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Sample records for generation safeguards initiative

  1. 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 ...

  2. 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

  3. 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 ...

  4. NNSA Next Generation Safeguards Initiative | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) NNSA Next Generation Safeguards Initiative January 02, 2009 International safeguards are a central pillar of the nuclear nonproliferation regime. Administered by the International Atomic Energy Agency (IAEA), international safeguards serve to monitor nuclear activities under the Non-Proliferation Treaty (NPT) and are the primary vehicle for verifying compliance with peaceful use and nuclear nonproliferation undertakings. The Department of Energy's National Nuclear

  5. Oak Ridge National Laboratory Next Generation Safeguards Initiative

    SciTech Connect (OSTI)

    Kirk, Bernadette Lugue; Eipeldauer, Mary D; Whitaker, J Michael

    2011-12-01

    In 2007, the Department of Energy's 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 impacting the mission of international safeguards and the implications of expanding and evolving mission requirements on the legal authorities and institutions that serve as the foundation of the international safeguards system, as well as 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)'. One of the report's key recommendations was for DOE/NNSA to launch a major new program to revitalize the international safeguards technology and human resource base. In 2007, at the International Atomic Energy Agency's General Conference, then Secretary of Energy Samuel W. Bodman announced the newly created Next Generation Safeguards Initiative (NGSI). NGSI consists of five program elements: (1) Policy development and outreach; (2) Concepts and approaches; (3) Technology and analytical methodologies; (4) Human resource development; and (5) Infrastructure development. The ensuing report addresses the 'Human Resource Development (HRD)' component of NGSI. The goal of the HRD as defined in the NNSA Program Plan (November 2008) is 'to revitalize and expand the international safeguards human capital base by attracting and training a new generation of talent.' One of the major objectives listed in the HRD goal includes education and training, outreach to universities, professional societies, postdoctoral appointments, and summer internships at national laboratories. ORNL is a participant in the NGSI program, together with several DOE laboratories such as Pacific

  6. 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

  7. 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.

  8. 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.

  9. 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

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

    National Nuclear Security Administration (NNSA)

    safeguards, which protect against proliferation. "Effective nuclear safeguards are the ... system can grow to meet new proliferation challenges as we prepare for global ...

  11. 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 ...

  12. 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.

  13. 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.

  14. The Next Generation Safeguards Initiative s High-Purity Uranium-233 Preservation Effort

    SciTech Connect (OSTI)

    Krichinsky, Alan M; Bostick, Debra A; Giaquinto, Joseph; Bayne, Charles; Goldberg, Dr. Steven A.; Humphrey, Dr. Marc; Hutcheon, Dr. Ian D.; Sobolev, Taissa

    2012-01-01

    High-purity 233U serves as a crucial reference material for accurately quantifying and characterizing uranium. The most accurate analytical results which can be obtained only with high-purity 233U certified reference material (CRM) are required when used to confirm compliance with international safeguards obligations and international nonproliferation agreements. The U.S. supply of 233U CRM is almost depleted, and existing domestic stocks of this synthetic isotope are scheduled to be down-blended for disposition with depleted uranium beginning in 2015. Down blending batches of high-purity 233U will permanently eliminate the value of this material as a CRM. Furthermore, no replacement 233U stocks are expected to be produced in the future due to a lack of operating production capability and the high cost of replacing such capability. Therefore, preserving select batches of high-purity 233U is of great value and will assist in retaining current analytical capabilities for uranium-bearing samples. Any organization placing a priority on accurate results of uranium analyses, or on the confirmation of trace uranium in environmental samples, has a vested interest in preserving this material. This paper describes the need for high-purity 233U, the consequences organizations and agencies face if this material is not preserved, and the progress and future plans for preserving select batches of the purest 233U materials from disposition. This work is supported by the Next Generation Safeguards Initiative, Office of Nonproliferation and International Security, National Nuclear Security Administration.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

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

    SciTech Connect (OSTI)

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

    2011-01-01

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

  1. 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.

  2. 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

  3. 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...

  4. safeguards

    National Nuclear Security Administration (NNSA)

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

  5. safeguards

    National Nuclear Security Administration (NNSA)

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

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

    National Nuclear Security Administration (NNSA)

    This Site Budget IG Web Policy Privacy No Fear Act Accessibility FOIA Sitemap Federal Government The White House DOE.gov USA.gov Jobs Apply for Our Jobs Our Jobs Working at NNSA...

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

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

    ... And we know that the political will and the resiliency of the nonproliferation regime are ... So I commend you for your work, for attendance and attention and for your participation ...

  8. 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

  9. 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.

  10. 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.

  11. NGSI Safeguards by Design | National Nuclear Security Administration |

    National Nuclear Security Administration (NNSA)

    (NNSA) Nonproliferation and Arms Control / International Nuclear Safeguards NGSI Safeguards by Design NNSA's Next Generation Safeguards Initiative (NGSI) sponsors a project promoting international Safeguards by Design (SBD). The International Atomic Energy Agency (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,

  12. Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)

    SciTech Connect (OSTI)

    Dr. Mark Schanfein; Philip Casey Durst

    2012-07-01

    The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

  13. 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.

  14. Integrated safeguards testing laboratories in support of the advanced fuel cycle initiative

    SciTech Connect (OSTI)

    Santi, Peter A; Demuth, Scott F; Klasky, Kristen L; Lee, Haeok; Miller, Michael C; Sprinkle, James K; Tobin, Stephen J; Williams, Bradley

    2009-01-01

    A key enabler for advanced fuel cycle safeguards research and technology development for programs such as the Advanced Fuel Cycle Initiative (AFCI) is access to facilities and nuclear materials. This access is necessary in many cases in order to ensure that advanced safeguards techniques and technologies meet the measurement needs for which they were designed. One such crucial facility is a hot cell based laboratory which would allow developers from universities, national laboratories, and commercial companies to perform iterative research and development of advanced safeguards instrumentation under realistic operating conditions but not be subject to production schedule limitations. The need for such a facility arises from the requirement to accurately measure minor actinide and/or fission product bearing nuclear materials that cannot be adequately shielded in glove boxes. With the contraction of the DOE nuclear complex following the end of the cold war, many suitable facilities at DOE sites are increasingly costly to operate and are being evaluated for closure. A hot cell based laboratory that allowed developers to install and remove instrumentation from the hot cell would allow for both risk mitigation and performance optimization of the instrumentation prior to fielding equipment in facilities where maintenance and repair of the instrumentation is difficult or impossible. These benefits are accomplished by providing developers the opportunity to iterate between testing the performance of the instrumentation by measuring realistic types and amounts of nuclear material, and adjusting and refining the instrumentation based on the results of these measurements. In this paper, we review the requirements for such a facility using the Wing 9 hot cells in the Los Alamos National Laboratory's Chemistry and Metallurgy Research facility as a model for such a facility and describe recent use of these hot cells in support of AFCI.

  15. The Next Generation Safeguards Initiative s High-Purity Uranium...

    Office of Scientific and Technical Information (OSTI)

    Authors: Krichinsky, Alan M 1 ; Bostick, Debra A 1 ; Giaquinto, Joseph 1 ; Bayne, Charles 2 ; Goldberg, Dr. Steven A. 3 ; Humphrey, Dr. Marc 4 ; Hutcheon, Dr. Ian D. ...

  16. Next Generation Safeguards Initiatives at Los Alamos National...

    National Nuclear Security Administration (NNSA)

    ... for careers in government, industry, and at the International Atomic Energy Agency (IAEA). ... While at LANL, she assists with projects in x-ray fluorescence to measure plutonium ...

  17. 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

  18. 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

  19. 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.

  20. 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.

