC&A) and physical security provide complementary measures that can effectively protect nuclear material against the threats of theft, diversion, and sabotage. Tools have been introduced to evaluate and quantify the effectiveness of different protective measures and schemes, but the ability to fully model the contribution of MC&A to protection effectiveness has been limited. This is due, in part, by not fully recognizing that the two areas contribute differently, but not independently, to protection effectiveness. Physical protection provides detection, assessment, interruption, neutralization, and deterrence against a threat. Except for deterrence, mathematical models have been developed to quantify the contributions of the other elements to obtain an effectiveness value. MC&A helps contribute to this model by providing some detection capabilities and providing assessment under some circumstances to ensure all of the nuclear material is still present as documented. A strong program provides great confidence that nuclear material remains in the location and amounts documented in the nuclear material accounting system. Physical protection is not perfect, however, necessitating MC&A contribution.

  5. Exposure-Relevant Ozone Chemistry in Occupied Spaces

    SciTech Connect (OSTI)

    Coleman, Beverly Kaye

    2009-04-01

    Ozone, an ambient pollutant, is transformed into other airborne pollutants in the indoor environment. In this dissertation, the type and amount of byproducts that result from ozone reactions with common indoor surfaces, surface residues, and vapors were determined, pollutant concentrations were related to occupant exposure, and frameworks were developed to predict byproduct concentrations under various indoor conditions. In Chapter 2, an analysis is presented of secondary organic aerosol formation from the reaction of ozone with gas-phase, terpene-containing consumer products in small chamber experiments under conditions relevant for residential and commercial buildings. The full particle size distribution was continuously monitored, and ultrafine and fine particle concentrations were in the range of 10 to>300 mu g m-3. Particle nucleation and growth dynamics were characterized.Chapter 3 presents an investigation of ozone reactions with aircraft cabin surfaces including carpet, seat fabric, plastics, and laundered and worn clothing fabric. Small chamber experiments were used to determine ozone deposition velocities, ozone reaction probabilities, byproduct emission rates, and byproduct yields for each surface category. The most commonly detected byproducts included C1?C10 saturated aldehydes and skin oil oxidation products. For all materials, emission rates were higher with ozone than without. Experimental results were used to predict byproduct exposure in the cabin and compare to other environments. Byproduct levels are predicted to be similar to ozone levels in the cabin, which have been found to be tens to low hundreds of ppb in the absence of an ozone converter. In Chapter 4, a model is presented that predicts ozone uptake by and byproduct emission from residual chemicals on surfaces. The effects of input parameters (residue surface concentration, ozone concentration, reactivity of the residue and the surface, near-surface airflow conditions, and byproduct yield) were explored. In Chapter 5, the reaction of ozone with permethrin, a residual insecticide used in aircraft cabins, to form phosgene is investigated. A derivatization technique was developed to detect phosgene at low levels, and chamber experiments were conducted with permethrin-coated cabin materials. It was determined that phosgene formation, if it occurs in the aircraft cabin, is not likely to exceed the relevant, health-based phosgene exposure guidelines.

  6. Behavior of nanoceria in biologically-relevant environments

    SciTech Connect (OSTI)

    Kumar, Amit; Das, Soumen; Munusamy, Prabhakaran; Self, William; Baer, Donald R.; Sayle, Dean C.; Seal, Sudipta

    2014-09-08

    Cerium oxide nanoparticles (CNPs) have gained a considerable attention in biological research due to their anti-oxidant like behaviour and regenerative nature. The current literature on CNPs reports many successful attempts on harnessing the beneficial therapeutic properties in biology. However studies have also shown toxicity effect with some types of CNPs. This review discusses issues associated with the behaviours of CNPs in biological systems and identifies key knowledge gaps. We explore how salient physicochemical properties (size, surface chemistry, surface stabilizers) contribute to the potential positive and negative aspects of nanoceria in biological systems. Based on variations of results reported in the literature, important issues need to be addressed. Are we really studying the same particles with slight variations in size and physicochemical properties or do the particles being examined have fundamentally different behaviours? Are the variations observed in the result of differences in the initial properties of the particles or the results of downstream effects that emerge as the particles are prepared for specific studies and they interact with biological or other environmental moieties? How should particles be appropriately prepared for relevant environmental/toxicology/safety studies? It is useful to recognize that nanoparticles encompass some of the same complexities and variability associated with biological components

  7. Safeguards and Security Program

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

    1995-09-28

    Ensures appropriate levels of protection against unauthorized access; theft, diversion, loss of custody, or destruction of nuclear weapons, or weapons components; espionage; loss or theft of classified matter or Government property; and other hostile acts that may cause unacceptable adverse impacts on national security or on the health and safety of Department of Energy (DOE) and contractor employees, the public, or the environment. DOE N 251.40, dated 5/3/01, extends this directive until 12/31/01. Cancels DOE 5630.11B, DOE 5630.13A, DOE 5630.14A, DOE 5630.15, DOE 5630.16A, DOE 5630.17, DOE 5631.1C, DOE 5631.4A, DOE 5634.1B, DOE 5634.3, DOE 5639.3, and Chapter IX of DOE M 5632.1C-1

  8. Safeguards and Security Briefing

    National Nuclear Security Administration (NNSA)

    Rail Shipment Via Inter-Modal Transfer IMT Cask Status 0 3 6 9 12 15 FMF YM En Route Generator Transportation Operations Center * IMT intermodal transfer facility * FMFfleet...

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

    SciTech Connect (OSTI)

    Peters, William A; Smith, Michael Scott; Clement, Ryan; Tan, Wanpeng; Stech, Ed; Cizewski, J A; Febbraro, Michael; Madurga Flores, Miguel

    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 the 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 of Notre Dame (UND), will focus on three specific items: (1) making a precision (better than 10 %) determination of the absolute cross section of the 19F(α,n)22Na reaction as a function of energy; (2) determining the spectrum of neutrons and γ-rays emitted from 19F(α,n)22Na over an energy range pertinent to NDA; and (3) performing simulations with this new cross section to extract the neutron yield (neutrons/gram/second) and resulting neutron- and gamma ray-spectra when α particles interact with fluorine nuclei in actinide samples, to aid in the design and reduce uncertainty of future NDA measurements and simulations.

  10. Sustaining International CBRN Centers of Excellence with a Focus on Nuclear Security and Safeguards: Initial Scoping Session London, 23-24 September 2013 SUMMARY REPORT

    SciTech Connect (OSTI)

    Anderson, Roger G.; Frazar, Sarah L.

    2013-12-12

    This report provides a summary-level description of the key information, observations, ideas, and recommendations expressed during the subject meeting. The report is organized to correspond to the meeting agenda provided in Appendix 1 and includes references to several of the participants listed in Appendix 2 .The meeting venue was Lloyd’s Register in the City of London. Lloyd’s Register graciously accommodated the request of The Pacific Northwest Laboratory (PNNL) with whom it works on various safeguards activities commissioned by NNSA. PNNL and NNSA also shared the goal of the meeting/study with the United Kingdom (UK) Foreign and Commonwealth Office (FCO) and the Department of Energy and Climate Change with whom they coordinated the participant list.

  11. An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle

    SciTech Connect (OSTI)

    Evans, Louise G; Croft, Stephen; Swinhoe, Martyn T; Tobin, S. J.; Boyer, B. D.; Menlove, H. O.; Schear, M. A.; Worrall, Andrew

    2010-11-24

    Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

  12. An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle

    SciTech Connect (OSTI)

    Evans, Louise G; Croft, Stephen; Swinhoe, Martyn T; Tobin, S. J.; Menlove, H. O.; Schear, M. A.; Worrall, Andrew

    2011-01-13

    Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/ or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

  13. REVERSE RADIATIVE SHOCK LASER EXPERIMENTS RELEVANT TO ACCRETING STREAM-DISK

    Office of Scientific and Technical Information (OSTI)

    IMPACT IN INTERACTING BINARIES (Journal Article) | SciTech Connect REVERSE RADIATIVE SHOCK LASER EXPERIMENTS RELEVANT TO ACCRETING STREAM-DISK IMPACT IN INTERACTING BINARIES Citation Details In-Document Search Title: REVERSE RADIATIVE SHOCK LASER EXPERIMENTS RELEVANT TO ACCRETING STREAM-DISK IMPACT IN INTERACTING BINARIES We present the first results from high-energy-density laboratory astrophysics experiments that explore the hydrodynamic and radiative properties of a reverse shock relevant

  14. Giulia Galli | Center for Gas SeparationsRelevant to Clean Energy...

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

    http:angstrom.ucdavis.edu Research Interests: Quantum simulations of systems and processes relevant to condensed matter physics, physical chemistry, materials and nano- science...

  15. Cory Simon | Center for Gas SeparationsRelevant to Clean Energy...

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

    industrially relevant mixture of xenon and krypton. EFRC Publications Simon, Cory M.; Mercado, Rocio; Schnell, Sondre; Smit, Berend; and Haranczyk, Maciej. What Are the Best...

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

    SciTech Connect (OSTI)

    Bathke, Charles Gary; Wallace, Richard K; Hase, Kevin R; Sleaford, Brad W; Ebbinghaus, Bartley B; Collins, Brian W; Bradley, Keith S; Prichard, Andrew W; Smith, Brian W

    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 until 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.

  17. Manufactured solutions for the three-dimensional Euler equations with relevance to Inertial Confinement Fusion

    SciTech Connect (OSTI)

    Waltz, J.; Canfield, T.R.; Morgan, N.R.; Risinger, L.D.; Wohlbier, J.G.

    2014-06-15

    We present a set of manufactured solutions for the three-dimensional (3D) Euler equations. The purpose of these solutions is to allow for code verification against true 3D flows with physical relevance, as opposed to 3D simulations of lower-dimensional problems or manufactured solutions that lack physical relevance. Of particular interest are solutions with relevance to Inertial Confinement Fusion (ICF) capsules. While ICF capsules are designed for spherical symmetry, they are hypothesized to become highly 3D at late time due to phenomena such as Rayleigh–Taylor instability, drive asymmetry, and vortex decay. ICF capsules also involve highly nonlinear coupling between the fluid dynamics and other physics, such as radiation transport and thermonuclear fusion. The manufactured solutions we present are specifically designed to test the terms and couplings in the Euler equations that are relevant to these phenomena. Example numerical results generated with a 3D Finite Element hydrodynamics code are presented, including mesh convergence studies.

  18. Evaluation of alkali concentration in conditions relevant to oxygen/natural

    Office of Scientific and Technical Information (OSTI)

    gas glass furnaces by laser-induced breakdown spectroscopy. (Conference) | SciTech Connect Conference: Evaluation of alkali concentration in conditions relevant to oxygen/natural gas glass furnaces by laser-induced breakdown spectroscopy. Citation Details In-Document Search Title: Evaluation of alkali concentration in conditions relevant to oxygen/natural gas glass furnaces by laser-induced breakdown spectroscopy. A number of industrial combustion systems are adopting oxygen-enhanced firing

  19. Land and Resource Management Issues Relevant to Deploying In-Situ Thermal

    Office of Scientific and Technical Information (OSTI)

    Technologies (Technical Report) | SciTech Connect Land and Resource Management Issues Relevant to Deploying In-Situ Thermal Technologies Citation Details In-Document Search Title: Land and Resource Management Issues Relevant to Deploying In-Situ Thermal Technologies Utah is home to oil shale resources containing roughly 1.3 trillion barrels of oil equivalent and our nation's richest oil sands resources. If economically feasible and environmentally responsible means of tapping these resources

  20. Land and Resource Management Issues Relevant to Deploying In-Situ Thermal

    Office of Scientific and Technical Information (OSTI)

    Technologies (Technical Report) | SciTech Connect Land and Resource Management Issues Relevant to Deploying In-Situ Thermal Technologies Citation Details In-Document Search Title: Land and Resource Management Issues Relevant to Deploying In-Situ Thermal Technologies Ă— You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit OSTI to

  1. Theoretical/Computational Tools for Energy-Relevant Catalysis | The Ames

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

    Laboratory Theoretical/Computational Tools for Energy-Relevant Catalysis FWP/Project Description: Project Leader(s): James Evans, Mark Gordon Principal Investigators: James Evans, Mark Gordon This project will develop new strategies for and integrated combinations of electronic structure analysis and statistical mechanical, coarse-grained, and multi-scale modeling approaches to treat energy-relevant heterogeneous catalytic systems. Currently, there is a lack of effective molecular-level

  2. 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.

    SciTech Connect (OSTI)

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

    2010-01-01

    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 which 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 safeguards at almost all of its meeting.

  3. Preliminary Study of the Efficacy of Using Nuclear Resonance Fluorescence with Quasi-Monoenergetic Gamma-Ray Sources for Nuclear Safeguards Assay

    SciTech Connect (OSTI)

    Johnson, M S; McNabb, D P; Hall, J M; Gonzalez, J J

    2011-02-17

    We have studied the efficacy of using nuclear resonance fluorescence (NRF)-based techniques to assay spent nuclear fuel for Pu content using quasi-monoenergetic sources. We have developed two techniques to precisely determine the Pu content in a fuel rod/pin. One of our approaches is virtually free of systematic uncertainties. Using analytical models, we have determined the amount of time required to measure the Pu content in spent nuclear fuel rods and spent fuel assemblies to within 1% precision. We note that Pu content can be determined in a fuel assembly about as fast as in a single fuel pin. The performance of NRF-based assay techniques with improved photon sources, which are currently under development, will also estimated. For follow-on research we propose to: (1) Construct research prototype detection systems for both of the NRF-based assay systems proposed in this paper and measure their calibration curves; (2) Determine the systematic errors associated with both assay methods, explore ways to reduce the errors and fold the results into future performance calculations; (3) Develop an algorithm to assay a fuel assembly; (4) Perform validation measurements using a single pin and scaled assemblies; (5) Research and develop current-mode detection and/or threshold detection techniques to improve assay times; (6) Characterize the flux of newly constructed sources and fold the results into the calculations presented here to determine the feasibility of a variety of proposed sources; and (7) Collaborate with others in the safeguards community to build a prototype system and perform an NRF-based assay demonstration on spent fuel.