  1. Safeguards Culture

    SciTech Connect (OSTI)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2012-07-01

    The concepts of nuclear safety and security culture are well established; however, a common understanding of safeguards culture is not internationally recognized. Supported by the National Nuclear Security Administration, the authors prepared this report, an analysis of the concept of safeguards culture, and gauged its value to the safeguards community. The authors explored distinctions between safeguards culture, safeguards compliance, and safeguards performance, and evaluated synergies and differences between safeguards culture and safety/security culture. The report concludes with suggested next steps.

  2. 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.

  3. land art generator initiative | OpenEI Community

    Open Energy Info (EERE)

    land art generator initiative Home Dc's picture Submitted by Dc(266) Contributor 20 March, 2015 - 11:22 Public Art Generates Renewable Energy Beautifully biofuel art clean energy...

  4. 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.

  5. 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.

  6. NNSA Completes Fourth International Meeting on Next Generation Nuclear

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

    Safeguards | National Nuclear Security Administration | (NNSA) NNSA Completes Fourth International Meeting on Next Generation Nuclear Safeguards July 12, 2012 HANOI, VIETNAM - The U.S. Department of Energy's National Nuclear Security Administration (NNSA), together with the Vietnam Agency for Radiation and Nuclear Safety, announced today the successful completion of the Fourth International Meeting on Next Generation Safeguards. Organized by NNSA's Next Generation Safeguards Initiative

  7. 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.

  8. 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

  9. Training in Environmental Analyses for Safeguards

    SciTech Connect (OSTI)

    Williams, R W; Gaffney, A M; Hutcheon, N A; Kersting, A B

    2009-05-28

    Responding to recommendations of the DOE/NNSA's Next Generation Safeguards Initiative, a new course, Training in Environmental Sample Analysis for IAEA Safeguards, is being offered as a summer internship opportunity at Lawrence Livermore National Laboratory. The first students completed the 8 week program during the summer of 2008. Interns are given training in the analysis of bulk environmental samples for safeguards through hands-on experience working in a clean laboratory, purifying U and Pu from bulk environmental samples, and measuring U and Pu isotope ratios by multi-collector ICP mass spectrometry. A series of lectures by invited safeguards and non-proliferation experts gives the students a broad picture of the safeguards work of the IAEA. At the end of the course, the students prepare a poster of their work to showcase at LLNL's summer student poster symposium. Both undergraduate and graduate students are recruited and hired as paid interns under the aegis of the Glenn T. Seaborg Institute in the Physical and Life Sciences Directorate at LLNL. This training course seeks to introduce students to analytical and interpretive skill-sets that are not generally taught at universities, and to encourage them to pursue careers with the IAEA.

  10. 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. DOEs Next Generation Safeguards Initiative (NGSI), and is jointly sponsored by the Offices of Non-proliferation and Nuclear Energy.

  11. Next GeNeratioN SafeGuardS iNitiative

    National Nuclear Security Administration (NNSA)

    we will strengthen the Nuclear Non-Proliferation Treaty as a basis for cooperation...To ... power without increasing the risks of proliferation." iNterNatioNal CollaboratioN oN Next ...

  12. 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.

  13. 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.

  14. 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.

  15. 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 Administrations (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 IAEAs 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 NNSAs 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).

  16. Integrating Safeguards and Security with Safety into Design

    SciTech Connect (OSTI)

    Robert S. Bean; John W. Hockert; David J. Hebditch

    2009-05-01

    There is a need to minimize security risks, proliferation hazards, and safety risks in the design of new nuclear facilities in a global environment of nuclear power expansion, while improving the synergy of major design features and raising operational efficiency. In 2008, the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA) launched the Next Generation Safeguards Initiative (NGSI) covering many safeguards areas. One of these, launched by NNSA with support of the DOE Office of Nuclear Energy, was a multi-laboratory project, led by the Idaho National Laboratory (INL), to develop safeguards by design. The proposed Safeguards-by-Design (SBD) process has been developed 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 security, and safety objectives into the overall design process for the nuclear facility lifecycle. A graded, iterative process was developed to integrate these areas throughout the project phases. It identified activities, deliverables, interfaces, and hold points covering both domestic regulatory requirements and international safeguards using the DOE regulatory environment as exemplar to provide a framework and guidance for project management and integration of safety with security during design. Further work, reported in this paper, created a generalized SBD process which could also be employed within the licensed nuclear industry and internationally for design of new facilities. Several tools for integrating safeguards, safety, and security into design are discussed here. SBD appears complementary to the EFCOG TROSSI process for security and safety integration created in 2006, which focuses on standardized upgrades to enable existing DOE facilities to meet a more severe design basis threat. A collaborative approach is suggested.

  17. 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.

  18. 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 countrys nonproliferation posture can be a useful tool.

  19. Eastern Renewable Generation Integration Study: Initial Results (Poster)

    SciTech Connect (OSTI)

    Bloom, A.; Townsend, A.; Hummon, M.; Weekley, A.; Clark, K.; King, J.

    2013-10-01

    This poster presents an overview of the Eastern Renewable Generation Integration Study, which aims to answer critical questions about the future of the Eastern Interconnection under high levels of solar and wind generation penetration.

  20. 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 IAEAs Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facilitys general character, purpose, capacity, and location; (2) Description of the facilitys 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

  1. SARP-II: Safeguards Accounting and Reports Program, Revised

    SciTech Connect (OSTI)

    Kempf, C.R.

    1994-03-01

    A computer code, SARP (Safeguards Accounting and Reports Program) which will generate and maintain at-facility safeguards accounting records, and generate IAEA safeguards reports based on accounting data input by the user, was completed in 1990 by the Safeguards, Safety, and Nonproliferation Division (formerly the Technical Support Organization) at Brookhaven National Laboratory as a task under the US Program of Technical Support to IAEA safeguards. The code was based on a State System of Accounting for and Control of Nuclear Material (SSAC) for off-load refueled power reactor facilities, with model facility and safeguards accounting regime as described in IAEA Safeguards Publication STR-165. Since 1990, improvements in computing capabilities and comments and suggestions from users engendered revision of the original code. The result is an updated, revised version called SARP-II which is discussed in this report.

  2. 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.

  3. 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

  4. 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.

  5. Nuclear Resonance Fluorescence for Safeguards Applications

    SciTech Connect (OSTI)

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

    2011-02-04

    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.

  6. safeguards and security

    National Nuclear Security Administration (NNSA)

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

  7. 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, ...

  8. Advanced safeguards for the nuclear renaissance

    SciTech Connect (OSTI)

    Miller, Michael C; Menlove, Howard O

    2008-01-01

    The global expansion of nuclear energy provides not only the benefit of carbon-neutral electricity, but also the potential for proliferation concern as well. Nuclear safeguards implemented at the state level (domestic) and at the international level by the International Atomic Energy Agency (IAEA) are essential for ensuring that nuclear materials are not misused and are thereby a critical component of the increased usage of nuclear energy. In the same way that the 1950's Atoms for Peace initiative provided the foundation for a robust research and development program in nuclear safeguards, the expansion of nuclear energy that is underway today provides the impetus to enter a new era of technical development in the safeguards community. In this paper, we will review the history of nuclear safeguards research and development as well future directions.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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

  15. 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.

  16. 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

  17. 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.

  18. 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.

  19. 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.

  20. 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/)

  1. 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

  2. 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

  3. 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

  4. 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.

  5. safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    safeguards WSU Mechanical Engineering students unveil their solutions to help PNNL researchers with nonproliferation and international safeguards work Pacific Northwest National Laboratory (PNNL) has partnered with Washington State University students for the past seven years to develop new instruments, tools, and methods to support nonproliferation and international safeguards. The students unveiled their latest designs last month in Richland,... Nuclear Verification Challenge: Maintain the

  6. Initial

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

    ... Initial operation of the first amplifier stage resulted in self-lasing due to an optical cavity between the polarizing beam-splitter cube and the 0 reflecting mirror a setup ...

  7. 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.

  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)]

    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.

  10. 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.

  11. Facility Safeguardability Analysis In Support of Safeguards-by-Design

    SciTech Connect (OSTI)

    Philip Casey Durst; Roald Wigeland; Robert Bari; Trond Bjornard; John Hockert; Michael Zentner

    2010-07-01

    The following report proposes the use of Facility Safeguardability Analysis (FSA) to: i) compare and evaluate nuclear safeguards measures, ii) optimize the prospective facility safeguards approach, iii) objectively and analytically evaluate nuclear facility safeguardability, and iv) evaluate and optimize barriers within the facility and process design to minimize the risk of diversion and theft of nuclear material. As proposed by the authors, Facility Safeguardability Analysis would be used by the Facility Designer and/or Project Design Team during the design and construction of the nuclear facility to evaluate and optimize the facility safeguards approach and design of the safeguards system. Through a process of “Safeguards-by-Design” (SBD), this would be done at the earliest stages of project conceptual design and would involve domestic and international nuclear regulators and authorities, including the International Atomic Energy Agency (IAEA). The benefits of the Safeguards-by-Design approach is that it would clarify at a very early stage the international and domestic safeguards requirements for the Construction Project Team, and the best design and operating practices for meeting these requirements. It would also minimize the risk to the construction project, in terms of cost overruns or delays, which might otherwise occur if the nuclear safeguards measures are not incorporated into the facility design at an early stage. Incorporating nuclear safeguards measures is straight forward for nuclear facilities of existing design, but becomes more challenging with new designs and more complex nuclear facilities. For this reason, the facility designer and Project Design Team require an analytical tool for comparing safeguards measures, options, and approaches, and for evaluating the “safeguardability” of the facility. The report explains how preliminary diversion path analysis and the Proliferation Resistance and Physical Protection (PRPP) evaluation

  12. 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

    Generation Safeguards Initiative (NGSI).

  13. 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.

  14. International Nuclear Safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

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

  15. The effect of initial conditions on the electromagnetic radiation generation in type III solar radio bursts

    SciTech Connect (OSTI)

    Schmitz, H.; Tsiklauri, D.

    2013-06-15

    Extensive particle-in-cell simulations of fast electron beams injected in a background magnetised plasma with a decreasing density profile were carried out. These simulations were intended to further shed light on a newly proposed mechanism for the generation of electromagnetic waves in type III solar radio bursts [D. Tsiklauri, Phys. Plasmas, 18, 052903 (2011)]. The numerical simulations were carried out using different density profiles and fast electron distribution functions. It is shown that electromagnetic L and R modes are excited by the transverse current, initially imposed on the system. In the course of the simulations, no further interaction of the electron beam with the background plasma could be observed.

  16. Safeguards & Security | Department of Energy

    Energy Savers [EERE]

    The mission of the PPPO Safeguards and Security Program is to effectively implement the Office of Environmental Management ... Serves as the Federal liaison with the Nuclear Regulatory ...

  17. Los Alamos safeguards program overview and NDA in safeguards

    SciTech Connect (OSTI)

    Keepin, G.R. )

    1989-07-01

    The safeguards R and D program at Los Alamos will be outlined briefly, from its formal beginning in December 1966 to the present. From the start, an important factor in the success and ongoing achievements of the Los Alamos program has been a close technical liaison between safeguards researchers and the materials processing experts in the Laboratory's extensive nuclear material processing facilities. Some of the major contributions of the program to safeguards technology development and its effective implementation will be highlighted, together with a brief overview of the several ongoing safeguards training courses at Los Alamos for IAEA inspectors and safeguards professionals from the United States as well as many advanced and developing countries around the world.

  18. Fundamentals of materials accounting for nuclear safeguards ...

    Office of Scientific and Technical Information (OSTI)

    Fundamentals of materials accounting for nuclear safeguards Citation Details In-Document Search Title: Fundamentals of materials accounting for nuclear safeguards You are ...

  19. 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,...

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

    Office of Scientific and Technical Information (OSTI)

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

  1. 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.

  2. Generation and focusing of electron beams with initial transverse-longitudinal correlation

    SciTech Connect (OSTI)

    Harris, J. R.; Lewellen, J. W.; Poole, B. R.

    2014-10-07

    In charged particle beams, one of the roles played by space charge is to couple the transverse and longitudinal dynamics of the beam. This can lead to very complex phenomena which are generally studied using computer simulations. However, in some cases models based on phenomenological or analytic approximations can provide valuable insight into the system behavior. In this paper, we employ such approximations to investigate the conditions under which all the slices of a space charge dominated electron beam with slowly varying current could be focused to a waist with the same radius and at the same location, independent of slice current, and show that this can be accomplished approximately if the initial transverse-longitudinal correlation introduced onto the beam by the electron gun is chosen to compensate for the transverse-longitudinal correlation introduced onto the beam in the drift section. The validity of our approximations is assessed by use of progressively more realistic calculations. We also consider several design elements of electron guns that affect the initial correlations in the beams they generate.

  3. 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.

  4. 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.

  5. 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

  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: September 1, 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

  7. 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)

  8. 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...

  9. 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.

  10. International Nuclear Safeguards Inspection Support Tool (INSIST)

    SciTech Connect (OSTI)

    St. Pierre, D.E.; Steinmaus, K.L.; Moon, B.D.

    1994-07-01

    DOE is committed to providing technologies to the International Atomic Energy Agency (IAEA) to meet escalating monitoring and inspection requirements associated with the Non-Proliferation Treaty (NPT). One example of technology provided to the IAEA is the information management and remote monitoring capabilities being customized for the IAEA by the International Safeguards Division of the Office of Non-Proliferation and National Security. The ongoing Safeguards Information Management Systems (SIMS) program is an interlaboratory effort providing the IAEA with a range of information management capabilities designed to enhance the effectiveness of their nuclear inspection activities. The initial commitment involved the customization of computer capabilities to provide IAEA with the basic capability to geographically organize, store, and retrieve the large quantity of information involved in their nuclear on site inspection activities in Iraq. This initial system, the International Nuclear Safeguards Inspection Support Tool (INSIST), was developed by DOE`s Pacific Northwest Laboratory (PNL). To date, two INSIST workstations have been deployed at the IAEA. The first has been used to support the IAEA Action Team in the inspection of Iraqi nuclear facilities since August 1993. A second, and similar, workstation has been deployed to support environmental monitoring under the IAEA 93+2 Programme. Both INSIST workstations geographically integrate analog (video) and digital data to provide an easy to use and effective tool for storing retrieving and displaying multimedia site and facility information including world-wide maps, satellite and aerial imagery, on site photography, live inspection videos, and treaty and inspection textual information. The interactive, UNIX-based workstations have a variety of peripheral devices for information input and output. INSIST software includes commercial-off-the-shelf (COTS) modules and application-specific code developed at PNL.

  11. 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.

  12. 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.

  13. 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.

  14. 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: ...

  15. 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.

  16. Safeguards Transporter | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    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. 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.

  18. Global partnering related to nuclear materials safeguards and security - A pragmatic approach to international safeguards work

    SciTech Connect (OSTI)

    Stanford, Dennis

    2007-07-01

    This paper documents issues Nuclear Fuel Services, Inc. has addressed in the performance of international work to safeguards and security work. It begins with a description of the package we put together for a sample proposal for the Global Threat Reduction Initiative, for which we were ranked number one for technical approach and cost, and concludes with a discussion of approaches that we have taken to performing this work, including issues related to performing the work as part of a team. The primary focus is on communication, workforce, equipment, and coordination issues. Finally, the paper documents the rules that we use to assure the work is performed safely and successfully. (author)

  19. 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...

  20. 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.

  1. 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.