  4. Program of technical assistance to the Organization for the Prohibition of Chemical Weapons - lessons learned from the U.S. program of technical assistance to IAEA safeguards. Final report

    SciTech Connect (OSTI)

    1995-06-01

    The Defense Nuclear Agency is sponsoring a technical study of the requirements of a vehicle to meet the OPCW`s future needs for enhanced chemical weapons verification capabilities. This report provides information about the proven mechanisms by which the U.S. provided both short- and long-term assistance to the IAEA to enhance its verification capabilities. Much of the technical assistance has generic application to international organizations verifying compliance with disarmament treaties or conventions. In addition, some of the equipment developed by the U.S. under the existing arrangements can be applied in the verification of other disarmament treaties or conventions. U.S. technical assistance to IAEA safeguards outside of the IAEA`s regular budget proved to be necessary. The U.S. technical assistance was successful in improving the effectiveness of IAEA safeguards for its most urgent responsibilities and in providing the technical elements for increased IAEA {open_quotes}readiness{close_quotes} for the postponed responsibilities deemed important for U.S. policy objectives. Much of the technical assistance was directed to generic subjects and helped to achieve a system of international verification. It is expected that the capabilities of the Organization for the Prohibition of Chemical Weapons (OPCW) to verify a state`s compliance with the {open_quotes}Chemical Weapons Convention{close_quotes} will require improvements. This report presents 18 important lessons learned from the experience of the IAEA and the U.S. Program of Technical Assistance to IAEA Safeguards (POTAS), organized into three tiers. Each lesson is presented in the report in the context of the difficulty, need and history in which the lesson was learned. Only the most important points are recapitulated in this executive summary.

  5. Progress and goals for INMM ASC N15 consensus standard ""Administrative practices for the determination and reporting of results of non-destructive assay measurements of nuclear material in situ for safeguards nuclear criticality safety and other purposes

    SciTech Connect (OSTI)

    Bracken, David S; Lamb, Frank W

    2009-01-01

    This paper will discuss the goals and progress to date on the development of INMM Accredited Standard Committee (ASC) N15 consensus standard Administrative Practices for the Determination and Reporting of Results of Non-Destructive Assay Measurements of Nuclear Material in situ for Safeguards, Nuclear Criticality Safety, and Other Purposes. This standard will define administrative practices in the areas of data generation and reporting of NDA assay of holdup deposits with consideration of the stakeholders of the reported results. These stakeholders may include nuclear material accounting and safeguards, nuclear criticality safety, waste management, health physics, facility characterization, authorization basis, radiation safety, and site licensing authorities. Stakeholder input will be solicited from interested parties and incorporated during the development of the document. Currently only one consensus standard exists that explicitly deals with NDA holdup measurements: ASTM C1455 Standard Test Method for Nondestructive Assay of Special Nuclear Material Holdup Using Gamma-Ray Spectroscopic Methods. The ASTM International standard emphasizes the activities involved in actually making measurements, and was developed by safeguards and NDA experts. This new INMM ASC N15 standard will complement the existing ASTM international standard. One of the largest driving factors for writing this new standard was the recent emphasis on in situ NDA measurements by the safeguards community due to the Defense Nuclear Facility Safety Board (DNFSB) recommendation 2007-1 on in situ NDA measurements. Specifically, DNFSB recommendation 2007-1 referenced the lack of programmatic requirements for accurate in situ measurements and the use of measurement results for compliance with safety based requirements. That being the case, this paper will also discuss the progress made on the Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2007-1 Safety-Related In Situ Nondestructive Assay of Radioactive Materials. Some of the information that will be presented includes observations made during site visits, how information useful to all facilities using nondestructive assay to determine holdup material quantities will be disseminated, and preliminary results of a gap analysis performed on current in situ nondestructive assay holdup measurements.

  6. Subsurface Behavior of Plutonium and Americium at Non-Hanford Sites and Relevance to Hanford

    SciTech Connect (OSTI)

    Cantrell, Kirk J.; Riley, Robert G.

    2008-02-01

    Seven sites where Pu release to the environment has raised significant environmental concerns have been reviewed. A summary of the most significant hydrologic and geochemical features, contaminant release events and transport processes relevant to Pu migration at the seven sites is presented.

  7. Nuclear structure relevant to neutrinoless double beta decay candidate {sup 130}Te and other recent results

    SciTech Connect (OSTI)

    Kay, B. P. [Physics Division, Argonne National Laboratory, Illinois 60439 (United States)

    2013-12-30

    We have undertaken a series of single-nucleon and pair transfer reaction measurements to help constrain calculations of the nuclear matrix elements for neutrinoless double beta decay. In this talk, a short overview of measurements relevant to the {sup 130}Te?{sup 130}Xe system is given. Brief mention is made of other recent and forthcoming results.

  8. Complete Genome Sequences for 35 Biothreat Assay-Relevant Bacillus Species

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

    Johnson, Shannon L.; Daligault, Hajnalka E.; Davenport, Karen W.; Jaissle, James; Frey, Kenneth G.; Ladner, Jason T.; Broomall, Stacey M.; Bishop-Lilly, Kimberly A.; Bruce, David C.; Gibbons, Henry S.; et al

    2015-04-30

    In 2011, the Association of Analytical Communities (AOAC) International released a list of Bacillus strains relevant to biothreat molecular detection assays. Presented in this document are the complete and annotated genome assemblies for the 15 strains listed on the inclusivity panel, as well as the 20 strains listed on the exclusivity panel.

  9. Systematic Assessment of Neutron and Gamma Backgrounds Relevant to Operational Modeling and Detection Technology Implementation

    SciTech Connect (OSTI)

    Archer, Daniel E.; Hornback, Donald Eric; Johnson, Jeffrey O.; Nicholson, Andrew D.; Patton, Bruce W.; Peplow, Douglas E.; Miller, Thomas Martin; Ayaz-Maierhafer, Birsen

    2015-01-01

    This report summarizes the findings of a two year effort to systematically assess neutron and gamma backgrounds relevant to operational modeling and detection technology implementation. The first year effort focused on reviewing the origins of background sources and their impact on measured rates in operational scenarios of interest. The second year has focused on the assessment of detector and algorithm performance as they pertain to operational requirements against the various background sources and background levels.