  2. Initial operating results of coal-fired steam generators converted to 100% refuse-derived fuel

    SciTech Connect (OSTI)

    Barsin, J.A. ); Graika, P.K. ); Gonyeau, J.A. ); Bloomer, T.M. )

    1988-01-01

    The conversion of Northern States Power Company's (NSP) Red Wing and Wilmarth steam generators to fire refuse-derived fuel (RDF) is discussed. The use of the existing plant with the necessary modifications to the boilers has allowed NSP to effectively incinerate the fuel as required by Washington and Ramsey Counties. This paper covers the six-month start-up of Red Wing No. 1, commencing in May 1987, and the operating results since the plant went commercial in July 1987.

  3. INITIAL EVALUATION OF A PULSED WHITE SPECTRUM NEUTRON GENERATOR FOR EXPLOSIVE DETECTION

    SciTech Connect (OSTI)

    King, Michael J.; Miller, Gill T.; Reijonen, Jani; Ji, Qing; Andresen, Nord; Gicquel,, Frederic; Kavlas, Taneli; Leung, Ka-Ngo; Kwan, Joe

    2008-06-02

    Successful explosive material detection in luggage and similar sized containers is acritical issue in securing the safety of all airline passengers. Tensor Technology Inc. has recently developed a methodology that will detect explosive compounds with pulsed fast neutron transmission spectroscopy. In this scheme, tritium beams will be used to generate neutrons with a broad energy spectrum as governed by the T(t,2n)4He fission reaction that produces 0-9 MeV neutrons. Lawrence Berkeley National Laboratory (LBNL), in collaboration with Tensor Technology Inc., has designedand fabricated a pulsed white-spectrum neutron source for this application. The specifications of the neutron source are demanding and stringent due to the requirements of high yield and fast pulsing neutron emission, and sealed tube, tritium operation. In a unique co-axial geometry, the ion source uses ten parallel rf induction antennas to externally couple power into a toroidal discharge chamber. There are 20 ion beam extraction slits and 3 concentric electrode rings to shape and accelerate the ion beam into a titanium cone target. Fast neutron pulses are created by using a set ofparallel-plate deflectors switching between +-1500 volts and deflecting the ion beams across a narrow slit. The generator is expected to achieve 5 ns neutron pulses at tritium ion beam energies between 80 - 120 kV. First experiments demonstrated ion source operation and successful beam pulsing.

  4. Simulation Enabled Safeguards Assessment Methodology

    SciTech Connect (OSTI)

    Robert Bean; Trond Bjornard; Thomas Larson

    2007-09-01

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

  5. 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)

  6. 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

  7. 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.

  8. 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.

  9. 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.

  10. a state department perspective on IAEA safeguards

    SciTech Connect (OSTI)

    Kessler, J.C. )

    1989-07-01

    The maintenance of effective international safeguards is a fundamental tenet of U.S. non-proliferation policy. The U.S. Department of State plays a substantial role not only in articulating U.S. non-proliferation policy, but in the implementation of that policy, including a substantial role in all aspects of U.S. support of IAEA safeguards. The State Department's role in supporting IAEA safeguards ranges from considerations related to bilateral agreements for cooperation in peaceful uses of nuclear energy and export control to many rather technical aspects of safeguards such as the U.S. Program of Technical Assistance to IAEA Safeguards (POTAS) and negotiation of Facility Attachments for U.S. nuclear facilities subject to IAEA safeguards. TSO plays an important role in support of these efforts by providing technical advice on a broad range of matters where technical and policy issues are closely intertwined.

  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. 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...

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

    Office of Scientific and Technical Information (OSTI)

    International safeguards recommendations for the Indian advanced heavy water reactor ... Visit OSTI to utilize additional information resources in energy science and technology. A ...

  14. 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, ...

  15. 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) ...

  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. 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: ...

  18. 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.

  19. Early AEC safeguards and TSO beginnings

    SciTech Connect (OSTI)

    Higinbotham, W.A. )

    1989-07-01

    In 1967, a committee at Brookhaven National Laboratory suggested that the Atomic Energy Commission (AEC) should establish a safeguards technical support organization at a national laboratory. In February 1968, the AEC established the Technical Support Organization (TSO) at Brookhaven. The AEC 1968 safeguards R and D program and the first TSO task assignments are summarized. To illustrate the nature of the national safeguards activities of TSO during the following 20 years, some of the many field exercises, systems studies, special project, and technical assistance on implementing safeguards measures are described briefly.

  20. 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 ...

  1. US Department of Energy Central Training Academy safeguards and technical security training program

    SciTech Connect (OSTI)

    Nessel, S. )

    1991-01-01

    In 1984 the U.S. Department of Energy (DOE) established the Central Training Academy (CTA). The academy's mission at that time was to provide state-of-the-art, standardized training to DOE and DOe contractor safeguards and security personnel. The CTA's primary mission still is to provide quality training of the safeguards and security personnel throughout the DOE who are, or may become, involved in the protection of vital national resources. Our major goals are to develop quality training instruction, use of an ongoing training evaluation program, establish and maintain a professional instructor cadre, and standardize training in the area of safeguards and security. This paper addresses current and future CTA training initiatives for safeguards and technical security programs. It also addresses specific courses, course content and objectives, and course prerequisites.

  2. Safeguards Considerations for Thorium Fuel Cycles

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

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

    2016-04-21

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

  3. Nuclear Safeguards and Nonproliferation Support | U.S. DOE Office...

    Office of Science (SC) Website

    Nuclear Safeguards and Nonproliferation Support NBL Program Office NBL PO Home About Programs Certified Reference Materials Program Measurement Evaluation Nuclear Safeguards and ...

  4. Success Through Safety, Security, and Safeguards by Design (3SBD...

    Office of Scientific and Technical Information (OSTI)

    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 ...

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

    Office of Scientific and Technical Information (OSTI)

    safeguards operations monitoring Citation Details In-Document Search Title: Simulated process test bed for integrated safeguards operations monitoring No abstract prepared. ...

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

    Office of Scientific and Technical Information (OSTI)

    Processing For Safeguards Monitoring System Citation Details In-Document Search Title: Using Rules-Based Event Processing For Safeguards Monitoring System No abstract prepared. ...

  7. Working Toward Robust Process Monitoring for Safeguards Applications...

    Office of Scientific and Technical Information (OSTI)

    Working Toward Robust Process Monitoring for Safeguards Applications Citation Details In-Document Search Title: Working Toward Robust Process Monitoring for Safeguards Applications ...

  8. 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...

  9. 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 ...

  10. 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, ...

  11. 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, ...

  12. 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: ...

  13. 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...

  14. 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 ...

  15. 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.

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

    SciTech Connect (OSTI)

    Barefield Ii, James E; Clegg, Samuel M; Lopez, Leon N; Le, Loan A; Veirs, D Kirk; Browne, Mike

    2010-01-01

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

  17. 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.

  18. 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.

  19. 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.

  20. NNSA and MEXT to Co-host Second International Meeting on Next Generation

    National Nuclear Security Administration (NNSA)

    Safeguards | National Nuclear Security Administration | (NNSA) and MEXT to Co-host Second International Meeting on Next Generation Safeguards October 20, 2009 NNSA and MEXT to Co-host Second International Meeting on Next Generation Safeguards WASHINGTON - The National Nuclear Security Administration (NNSA) and the Japanese Ministry of Education, Culture, Sports, Science and Technology (MEXT) will co-host the second international meeting on Next Generation Safeguards from Oct. 26 - 28, 2009

  1. 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.

  2. 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

  3. 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.

  4. 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.

  5. 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 Safeguards and Security Program, acronyms and abbereviations - DOE M 470.4-7 (381.95 KB) More Documents & Publications Safeguards and Security Glossary - DOE M

  6. 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 organizations 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.

  7. 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.

  8. 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....