  10. Hong-Cai (Joe) Zhou | Center for Gas SeparationsRelevant to Clean Energy

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

    ScienceCinema Database Searchable Videos Showcasing DOE Research Search DOE ScienceCinema for Multimedia Find + Fielded Search Audio Search Ă— Fielded Search Title: Description/Abstract: Bibliographic Data: Author/Speaker: Name Name ORCID Media Type: All Audio Video Subject: Identifier Numbers: Media Source: All DOE CERN Research Org.: Sponsoring Org.: Publication Date: Publication Date Until to System Entry Date: Publication Date Until to Sort: Relevance Publication Date (Newest to Oldest)

  11. Jeffrey Neaton | Center for Gas SeparationsRelevant to Clean Energy

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

    Technologies | Blandine Jerome Jeffrey Neaton Previous Next List AMS 0246 Jeff Neaton Director, Molecular Foundry & Senior Faculty Scientist, Materials Sciences Division, Lawrence Berkeley National Laboratory Email: jbneaton [at] lbl.gov Phone: 510-486-4527 EFRC research: Within the CGS, the Neaton group is developing novel electronic structure methods relevant to the study of MOFs and their interaction with gas molecules. EFRC publications: Lee, Jason S.; Vlaisavljevich, Bess; Britt,

  12. Jeffrey Reimer | Center for Gas SeparationsRelevant to Clean Energy

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

    Technologies | Blandine Jerome Reimer Previous Next List HewlittAugust2013 Jeffrey Reimer Department Chair, Department of Chemical & Biomolecular Engineering, University of California, Berkeley Email: reimer [at] berkeley.edu Phone: 510-642-8011 EFRC research: Within the CGS, the Reimer group is developing novel NMR techniques relevant to the study of solid sorbents and the behavior of gas molecules inside them. EFRC publications: Braun, Efrem; Chen, Joseph J.; Schnell, Sondre K.; Lin,

  13. Perspectives on Changing Safeguards Culture

    SciTech Connect (OSTI)

    Mladineo, Stephen V.; Durbin, Karyn R.; Van Duzer, Andrew

    2005-12-01

    The importance of culture in the nuclear field has become widely recognized. In the wake of the 9-11 attacks in the United States, and terrorist attacks worldwide, the international community has become interested in strengthening nuclear security culture for much of the same reasons that it became interested in strengthening the nuclear safety culture in the 1980’s. The accidents that occurred at Three Mile Island and Chernobyl led to a realization that nuclear operations in one country can directly affect other countries. The accidents also led to the realization that technology alone cannot guarantee safety and that the human element has a key role to play in the safety operation of nuclear power plans.

  14. safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Nonproliferation and Arms Control The mission of the Office of Nonproliferation and Arms Control (NPAC) is to prevent proliferation, ensure peaceful nuclear uses, and enable ...

  15. Biologically Relevant Mechanism For Catalytic Removal of Superoxide by Simple Manganese Compounds

    SciTech Connect (OSTI)

    Barnese K.; Cabelli D.; Gralla, E.B.; Valentine, J.S.

    2012-05-01

    Nonenzymatic manganese was first shown to provide protection against superoxide toxicity in vivo in 1981, but the chemical mechanism responsible for this protection subsequently became controversial due to conflicting reports concerning the ability of Mn to catalyze superoxide disproportionation in vitro. In a recent communication, we reported that low concentrations of a simple Mn phosphate salt under physiologically relevant conditions will indeed catalyze superoxide disproportionation in vitro. We report now that two of the four Mn complexes that are expected to be most abundant in vivo, Mn phosphate and Mn carbonate, can catalyze superoxide disproportionation at physiologically relevant concentrations and pH, whereas Mn pyrophosphate and citrate complexes cannot. Additionally, the chemical mechanisms of these reactions have been studied in detail, and the rates of reactions of the catalytic removal of superoxide by Mn phosphate and carbonate have been modeled. Physiologically relevant concentrations of these compounds were found to be sufficient to mimic an effective concentration of enzymatic superoxide dismutase found in vivo. This mechanism provides a likely explanation as to how Mn combats superoxide stress in cellular systems.

  16. 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 II/III IAEA COMMITTEE 24, Major Issues Underlying the Model Additional Protocol (1996-1997).

    SciTech Connect (OSTI)

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

    2010-01-01

    Volume I of this Review traces the origins of the Model Additional Protocol. It covers the period from 1991, when events in Iraq triggered an intensive review of the safeguards system, until 1996, when the IAEA Board of Governors established Committee 24 to negotiate a new protocol to safeguards agreement. The period from 1991-1996 set the stage for this negotiation and shaped its outcome in important ways. During this 5-year period, many proposals for strengthening safeguards were suggested and reviewed. Some proposals were dropped, for example, the suggestion by the IAEA Secretariat to verify certain imports, and others were refined. A rough consensus was established about the directions in which the international community wanted to go, and this was reflected in the draft of an additional protocol that was submitted to the IAEA Board of Governors on May 6, 1996 in document GOV/2863, Strengthening the Effectiveness and Improving the Efficiency of the Safeguards System - Proposals For Implementation Under Complementary Legal Authority, A Report by the Director General. This document ended with a recommendation that, 'the Board, through an appropriate mechanism, finalize the required legal instrument taking as a basis the draft protocol proposed by the Secretariat and the explanation of the measures contained in this document.'

  17. Culturally relevant science: An approach to math science education for Hispanics

    SciTech Connect (OSTI)

    Montellano, B.O. de

    1996-11-14

    This report describes later stages of a program to develop culturally relevant science and math programs for Hispanic students. Part of this effort was follow-up with 17 teachers who participated in early stages of the program. Response was not very good. Included with the report is a first draft effort for curriculum materials which could be used as is in such a teaching effort. Several of the participating teachers were invited to a writing workshop, where lesson plans were drafted, and critiqued and following rework are listed in this publication. Further work needs to be completed and is ongoing.

  18. Final Report: Laser-Material Interactions Relevant to Analytic Spectroscopy of Wide Band Gap Materials

    SciTech Connect (OSTI)

    Dickinson, J. T.

    2014-04-05

    We summarize our studies aimed at developing an understanding of the underlying physics and chemistry in terms of laser materials interactions relevant to laser-based sampling and chemical analysis of wide bandgap materials. This work focused on the determination of mechanisms for the emission of electrons, ions, atoms, and molecules from laser irradiation of surfaces. We determined the important role of defects on these emissions, the thermal, chemical, and physical interactions responsible for matrix effects and mass-dependent transport/detection. This work supported development of new techniques and technology for the determination of trace elements contained such as nuclear waste materials.

  19. Conceptual Framework to Enable Early Warning of Relevant Phenomena (Emerging Phenomena and Big Data)

    SciTech Connect (OSTI)

    Schlicher, Bob G; Abercrombie, Robert K; Hively, Lee M

    2013-01-01

    Graphs are commonly used to represent natural and man-made dynamic systems such as food webs, economic and social networks, gene regulation, and the internet. We describe a conceptual framework to enable early warning of relevant phenomena that is based on an artificial time-based, evolving network graph that can give rise to one or more recognizable structures. We propose to quantify the dynamics using the method of delays through Takens Theorem to produce another graph we call the Phase Graph. The Phase Graph enables us to quantify changes of the system that form a topology in phase space. Our proposed method is unique because it is based on dynamic system analysis that incorporates Takens Theorem, Graph Theory, and Franzosi-Pettini (F-P) theorem about topology and phase transitions. The F-P Theorem states that the necessary condition for phase transition is a change in the topology. By detecting a change in the topology that we represent as a set of M-order Phase Graphs, we conclude a corresponding change in the phase of the system. The onset of this phase change enables early warning of emerging relevant phenomena.

  20. Catalog of CERCLA applicable or relevant and appropriate requirements (ARARs) - fact sheets

    SciTech Connect (OSTI)

    Not Available

    1990-07-01

    Section 121(d) of the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), requires attainment of federal and state applicable or relevant and appropriate requirements (ARARs). Subpart E, Section 300.400(g) {open_quotes}Identification of applicable or relevant and appropriate requirements{close_quotes} of the National Oil and Hazardous Substances Pollution Contingency Plan (NCP)(55 FR 8666, March 8, 1990) describes the process for attaining ARARs. The purpose of this catalog is to provide DOE Program Offices and Field Organizations with all of the {open_quotes}Quick Reference Fact Sheets{close_quotes} on attaining ARARS. These fact sheets provide overviews of ARARs for CERCLA cleanup actions pertinent to DOE environmental restoration activities. All of the fact sheets in this catalog were prepared by the Environmental Protection Agency`s Office of Solid Waste and Emergency Response. Fact sheets 1-7 discuss land disposal restrictions (LDRs) and their applicability. LDRs may pertain to a number of CERCLA response actions at DOE facilities. Fact Sheets 8-13 are based on the CERCLA Compliance with Other Laws Manual: Parts I and II and provide an overview of many other CERCLA ARARs. Overview of ARARs-Focus on ARAR Waivers (fact sheet 11), provides a good introduction to ARARS. The last two fact sheets, 14 and 15, are periodic reports that describe additional fact sheets and clarify issues.

  1. Method for extracting relevant electrical parameters from graphene field-effect transistors using a physical model

    SciTech Connect (OSTI)

    Boscá, A.; Pedrós, J.; Martínez, J.; Calle, F.

    2015-01-28

    Due to its intrinsic high mobility, graphene has proved to be a suitable material for high-speed electronics, where graphene field-effect transistor (GFET) has shown excellent properties. In this work, we present a method for extracting relevant electrical parameters from GFET devices using a simple electrical characterization and a model fitting. With experimental data from the device output characteristics, the method allows to calculate parameters such as the mobility, the contact resistance, and the fixed charge. Differentiated electron and hole mobilities and direct connection with intrinsic material properties are some of the key aspects of this method. Moreover, the method output values can be correlated with several issues during key fabrication steps such as the graphene growth and transfer, the lithographic steps, or the metalization processes, providing a flexible tool for quality control in GFET fabrication, as well as a valuable feedback for improving the material-growth process.

  2. REVERSE RADIATIVE SHOCK LASER EXPERIMENTS RELEVANT TO ACCRETING STREAM-DISK IMPACT IN INTERACTING BINARIES

    SciTech Connect (OSTI)

    Krauland, C. M.; Drake, R. P.; Kuranz, C. C.; Huntington, C. M.; Kaczala, D. N.; Klein, S.; Sweeney, R.; Young, R. P.; Keiter, P. A.; Loupias, B.; Falize, E.; Villette, B.; Plewa, T. E-mail: rpdrake@umich.edu

    2013-01-01

    We present the first results from high-energy-density laboratory astrophysics experiments that explore the hydrodynamic and radiative properties of a reverse shock relevant to a cataclysmic variable system. A reverse shock is a shock wave that develops when a freely flowing, supersonic plasma is impeded. In our experiments, performed on the Omega Laser Facility, a laser pulse is used to accelerate plasma ejecta into a vacuum. This flow is directed into an Al plate in front of which a shock forms in the rebounding plasma. The plasma flow is moving fast enough that it is shocked to high enough temperatures that radiative cooling affects the shock structure. These are the first experiments to produce a radiative reverse shock wave.

  3. Diagnosing laser-preheated magnetized plasmas relevant to magnetized liner inertial fusion

    SciTech Connect (OSTI)

    Harvey-Thompson, Adam James; Sefkow, Adam B.; Nagayama, Taisuke N.; Wei, Mingsheng; Campbell, Edward Michael; Fiksel, Gennady; Chang, Po -Yu; Davies, Jonathan R.; Barnak, Daniel H.; Glebov, Vladimir Y.; Fitzsimmons, Paul; Fooks, Julie; Blue, Brent E.

    2015-12-22

    In this paper, we present a platform on the OMEGA EP Laser Facility that creates and diagnoses the conditions present during the preheat stage of the MAGnetized Liner Inertial Fusion (MagLIF) concept. Experiments were conducted using 9 kJ of 3ω (355 nm) light to heat an underdense deuterium gas (electron density: 2.5 × 1020 cm-3 = 0.025 of critical density) magnetized with a 10 T axial field. Results show that the deuterium plasma reached a peak electron temperature of 670 ± 140 eV, diagnosed using streaked spectroscopy of an argon dopant. The results demonstrate that plasmas relevant to the preheat stage of MagLIF can be produced at multiple laser facilities, thereby enabling more rapid progress in understanding magnetized preheat. Results are compared with magneto-radiation-hydrodynamics simulations, and plans for future experiments are described.

  4. Beta-decay spectroscopy relevant to the r-process nucleosynthesis

    SciTech Connect (OSTI)

    Nishimura, Shunji; Collaboration: RIBF Decay Collaboration

    2012-11-12

    A scientific program of beta-decay spectroscopy relevant to r-process nucleosynthesis has been started using high intensity U-beam at the RIBF. The first results of {beta}-decay half-lives of very neutron-rich Kr to Tc nuclides, all of which lie close to the r-process path, suggest a systematic enhancement of the the {beta}-decay rates of the Zr and Nb isotopes around A110 with respect to the predictions of the deformed quasiparticle-random-phase-approximation model (FRDM + QRPA). An impact of the results on the astrophysical r-process is discussed together with the future perspective of the {beta}-decay spectroscopy with the EURICA.

  5. Diagnosing laser-preheated magnetized plasmas relevant to magnetized liner inertial fusion

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

    Harvey-Thompson, Adam James; Sefkow, Adam B.; Nagayama, Taisuke N.; Wei, Mingsheng; Campbell, Edward Michael; Fiksel, Gennady; Chang, Po -Yu; Davies, Jonathan R.; Barnak, Daniel H.; Glebov, Vladimir Y.; et al

    2015-12-22

    In this paper, we present a platform on the OMEGA EP Laser Facility that creates and diagnoses the conditions present during the preheat stage of the MAGnetized Liner Inertial Fusion (MagLIF) concept. Experiments were conducted using 9 kJ of 3ω (355 nm) light to heat an underdense deuterium gas (electron density: 2.5 × 1020 cm-3 = 0.025 of critical density) magnetized with a 10 T axial field. Results show that the deuterium plasma reached a peak electron temperature of 670 ± 140 eV, diagnosed using streaked spectroscopy of an argon dopant. The results demonstrate that plasmas relevant to the preheatmore » stage of MagLIF can be produced at multiple laser facilities, thereby enabling more rapid progress in understanding magnetized preheat. Results are compared with magneto-radiation-hydrodynamics simulations, and plans for future experiments are described.« less

  6. Elastic Cross Sections for Electron Collisions with Molecules Relevant to Plasma Processing

    SciTech Connect (OSTI)

    Yoon, J.-S.; Song, M.-Y.; Kato, H.; Hoshino, M.; Tanaka, H.; Brunger, M. J.; Buckman, S. J.; Cho, H.