  9. 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

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  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. U. S. safeguards history and the evolution of safeguards research and development

    SciTech Connect (OSTI)

    Brenner, L.M.; McDowell, S.C.T. )

    1989-07-01

    In discussing the U.S. safeguards history and the evolution of safeguards research and development, five significant eras are identified. The period ending January 1, 1947, may be called the first era. Safeguards as known today did not exist and the classic military approach of security protection applied. The second era covers the period from 1947 to 1954 (when the Atomic Energy Act was completely rewritten to accommodate the then foreseen Civil uses Program and international cooperation in peaceful uses of nuclear energy), and the first steps were taken by the Atomic Energy Commission to establish material accounting records for all source and fissionable materials on inventory. The third era covers the period 1954 through 1968, which focused on nuclear safeguards in its domestic activities and made major policy changes in its approach to material control and accountability. The fourth era, 1968 to 1972 saw a quantum jump in the recognition and need for a significant safeguards research and development program, answered by the formation of a safeguards technical support organization at Brookhaven National Laboratory and a safeguards Laboratory at Los Alamos Scientific Laboratory for the development and application of non-destructive assay technology. The fifth era had its beginning in 1972 with the burgeoning of international terrorism. The corresponding need for a strong physical protection research and development support program was responded to by the Sandia National Laboratory.

  17. 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.

  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. 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 ORO Office Safeguards and Security Clearance Tracking System and

  20. 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) PIA - Savannah River Nuclear Solutions Electronic Safeguards Security System (E3S) (3.6 MB) More Documents & Publications PIA - 10th International Nuclear Graphite Specialists Meeting registration web site PIA - HSPD-12 Physical and Logical

  1. 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 (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

  2. 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.

  3. 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.

  4. 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.

  5. International Atomic Energy Agency safeguards after Iraq - some Austrailian perceptions

    SciTech Connect (OSTI)

    Bardsley, J.; Carlson, J.; Hill, J.

    1994-12-31

    Iraq`s nuclear weapons development program used facilities and nuclear material separate from its safeguarded activities. To detect such a strategy the IAEA`s safeguards inspectors need access to locations and information beyond that foreseen in NPT safeguards agreements. But the IAEA is short of money. And detecting undeclared activities could be expensive. If the IAEA can establish a capability to detect undeclared activities, then it might be able to save on regular safeguards. But it`s important not to put the cart before the horse - effective safeguards must come first, savings second.

  6. 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.

  7. Safeguards technology development for spent fuel storage and disposal

    SciTech Connect (OSTI)

    Sanders, K.E. )

    1991-01-01

    This paper reports on facilities for monitored retrievable storage and geologic repository that will be operating in the US by 1998 and 2010 respectively. The international safeguards approach for these facilities will be determined broadly by the Safeguards Agreement and the IAEA Safeguards Criteria (currently available for 1991-1995) and defined specifically in the General Subsidiary Arrangements and Specific Facility Attachments negotiated under the US/IAEA Safeguards Agreement. Design information for these facilities types, as it is conceptualized, will be essential input to the safeguards approach. Unique design and operating features will translate into equally unique challenges to the application of international safeguards. The development and use of new safeguards technologies offers the greatest potential for improving safeguards. The development and use of new safeguards technologies offers the greatest potential for improving safeguards by enabling efficient and effective application with regard to the operator's interest, US policies, and the IAEA's statutorial obligations. Advanced unattended or remote measurement, authentication of operator's measurement, authentication of operator's measurement data, and integration of monitoring and containment/surveillance potentially are among the most fruitful areas of technology development. During the next year, a long range program plan for international safeguard technology development for monitored retrievable storage and geologic repository will be developed by the International Branch in close coordination with the Office of Civilian Radioactive Waste Management. This presentation preliminarily identifies elements of this long range program.

  8. Technical support organization efforts in support of IAEA safeguards

    SciTech Connect (OSTI)

    Gordon, D.M. )

    1989-07-01

    The Technical Support Organization (TSO) of the Brookhaven National Laboratory has been carrying out tasks in support of International Atomic Energy Agency (IAEA) safeguards since 1968, when TSO was founded. These tasks have been funded by both the Department of Energy Office of Safeguards and Security and by the United States Program of Technical Assistance to IAEA Safeguards (POTAS). These tasks have included a variety of systems studies (e.g. the zone approach to IAEA safeguards, the Safeguards Effectiveness Assessment Methodology, and international safeguards for uranium enrichment plants), development of instruments (e.g., the automated electromanometer and the load-cell-based weighing system for UF/sub 6/ cylinders), preparation of guidance documents, training of inspectors, and the development and evaluation of safeguards seals. This paper reviews some of the highlights from this program of support.

  9. Microsoft Word - NETL-TRS-X-2015_Field-Generated Foamed Cement Initial Collection, Computed Tomography, and Analysis.final.2015

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

    Field-Generated Foamed Cement: Initial Collection, Computed Tomography, and Analysis 20 July 2015 Office of Fossil Energy NETL-TRS-5-2015 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 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,

  10. 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.

  11. Implications for advanced safeguards derived from PR&PP case study results

    SciTech Connect (OSTI)

    Boyer, Brian D

    2009-01-01

    The proliferation resistance and physical protection (PR and PP) working group produced a case study on the Example Sodium Fast Reactor (ESFR). The ESFR is a hypothetical nuclear energy system consisting of four sodium-cooled fast reactors of medium size collocated with an on-site dry fuel storage facility and a spent fuel reprocessing facility using pyroprocessing technology. This study revealed how safeguards would be applied at such site consisting of integrated multiple fuel cycle facilities and the implications of what safeguards technology and safeguards concepts would need to be adapted and developed to safeguard successfully this Generation IV nuclear energy system concept. The major safeguards concepts driving our safeguards analysis are timeliness goals and material quantity goals. Because the fresh transuranic (TRU) fuel to be produced in the ESFR fuel fabrication facility contains plutonium, the ESFR will be reprocessing, using in the reactor, and storing material on site that will have IAEA defined 'direct-use material' in it with stringent timeliness goals and material quantity goals that drive the safeguards implementation. Specifically, the TRU fresh fuel, pyroprocessing in process material, LWR spent fuel sent to the ESFR, and TRU spent fuel will contain plutonium. This material will need to be verified at interim intervals four times per year because the irradiated direct-use material, as defined previously, has three-month timeliness goals and 8 kg material quantity goals for plutonium. The TRU in-process material is, of course, irradiated direct-use material as defined by the IAEA. Keeping the plutonium and uranium together with TRu products should provide a radiation barrier. this radiation barrier slows down the ability to reprocess the fuel. Furthermore, the reprocessing technique, if it has some intrinsic proliferation resistance, will need major modifications to be able to separate plutonium from the uranium and TRU mixture. The ESFR design

  12. 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

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

    SciTech Connect (OSTI)

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

    2011-10-10

    The safeguards system of the International Atomic Energy Agency (IAEA) provides the international community with credible assurance that a State is fulfilling its nonproliferation obligations. The IAEA draws such conclusions from the evaluation of all available information. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of this “State-level” approach. Efficiently used, the Safeguards by Design (SBD) methodologies , , , now being developed can contribute to effective and cost-efficient facility-level safeguards. The Facility Safeguardability Assessment (FSA) introduced here supports SBD in three areas. 1. It describes necessary interactions between the IAEA, the State regulator, and the owner / designer of a new or modified facility to determine where SBD efforts can be productively applied, 2. It presents a screening approach intended to identify potential safeguard issues for; a) design changes to existing facilities; b) new facilities similar to existing facilities with approved safeguards approaches, and c) new designs, 3. It identifies resources (the FSA toolkit), such as good practice guides, design guidance, and safeguardability evaluation methods that can be used by the owner/designer to develop solutions for potential safeguards issues during the interactions with the State regulator and IAEA. FSA presents a structured framework for the application of the SBD tools developed in other efforts. The more a design evolves, the greater the probability that new safeguards issues could be introduced. Likewise, for first-of-a-kind facilities or research facilities that involve previously unused processes or technologies, it is reasonable to expect that a number of possible safeguards issues might exist. Accordingly, FSA is intended to help the designer and its safeguards experts identify early in the design process: • Areas where elements of previous accepted safeguards approach(es) may be applied