    2010-09-15

    Absolute electron-impact cross sections for molecular targets, including their radicals, are important in developing plasma reactors and testing various plasma processing gases. Low-energy electron collision data for these gases are sparse and only the limited cross section data are available. In this report, elastic cross sections for electron-polyatomic molecule collisions are compiled and reviewed for 17 molecules relevant to plasma processing. Elastic cross sections are essential for the absolute scale conversion of inelastic cross sections, as well as for testing computational methods. Data are collected and reviewed for elastic differential, integral, and momentum transfer cross sections and, for each molecule, the recommended values of the cross section are presented. The literature has been surveyed through early 2010.

  7. Culturally relevant science: An approach to math science education for hispanics. Final technical report

    SciTech Connect (OSTI)

    Montellano, B.O. de

    1996-11-14

    This progress report summarizes results of a teacher workshop. A letter sent to 17 teachers who had participated in the workshop requested a report of any activities undertaken and copies of lesson plans and materials developed. Only nine responses were received, and not all of them demonstrated a satisfactory level of activity. Teachers who submitted materials showing the most promise were invited to participate in the Summer Writing Workshop. A partial first draft of a companion volume for the teacher`s manual was written which provides a rationale for culturally relevant science and presents the cultural and scientific background needed. The outline of the book is presented in Appendix 1. Appendix 2 is a sample chapter from the book.

  8. Connecting Organic Aerosol Climate-Relevant Properties to Chemical Mechanisms of Sources and Processing

    SciTech Connect (OSTI)

    Thornton, Joel

    2015-01-26

    The research conducted on this project aimed to improve our understanding of secondary organic aerosol (SOA) formation in the atmosphere, and how the properties of the SOA impact climate through its size, phase state, and optical properties. The goal of this project was to demonstrate that the use of molecular composition information to mechanistically connect source apportionment and climate properties can improve the physical basis for simulation of SOA formation and properties in climate models. The research involved developing and improving methods to provide online measurements of the molecular composition of SOA under atmospherically relevant conditions and to apply this technology to controlled simulation chamber experiments and field measurements. The science we have completed with the methodology will impact the simulation of aerosol particles in climate models.

  9. Kinetics of elementary processes relevant to incipient soot formation. Final technical report

    SciTech Connect (OSTI)

    Lin, M.C.

    1998-03-09

    In order to better understand the mechanism of soot formation (one of the most challenging problems in the study of hydrocarbon combustion chemistry), reliable rate constants for the key reaction steps involved in the formation and polymerization of aromatic hydrocarbons in the inception stage are required for kinetic modeling. In this DOE sponsored work, the authors have developed three new experimental methods: cavity ring-down (CRD) spectrometry, pyrolysis/Fourier transform infrared spectrometry (p/FTIRS) and pulsed laser photolysis/mass spectrometry (PLP/MS) for kinetic measurements of C{sub 6}H{sub 5} reactions pivotal to incipient soot formation chemistry. In addition, the authors have also carried out ab initio molecular orbital (MO) calculations for several key elementary combustion reactions relevant to soot formation. The results are briefly summarized in the report using selected examples for more detailed discussion. 84 refs.

  10. Culturally relevant science: An approach to math science education for Hispanics. Final technical report

    SciTech Connect (OSTI)

    Ortiz de Montellano, B.

    1996-11-14

    As planned a letter was sent out to 17 teachers who had participated in a Summer 1994 workshop on ``Culturally Relevant Science for Hispanics`` at Michigan State. These teachers were supposed to have spent the intervening time developing lesson plans and curricula. The letter requested a report of any activities undertaken and copies of lesson plans and materials developed by February 1996 with a stipend of $400 for satisfactory reports. It was a disappointment to only get 9 responses and not all of them demonstrating a satisfactory level of activity. Diana Marinez, Dean of Science at Texas A and M University, Corpus Christi, who is the other developer of this curriculum and the author reviewed the submitted materials and chose those showing the most promise to be invited to participate in the Summer Writing Workshop. Spring of 1996 and particularly in May--June, the author wrote a partial first draft of a companion volume for the teacher`s manual which would provide a rationale for doing culturally relevant science, present the cultural and the scientific background that teachers would need in order to be able to teach. One of the goals of this curriculum is that it should be off-the-shelf ready to teach and that teachers would not have to do extra research to encourage its adoption. The outline of the book is appendix 1. The Writing Workshop was held at Texas A and M University, Corpus Christi from July 14 to July 27, 1996. Participating teachers chose topics that they were interested in developing and wrote first drafts. These were distributed to all participants and critiqued by the workshop directors before being rewritten. Some teachers were more productive than others depending on their science background. In total an impressive number of lesson plans were written. These lesson plans are listed in Appendix 3. Appendix 4 is a sample lesson. Work still needs to be done on both the source book and the teachers` manual.

  11. Coupling of Nuclear Waste Form Corrosion and Radionuclide Transports in Presence of Relevant Repository Sediments

    SciTech Connect (OSTI)

    Wall, Nathalie A.; Neeway, James J.; Qafoku, Nikolla P.; Ryan, Joseph V.

    2015-09-30

    Assessments of waste form and disposal options start with the degradation of the waste forms and consequent mobilization of radionuclides. Long-term static tests, single-pass flow-through tests, and the pressurized unsaturated flow test are often employed to study the durability of potential waste forms and to help create models that predict their durability throughout the lifespan of the disposal site. These tests involve the corrosion of the material in the presence of various leachants, with different experimental designs yielding desired information about the behavior of the material. Though these tests have proved instrumental in elucidating various mechanisms responsible for material corrosion, the chemical environment to which the material is subject is often not representative of a potential radioactive waste repository where factors such as pH and leachant composition will be controlled by the near-field environment. Near-field materials include, but are not limited to, the original engineered barriers, their resulting corrosion products, backfill materials, and the natural host rock. For an accurate performance assessment of a nuclear waste repository, realistic waste corrosion experimental data ought to be modeled to allow for a better understanding of waste form corrosion mechanisms and the effect of immediate geochemical environment on these mechanisms. Additionally, the migration of radionuclides in the resulting chemical environment during and after waste form corrosion must be quantified and mechanisms responsible for migrations understood. The goal of this research was to understand the mechanisms responsible for waste form corrosion in the presence of relevant repository sediments to allow for accurate radionuclide migration quantifications. The rationale for this work is that a better understanding of waste form corrosion in relevant systems will enable increased reliance on waste form performance in repository environments and potentially decrease the need for expensive engineered barriers.Our current work aims are 1) quantifying and understanding the processes associated with glass alteration in contact with Fe-bearing materials; 2) quantifying and understanding the processes associated with glass alteration in presence of MgO (example of engineered barrier used in WIPP); 3) identifying glass alteration suppressants and the processes involved to reach glass alteration suppression; 4) quantifying and understanding the processes associated with Saltstone and Cast Stone (SRS and Hanford cementitious waste forms) in various representative groundwaters; 5) investigating positron annihilation as a new tool for the study of glass alteration; and 6) quantifying and understanding the processes associated with glass alteration under gamma irradiation.

  12. DOE SBIR Phase II Final Report: Distributed Relevance Ranking in Heterogeneous Document Collections

    SciTech Connect (OSTI)

    Abe Lederman

    2007-01-08

    This report contains the comprehensive summary of the work performed on the SBIR Phase II project (“Distributed Relevance Ranking in Heterogeneous Document Collections”) at Deep Web Technologies (http://www.deepwebtech.com). We have successfully completed all of the tasks defined in our SBIR Proposal work plan (See Table 1 - Phase II Tasks Status). The project was completed on schedule and we have successfully deployed an initial production release of the software architecture at DOE-OSTI for the Science.gov Alliance's search portal (http://www.science.gov). We have implemented a set of grid services that supports the extraction, filtering, aggregation, and presentation of search results from numerous heterogeneous document collections. Illustration 3 depicts the services required to perform QuickRank™ filtering of content as defined in our architecture documentation. Functionality that has been implemented is indicated by the services highlighted in green. We have successfully tested our implementation in a multi-node grid deployment both within the Deep Web Technologies offices, and in a heterogeneous geographically distributed grid environment. We have performed a series of load tests in which we successfully simulated 100 concurrent users submitting search requests to the system. This testing was performed on deployments of one, two, and three node grids with services distributed in a number of different configurations. The preliminary results from these tests indicate that our architecture will scale well across multi-node grid deployments, but more work will be needed, beyond the scope of this project, to perform testing and experimentation to determine scalability and resiliency requirements. We are pleased to report that a production quality version (1.4) of the science.gov Alliance's search portal based on our grid architecture was released in June of 2006. This demonstration portal is currently available at http://science.gov/search30 . The portal allows the user to select from a number of collections grouped by category and enter a query expression (See Illustration 1 - Science.gov 3.0 Search Page). After the user clicks “search” a results page is displayed that provides a list of results from the selected collections ordered by relevance based on the query expression the user provided. Our grid based solution to deep web search and document ranking has already gained attention within DOE, other Government Agencies and a fortune 50 company. We are committed to the continued development of grid based solutions to large scale data access, filtering, and presentation problems within the domain of Information Retrieval and the more general categories of content management, data mining and data analysis.

  13. Advancing sustainable bioenergy: Evolving stakeholder interests and the relevance of research

    SciTech Connect (OSTI)

    Johnson, Timothy L [U.S. Environmental Protection Agency, Raleigh, North Carolina; Bielicki, Dr Jeffrey M [University of Minnesota; Dodder, Rebecca [U.S. Environmental Protection Agency; Hilliard, Michael R [ORNL; Kaplan, Ozge [U.S. Environmental Protection Agency; Miller, C. Andy [U.S. Environmental Protection Agency

    2013-01-01

    The sustainability of future bioenergy production rests on more than continual improvements in its environmental, economic, and social impacts. The emergence of new biomass feedstocks, an expanding array of conversion pathways, and expected increases in overall bioenergy production are connecting diverse technical, social, and policy communities. These stakeholder groups have different and potentially conflicting values and cultures, and therefore different goals and decision making processes. Our aim is to discuss the implications of this diversity for bioenergy researchers. The paper begins with a discussion of bioenergy stakeholder groups and their varied interests, and illustrates how this diversity complicates efforts to define and promote sustainable bioenergy production. We then discuss what this diversity means for research practice. Researchers, we note, should be aware of stakeholder values, information needs, and the factors affecting stakeholder decision making if the knowledge they generate is to reach its widest potential use. We point out how stakeholder participation in research can increase the relevance of its products, and argue that stakeholder values should inform research questions and the choice of analytical assumptions. Finally, we make the case that additional natural science and technical research alone will not advance sustainable bioenergy production, and that important research gaps relate to understanding stakeholder decision making and the need, from a broader social science perspective, to develop processes to identify and accommodate different value systems. While sustainability requires more than improved scientific and technical understanding, the need to understand stakeholder values and manage diversity presents important research opportunities.

  14. Selected, annotated bibliography of studies relevant to the isolation of nuclear wastes. [705 references

    SciTech Connect (OSTI)

    Hyder, L.K.; Fore, C.S.; Vaughan, N.D.; Faust, R.A.

    1980-09-01

    This annotated bibliography of 705 references represents the first in a series to be published by the Ecological Sciences Information Center containing scientific, technical, economic, and regulatory information relevant to nuclear waste isolation. Most references discuss deep geologic disposal, with fewer studies of deep seabed disposal; space disposal is also included. The publication covers both domestic and foreign literature for the period 1954 to 1980. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Envirnmental Transport; General Studies and Reviews; Geology, Hydrology and Site Resources; Regulatory and Economic Aspects; Repository Design and Engineering; Transportation Technology; Waste Production; and Waste Treatment. Specialized data fields have been incorporated to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the Measured Radionuclides field, and specific parameters which affect the migration of these radionuclides are presented in the Measured Parameters field. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for author(s), keywords, subject category, title, geographic location, measured parameters, measured radionuclides, and publication description.

  15. Survey of Field Programmable Gate Array Design Guides and Experience Relevant to Nuclear Power Plant Applications

    SciTech Connect (OSTI)

    Bobrek, Miljko; Bouldin, Don; Holcomb, David Eugene; Killough, Stephen M; Smith, Stephen Fulton; Ward, Christina D

    2007-09-01

    From a safety perspective, it is difficult to assess the correctness of FPGA devices without extensive documentation, tools, and review procedures. NUREG/CR-6463, "Review Guidelines on Software Languages for Use in Nuclear Power Plant Safety Systems," provides guidance to the Nuclear Regulatory Commission (NRC) on auditing of programs for safety systems written in ten high-level languages. A uniform framework for the formulation and discussion of language-specific programming guidelines was employed. Comparable guidelines based on a similar framework are needed for FPGA-based systems. The first task involves evaluation of regulatory experience gained by other countries and other agencies, and those captured in existing standards, to identify regulatory approaches that can be adopted by NRC. If existing regulations do not provide a sufficient regulatory basis for adopting relevant regulatory approaches that are uncovered, ORNL will identify the gaps. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

  16. Transport of fluorescently labeled hydroxyapatite nanoparticles in saturated granular media at environmentally relevant concentrations of surfactants

    SciTech Connect (OSTI)

    Wang, Dengjun; Su, Chuming; Liu, Chongxuan; Zhou, Dongmei

    2014-05-01

    Hydroxyapatite nanoparticle (nHAP) is being used to remediate soils and aquifers contaminated with metals and radionuclides; however, the mobility of nHAP is still poorly understood in subsurface granular environments. In this study, transport and retention kinetics of alizarin red S (ARS)-labeled nHAP were investigated in water-saturated quartz sand at low concentrations of surfactants: sodium dodecyl benzene sulfonate (SDBS, an anionic surfactant, 0–50 mg L–1) and cetyltrimethylammonium bromide (CTAB, a cationic surfactant, 0–5 mg L–1). Both surfactants were found to have a marked effect on the electrokinetic properties of ARS-nHAP and, consequently, on their transport and retention behaviors. Transport of nanoparticles (NPs) increased significantly with increasing SDBS concentration, largely because of enhanced colloidal stability and reduced aggregate size arising from enhanced electrostatic, osmotic, and elastic-steric repulsions between ARS-nHAP and sand grains. Conversely, transport decreased significantly in the presence of increasing CTAB concentrations due to reduced surface charge and consequential enhanced aggregation of the NPs. Osmotic and elastic-steric repulsions played only a minor role in enhancing the colloidal stability of ARS-nHAP in the presence of CTAB. Retention profiles of ARS-nHAP exhibited hyperexponential-shapes (decreasing rates of retention with increasing distance) for all conditions tested, and became more pronounced as CTAB concentration increased. The phenomenon was attributed to the aggregation and ripening of ARS-nHAP in the presence of surfactants, particularly CTAB. Overall, the present study suggests that surfactants at environmentally relevant concentrations may be an important consideration in employing nHAP for engineered in-situ remediation of certain metals and radionuclides in contaminated soils and aquifers.