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

    SciTech Connect (OSTI)

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

    2010-01-01

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

  16. Education in Safeguards and Security Technology Meeting Challenges with Technology and Experience

    SciTech Connect (OSTI)

    Paschal, Linda J; Chapman, Jeffrey Allen; Rowe, Nathan C; Stinson, Brad J

    2011-01-01

    Education and hands-on experience are crucial to ensuring a workforce of safeguards and security professionals who can meet the challenges currently faced in global nuclear safeguards and security. Global demand for nuclear energy and technology, the new Strategic Arms Reduction Treaty (START), and the cleanup of Cold War facilities have resulted in an increased need for trained safeguards and security personnel. At the same time, the global community is facing a growing shortage of experienced workers with hands-on knowledge of nuclear material processing. Limited access to operating facilities has dramatically reduced the opportunities for next-generation practitioners to obtain hands-on training experience. To address these needs, the Safeguards Technology Integration Center (STIC) at Oak Ridge National Laboratory was created as a Department of Energy User Facility to provide access both to the latest technology and to field-experienced professionals. The STIC provides real-world conditions, process equipment mock-ups, and controlled access to encapsulated radioactive materials (including highly enriched uranium and plutonium) for training and technology evaluation encompassing various techniques and skills, such as Radiation Inspection Systems, Containment and Surveillance Systems, Nondestructive Assay, Security System Performance Testing, and System Design and Analysis. The STIC facilities, laboratories, test beds, and training facilities are described along with the more notable aspects of the training program, which has included more than 1000 participants in the last four years.

  17. 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

  18. SAFEGUARD AND SECURE CONTROL VERIFY POLICY

    National Nuclear Security Administration (NNSA)

    Fall 2014 National Nuclear Security Administration ENERGY U.S. DEPARTMENT OF NIS Leads International Workshop to Strengthen Nuclear Safeguards Regime By Jessica WilBourne and sean dunlop T he National Nuclear Security Administration (NNSA)'s Office of Nonproliferation and International Security (NIS) recently concluded a five-day workshop aimed at strengthening the ability of countries to ensure that civilian nuclear material is not being used for the illicit manufacture of nuclear weapons.

  19. safeguards and security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    safeguards and security ProForce marks 65 years protecting Sandia resources, facilities, people Current and former members of the Lab's Protective Force gathered to reflect on and recognize the contributions ProForce has made to securing Sandia National Laboratory's resources, facilities, and people. Over the past 65 years, the force has changed in size and structure but its mission has... Nuclear Verification Challenge: Maintain the U.S. ability to monitor and verify nuclear reduction

  20. Implementation of Safeguards and Security Policy Panels

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

    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

  1. 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.

  2. 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

  3. 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.

  4. Project planning at the Hanford Site for International Atomic Energy Agency (IAEA) safeguards of excess fissile material

    SciTech Connect (OSTI)

    Smith, B.W.; McRae, L.P.; Walker, A.C.

    1995-06-01

    In his September 1993 address to the United Nations General Assembly, President Clinton proposed several initiatives to promote nuclear nonproliferation. One element is of these initiatives was that the United States offered to place excess fissile material under International Atomic Energy Agency @A) safeguards. Three Department of Energy (DOE) facilities were identified as part of a phased approach for initial implementation. This paper describes the planning process used to provide information to assist the DOE in making decisions for the initial offer, outlines tasks to be performed, and develops a budget request. The process consisted of: (1) Characterizing the Hanford Site from the perspective of IAEA safeguards; (2) identify key issues to be resolved; (3) developing budget estimates and schedules; (4) interfacing with other DOE components and the IAEA to clarify expected activities; and (5) initiating additional data collection and preparatory activities to reduce planning uncertainties.

  5. Memorandum, Safeguards & Security Policy Panels - February 15, 2008 |

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

    Department of Energy Memorandum, Safeguards & Security Policy Panels - February 15, 2008 Memorandum, Safeguards & Security Policy Panels - February 15, 2008 February 15, 2008 As outlined in the attached HSS memo, dated December 3,2007, subject: Safeguards and Security Policy Panels, the HSS Office of Security Policy is establishing several new policy panels that will create new opportunities for communication and will include those current active groups that are now effectively

  6. Integrating Safeguards, Security, & Emergency Services at CNS | Y-12

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

    National Security Complex Integrating Safeguards, ... Integrating Safeguards, Security, & Emergency Services at CNS Posted: October 14, 2015 - 5:34pm Lindy Pyatt, Y-12 S&S Performance Assurance Issues Management, assists Gannon Tucker, the CNS SS&ES change control administrator based at Pantex, with consolidating security's document control. Integrating organizations across two states (and two time zones) can be complex. The divisions within the Safeguards, Security, &

  7. New Measures to Safeguard Gas Centrifuge Enrichment Plants (Conference...

    Office of Scientific and Technical Information (OSTI)

    use equipment for process monitoring of load cells at feed and withdrawal (FW) stations. ... CAPACITY; GAS CENTRIFUGES; IAEA; MONITORING; ORNL; SAFEGUARDS; SENSORS; ...

  8. 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.

  9. 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...

  10. 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 ...

  11. 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 ...

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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.

  13. 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;...

  14. Practical issues associated with implementing an advanced safeguards...

    Office of Scientific and Technical Information (OSTI)

    at gas centrifuge enrichment facilities Citation Details In-Document Search Title: Practical issues associated with implementing an advanced safeguards approach at gas ...

  15. The IAEA and the International Safeguards System (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    The IAEA and the International Safeguards System Citation Details In-Document Search ... Sponsoring Org: DOELANL Country of Publication: United States Language: English Subject: ...

  16. 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.

  17. Voluntary Protection Program Onsite Review, Safeguards and Security- August 2012

    Broader source: Energy.gov [DOE]

    Evaluation to determine whether Safeguards and Security at Hanford is continuing to perform at a level deserving DOE-VPP Star recognition.

  18. 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.

  19. 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....

  20. A Brief History of International Safeguards (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    Research Org: Los Alamos National Laboratory (LANL) Sponsoring Org: DOELANL Country of Publication: United States Language: English Subject: Nuclear Disarmament, Safeguards, & ...

  1. International Safeguards Regime (Technical Report) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Research Org: Los Alamos National Laboratory (LANL) Sponsoring Org: DOELANL Country of Publication: United States Language: English Subject: Nuclear Disarmament, Safeguards, & ...

  2. 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.

  3. 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

  4. Safeguards and security modeling for electrochemical plants

    SciTech Connect (OSTI)

    Cipiti, B.B.; Duran, F.A.; Mendoza, L.A.; Parks, M.J.; Dominguez, D.; Le, T.D.

    2013-07-01

    Safeguards and security design for reprocessing plants can lead to excessive costs if not incorporated early in the design process. The design for electrochemical plants is somewhat uncertain since these plants have not been built at a commercial scale in the past. The Separation and Safeguards Performance Model (SSPM), developed at Sandia National Laboratories, has been used for safeguards design and evaluation for multiple reprocessing plant types. The SSPM includes the following capabilities: -) spent fuel source term library, -) mass tracking of elements 1-99 and bulk solid/liquids, -) tracking of heat load and activity, -) customisable measurement points, -) automated calculation of ID and error propagation, -) alarm conditions and statistical tests, and -) user-defined diversion scenarios. Materials accountancy and process monitoring data can provide more timely detection of material loss specifically to protect against the insider threat. While the SSPM is capable of determining detection probabilities and examining detection times for material loss scenarios, it does not model the operations or spatial effects for a plant design. The STAGE software was chosen to model the physical protection system. STAGE provides a framework to create end-to-end scalable force-on-force combat simulations. It allows for a complete 3D model of a facility to be designed along with the design of physical protection elements. This software, then, can be used to model operations and response for various material loss scenarios. The future integration of the SSPM model data with the STAGE software will provide a more complete analysis of diversion scenarios to assist plant designers.