  17. Stability of SiC-Matrix Microencapsulated Fuel Constituents at Relevant LWR Conditions

    SciTech Connect (OSTI)

    Terrani, Kurt A; Katoh, Yutai; Leonard, Keith J; Perez-Bergquist, Alex G; Silva, Chinthaka M; Snead, Lance Lewis

    2014-01-01

    This paper addresses certain key feasibility issues facing the application of SiC-matrix microencapsulated fuels for light water reactor application. Issues addressed are the irradiation stability of the SiC-based nano-powder ceramic matrix under LWR-relevant irradiation conditions, the presence or extent of reaction of the SiC matrix with zirconium-based cladding, the stability of the inner and outer pyrolytic graphite layers of the microencapsulated (TRISO) particle at this uncharacteristically low irradiation temperature, and the state of the particle-matrix interface following irradiation which could possibly effect thermal transport. In the process of determining these feasibility issues microstructural evolution and change in dimension and thermal conductivity was studied. As a general finding the SiC matrix was found to be quite stable with behavior similar to that of CVD SiC. In magnitude the irradiation-induced swelling of the matrix material was slightly higher and irradiation-degraded thermal conductivity was slightly lower as compared to CVD SiC. No significant reaction of this SiC-based nano-powder ceramic matrix material with Zircaloy was observed. Irradiation of the TRISO in the 320-360 C range to a maximum dose of 7.7 1025 n/m2 (E > 0.1 MeV) did not have significant negative impact on the constituent layers of the TRISO fuel. At the highest dose studied layer structure and interface integrity remained essentially unchanged with good apparent thermal transport through the microsphere to the surrounding matrix.

  18. Gamma-ray spectrometric determination of UF/sub 6/ assay with 1 percent precision for international safeguards. Part 1: product and feed in 1S and 2S sample cylinders

    SciTech Connect (OSTI)

    Ricci, E.

    1981-06-15

    The method is based on counting the 186-keV gamma rays emitted by /sup 235/U using a Pb-collimated Ge(Li) detector. Measurements of fifty UF/sub 6/ product and feed cylinders reveal the following precisions and counting times: Product - 2S, 0.98% (600 s); Feed - 2S, 0.48% (2500 s); Product - 1S, 0.62% (1000 s); Feed - 1S, 0.73% (3000 s). A 1% precision is desired for variables - attributes verification measurements of /sup 235/U assay in UF/sub 6/ sample cylinders for safeguards inspections by the International Atomic Energy Agency (IAEA). Statistically, these measurements stand between fine, high-precision (or variables) measurements and gross, low-precision (or attributes) ones. Because of their intermediate precisions, the variables-attributes measurements may not require analysis of all samples, and this could result in significant savings of IAEA inspector time. Although the precision of the above results is satisfactory, the average relative differences between gamma-ray and mass-spectrometric determinations for the last two sets of measurements (1S cylinders) have positive biases.

  19. Sandia National Laboratories Releases Literature Survey of Crude Oil Properties Relevant to Handling and Fire Safety in Transport

    Broader source: Energy.gov [DOE]

    The Department of Energy is helping to develop an understanding of scientific questions associated with the production, treatment, and transportation of crude oils, including Bakken crude oil. To support this effort, the Department’s Sandia National Laboratory recently completed a report in cooperation with the Department of Transportation -- Literature Survey of Crude Oil Properties Relevant to Handling and Fire Safety in Transport.

  20. Investigation of Pressurized Entrained-Flow Kraft Black Liquor Gasification in an Industrially Relevant Environment

    SciTech Connect (OSTI)

    Kevin Whitty

    2008-06-30

    The University of Utah's project 'Investigation of Pressurized Entrained-Flow Kraft Black Liquor Gasification in an Industrially Relevant Environment' (U.S. DOE Cooperative Agreement DE-FC26-04NT42261) was a response to U.S. DOE/NETL solicitation DE-PS36-04GO94002, 'Biomass Research and Development Initiative' Topical Area 4-Kraft Black Liquor Gasification. The project began September 30, 2004. The objective of the project was to improve the understanding of black liquor conversion in high pressure, high temperature reactors that gasify liquor through partial oxidation with either air or oxygen. The physical and chemical characteristics of both the gas and condensed phase were to be studied over the entire range of liquor conversion, and the rates and mechanisms of processes responsible for converting the liquor to its final smelt and syngas products were to be investigated. This would be accomplished by combining fundamental, lab-scale experiments with measurements taken using a new semi-pilot scale pressurized entrained-flow gasifier. As a result of insufficient availability of funds and changes in priority within the Office of Biomass Programs of the U.S. Department of Energy, the research program was terminated in its second year. In total, only half of the budgeted funding was made available for the program, and most of this was used during the first year for construction of the experimental systems to be used in the program. This had a severe impact on the program. As a consequence, most of the planned research was unable to be performed. Only studies that relied on computational modeling or existing experimental facilities started early enough to deliver useful results by the time to program was terminated Over the course of the program, small scale (approx. 1 ton/day) entrained-flow gasifier was designed and installed at the University of Utah's off-campus Industrial Combustion and Gasification Research Facility. The system is designed to operate at pressures as high as 32 atmospheres, and at temperatures as high as 1500 C (2730 F). Total black liquor processing capacity under pressurized, oxygen-blown conditions should be in excess of 1 ton black liquor solids per day. Many sampling ports along the conversion section of the system will allow detailed analysis of the environment in the gasifier under industrially representative conditions. Construction was mostly completed before the program was terminated, but resources were insufficient to operate the system. A system for characterizing black liquor sprays in hot environments was designed and constructed. Silhouettes of black liquor sprays formed by injection of black liquor through a twin fluid (liquor and atomizing air) nozzle were videoed with a high-speed camera, and the resulting images were analyzed to identify overall characteristics of the spray and droplet formation mechanisms. The efficiency of liquor atomization was better when the liquor was injected through the center channel of the nozzle, with atomizing air being introduced in the annulus around the center channel, than when the liquor and air feed channels were reversed. Atomizing efficiency and spray angle increased with atomizing air pressure up to a point, beyond which additional atomizing air pressure had little effect. Analysis of the spray patterns indicates that two classifications of droplets are present, a finely dispersed 'mist' of very small droplets and much larger ligaments of liquor that form at the injector tip and form one or more relatively large droplets. This ligament and subsequent large droplet formation suggests that it will be challenging to obtain a narrow distribution of droplet sizes when using an injector of this design. A model for simulating liquor spray and droplet formation was developed by Simulent, Inc. of Toronto. The model was able to predict performance when spraying water that closely matched the vendor specifications. Simulation of liquor spray indicates that droplets on the order 200-300 microns can be expected, and that higher liquor flow will result in be