  5. 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.

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

    Office of Scientific and Technical Information (OSTI)

    System for Testing Safeguards Monitoring Systems and Strategies Intended for ... Title: A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and ...

  7. 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.

  8. 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.

  9. 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

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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

  15. 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

  16. 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.

  17. 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.

  18. Apparatus for safeguarding a radiological source

    SciTech Connect (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.

  19. Nuclear Materials Management and Safeguards System (NMMSS)

    SciTech Connect (OSTI)

    Jacobsen, S.E.; Matthews, W.B. III; McKamy, E.D.; Pedigo, R.B. )

    1991-01-01

    This paper describes the Nuclear Materials Management and Safeguards System (NMMSS) which is sponsored by the Department of Energy and the Nuclear Regulatory Commission. The system serves national security and program management interests, and international interests in the programs for the peaceful application of nuclear energy and non-proliferation of nuclear weapons. Within the scope of the NMMSS are found all nuclear materials applied and controlled under United States law and related international agreements, including U.S. nuclear materials production programs and U.S. private nuclear industrial activities. In addition, its national and international scope enables it to provide services to other organizations such as the Arms Control and Disarmament Agency, the Department of State, and the U.S. Congress.

  20. 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.

  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. 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.

  3. 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

  4. U. S. department of energy safeguards research and development program and the brookhaven national laboratory technical support organization role

    SciTech Connect (OSTI)

    Hammond, G.A. )

    1989-07-01

    The Brookhaven National Laboratory (BNL) Technical Support Organization (TSO) has played a key role over the past 20 years in the evolution of much of the effective materials control and accountability systems implemented successfully at Department of Energy (DOE) facilities. The safeguards research and development program of the U.S. DOE is summarized, noting the contributions of the BNL-TSO. During 1977-79, the non-proliferation features of many nuclear fuel cycles were studied in support of the International Nuclear Fuel Cycle Evaluation. The Beirut bombings of 1982 led to increased emphasis on physical protection and to establishment of a Central Training Academy. High-level and all-DOE reviews of DOE safeguards and security led to major improvements in the management, operations, and assessment of DOE's safeguards and security programs during 1985-88. TSO is expected to continue to play a lead role in stimulating new research initiatives and in guiding the development that is necessary for future challenges in maintaining cost-effective and credible safeguards.

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

    National Nuclear Security Administration (NNSA)

    of America and the International Atomic Energy Agency for the Application of Safeguards ... The reports are converted by NMMSS into the following IAEA data files: * MBR-288-1 ...

  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. 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.

  8. 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).

  9. Nuclear safeguards and security: we can do better.

    SciTech Connect (OSTI)

    Johnston, R. G.; Warner, Jon S.; Garcia, A. R. E.; Martinez, R. K.; Lopez, L. N.; Pacheco, A. N.; Trujillo, S. J.; Herrera, A. M.; Bitzer, E. G. , III

    2005-01-01

    There are a number of practical ways to significantly improve nuclear safeguards and security. These include recognizing and minimizing the insider threat; using adversarial vulnerability assessments to find vulnerabilities and countermeasures; fully appreciating the disparate nature of domestic and international nuclear safeguards; improving tamper detection and tamper-indicating seals; not confusing the inventory and security functions; and recognizing the limitations of GPS tracking, contact memory buttons, and RFID tags. The efficacy of nuclear safeguards depends critically on employing sophisticated security strategies and effective monitoring hardware. The Vulnerability Assessment Team (VAT) at Los Alamos National Laboratory has extensively researched issues associated with nuclear safeguards, especially in the areas of tamper/intrusion detection, transport security, and vulnerability assessments. This paper discusses some of our findings, recommendations, and warnings.

  10. 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

  11. FY09 Advanced Instrumentation and Active Interrogation Research for Safeguards

    SciTech Connect (OSTI)

    D. L. Chichester; S. A. Pozzi; E. H. Seabury; J. L. Dolan; M. Flaska; J. T. Johnson; S. M. Watson; J. Wharton

    2009-08-01

    Multiple small-scale projects have been undertaken to investigate advanced instrumentation solutions for safeguard measurement challenges associated with advanced fuel cycle facilities and next-generation fuel reprocessing installations. These activities are in support of the U.S. Department of Energy's Fuel Cycle Research and Development program and its Materials Protection, Accounting, and Control for Transmutation (MPACT) campaign. 1) Work was performed in a collaboration with the University of Michigan (Prof. Sara Pozzi, co-PI) to investigate the use of liquid-scintillator radiation detectors for assaying mixed-oxide (MOX) fuel, to characterize its composition and to develop advanced digital pulse-shape discrimination algorithms for performing time-correlation measurements in the MOX fuel environment. This work included both simulations and experiments and has shown that these techniques may provide a valuable approach for use within advanced safeguard measurement scenarios. 2) Work was conducted in a collaboration with Oak Ridge National Laboratory (Dr. Paul Hausladen, co-PI) to evaluate the strengths and weaknesses of the fast-neutron coded-aperture imaging technique for locating and characterizing fissile material, and as a tool for performing hold-up measurements in fissile material handling facilities. This work involved experiments at Idaho National Laboratory, using MOX fuel and uranium metal, in both passive and active interrogation configurations. A complete analysis has not yet been completed but preliminary results suggest several potential uses for the fast neutron imaging technique. 3) Work was carried out to identify measurement approaches for determining nitric acid concentration in the range of 1 – 4 M and beyond. This work included laboratory measurements to investigate the suitability of prompt-gamma neutron activation analysis for this measurement and product reviews of other commercial solutions. Ultrasonic density analysis appears to be

  12. 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

  13. Nuclear Materials Safeguards and Security Upgrade Project Completed Under

    National Nuclear Security Administration (NNSA)

    Budget | National Nuclear Security Administration | (NNSA) 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

  14. General Davis kicks the tires on a Safeguards Transporter | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration | (NNSA) General Davis kicks the tires on a Safeguards Transporter Tuesday, October 6, 2015 - 8:43am NNSA Blog 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 nuclear weapons, components and special nuclear materials to

  15. 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.

  16. 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

  17. Safeguards Considerations for Thorium Fuel Cycles (Journal Article) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Safeguards Considerations for Thorium Fuel Cycles Citation Details In-Document Search This content will become publicly available on April 21, 2017 Title: Safeguards Considerations for Thorium Fuel Cycles We report that by around 2025, thorium-based fuel cycles are likely to be deployed internationally. States such as China and India are pursuing research, development, and deployment pathways toward a number of commercial-scale thorium fuel cycles, and they are already

  18. Characterization of the neutron source term and multiplicity of a spent fuel assembly in support of NSDA safeguards of spent nuclear fuel

    SciTech Connect (OSTI)

    Richard, Joshua G; Fensin, Michael L; Tobin, Stephen J; Swinhoe, Martyn T; Menlove, Howard O; Baciak, James

    2010-01-01

    The gross neutron signal (GNS) is being considered as part of a fingerprinting or neutron balance approach to safeguards of spent nuclear fuel (SNF). Because the GNS is composed of many derivative components, understanding the time-dependent contribution of these derivative components is crucial to gauging the limitations of these approaches. The major components of the GNS are ({alpha}, n), spontaneous fission (SF), and multiplication neutrons. A methodology was developed to link MCNPX burnup output files to SOURCES4C input files for the purpose of automatically generating both the ({alpha}, n) and SF signals. Additional linking capabilities were developed to write MCNPX multiplication input files using the data obtained from the SOURCES4C output files. In this paper, the following are presented: (1) the relative contributions by source nuclide to the ({alpha}, n) signal as a function of initial enrichment/burnup/cooling time; (2) the relative contributions by source nuclide to the SF signal as a function of initial enrichment/burnup/cooling time; (3) the relative contributions by reaction type ({alpha},n vs. SF) to the GNS; and (4) the multiplication of the GNS as a function of initial enrichment/burnup/cooling time/counting environment. By developing these technologies to characterize the GNS, we can better evaluate the viability of the GNS fingerprint and neutron balance concepts for SNF.

  19. THIEF: An interactive simulation of nuclear materials safeguards

    SciTech Connect (OSTI)

    Stanbro, W. D.

    1990-01-01

    The safeguards community is facing an era in which it will be called upon to tighten protection of nuclear material. At the same time, it is probable that safeguards will face more competition for available resources from other activities such as environmental cleanup. To exist in this era, it will be necessary to understand and coordinate all aspects of the safeguards system. Because of the complexity of the interactions involved, this process puts a severe burden on designers and operators of safeguards systems. This paper presents a simulation tool developed at the Los Alamos National Laboratory to allow users to examine the interactions among safeguards elements as they apply to combating the insider threat. The tool consists of a microcomputer-based simulation in which the user takes the role of the insider trying to remove nuclear material from a facility. The safeguards system is run by the computer and consists of both physical protection and MC A computer elements. All data elements describing a scenario can be altered by the user. The program can aid in training, as well as in developing threat scenarios. 4 refs.

  20. Data Mining Techniques to Estimate Plutonium, Initial Enrichment, Burnup, and Cooling Time in Spent Fuel Assemblies

    SciTech Connect (OSTI)

    Trellue, Holly Renee; Fugate, Michael Lynn; Tobin, Stephen Joesph

    2015-03-19

    The Next Generation Safeguards Initiative (NGSI), Office of Nonproliferation and Arms Control (NPAC), National Nuclear Security Administration (NNSA) of the U.S. Department of Energy (DOE) has sponsored a multi-laboratory, university, international partner collaboration to (1) detect replaced or missing pins from spent fuel assemblies (SFA) to confirm item integrity and deter diversion, (2) determine plutonium mass and related plutonium and uranium fissile mass parameters in SFAs, and (3) verify initial enrichment (IE), burnup (BU), and cooling time (CT) of facility declaration for SFAs. A wide variety of nondestructive assay (NDA) techniques were researched to achieve these goals [Veal, 2010 and Humphrey, 2012]. In addition, the project includes two related activities with facility-specific benefits: (1) determination of heat content and (2) determination of reactivity (multiplication). In this research, a subset of 11 integrated NDA techniques was researched using data mining solutions at Los Alamos National Laboratory (LANL) for their ability to achieve the above goals.

  1. Neural information processing and self-organizing maps as a tool in safeguarding storage facilities

    SciTech Connect (OSTI)

    Howell, J.A.; Fuyat, C.

    1993-08-01

    Storage facilities for nuclear materials and weapons dismantlement facilities could have a large number of sensors with the potential for generating large amounts of data. Because of the anticipated complexity and diversity of the data, efficient automatic algorithms are necessary to make interpretations and ensure secure and safe operation. New, advanced safeguards systems are needed to process the information gathered from monitors and make interpretations that are in the best interests of the facility or agency. In this paper we present a conceptual design for software to assist with processing these large quantities of data from storage facilities.

  2. 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.

  3. 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.

  4. 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.

  5. Sustainable Forest Bioenergy Initiative

    SciTech Connect (OSTI)

    Breger, Dwayne; Rizzo, Rob

    2011-09-20

    In the state’s Electricity Restructuring Act of 1998, the Commonwealth of Massachusetts recognized the opportunity and strategic benefits to diversifying its electric generation capacity with renewable energy. Through this legislation, the Commonwealth established one of the nation’s first Renewable Energy Portfolio Standard (RPS) programs, mandating the increasing use of renewable resources in its energy mix. Bioenergy, meeting low emissions and advanced technology standards, was recognized as an eligible renewable energy technology. Stimulated by the state’s RPS program, several project development groups have been looking seriously at building large woody biomass generation units in western Massachusetts to utilize the woody biomass resource. As a direct result of this development, numerous stakeholders have raised concerns and have prompted the state to take a leadership position in pursuing a science based analysis of biomass impacts on forest and carbon emissions, and proceed through a rulemaking process to establish prudent policy to support biomass development which can contribute to the state’s carbon reduction commitments and maintain safeguards for forest sustainability. The Massachusetts Sustainable Forest Bioenergy Initiative (SFBI) was funded by the Department of Energy and started by the Department of Energy Resources before these contentious biomass issues were fully raised in the state, and continued throughout the substantive periods of this policy development. Thereby, while SFBI maintained its focus on the initially proposed Scope of Work, some aspects of this scope were expanded or realigned to meet the needs for groundbreaking research and policy development being advanced by DOER. SFBI provided DOER and the Commonwealth with a foundation of state specific information on biomass technology and the biomass industry and markets, the most comprehensive biomass fuel supply assessment for the region, the economic development impact

  6. 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

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop

    Office of Energy Efficiency and Renewable Energy (EERE)

    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.

  15. 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.

  16. 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.

  17. 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.

  18. Lawrence Livermore National Laboratory Safeguards and Security quarterly progress report ending March 31, 1996

    SciTech Connect (OSTI)

    Davis, B.; Davis, G.; Johnson, D.; Mansur, D.L.; Ruhter, W.D.; Strait, R.S.

    1996-04-01

    LLNL carries out safeguards and security activities for DOE Office of Safeguards and Security (OSS) and other organizations within and outside DOE. LLNL is supporting OSS in 6 areas: safeguards technology, safeguards and materials accountability, computer security--distributed systems, complex-wide access control, standardization of security systems, and information technology and security center. This report describes the activities in each of these areas.

  19. 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.

  20. 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.

  1. 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.

  2. nuclear safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    two prototypes developed as part of their senior design projects to their Pacific Northwest National Laboratory mentors. The design projects were supported by the Next Generation ...

  3. Report on the September 2011 Meeting of the Next Generation Safegaurds Professional Network

    SciTech Connect (OSTI)

    Gitau, Ernest TN; Benz, Jacob M.

    2011-12-19

    The Next Generation Safeguards Professional Network (NGSPN) was established in 2009 by Oak Ridge National Laboratory targeted towards the engagement of young professionals employed in safeguards across the many national laboratories. NGSPN focuses on providing a mechanism for young safeguards professionals to connect and foster professional relationships, facilitating knowledge transfer between current safeguards experts and the next generation of experts, and acting as an entity to represent the interests of the international community of young and mid-career safeguards professionals. This is accomplished in part with a yearly meeting held at a national laboratory site. In 2011, this meeting was held at Pacific Northwest National Laboratory. This report documents the events and results of that meeting.

  4. 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

  5. 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 operators and the IAEAs 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 IAEAs 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.

  6. 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.

  7. 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.

  8. 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.

  9. International safeguards concepts for the Yucca Mountain Geological Repository

    SciTech Connect (OSTI)

    Case, R.S.

    1991-12-31

    This paper reports that the Nuclear Waste Policy Act of 1982 assigns DOE the responsibility to develop a mined geological repository for the long-term storage and isolation from the biosphere of spent civilian nuclear fuel and high level waste from U.S. defense and civilian reprocessing activities. In fulfilling this Congressional mandate, DOE has performed preliminary site characterization on several possible repository sites over the last decade. Recently, Congress delimited site characterization to the site at Yucca Mountain, Nevada for the US`s first mined geologic repository. Although the actual repository is not scheduled to begin operation until the first decade of the next century, planning ahead for international safeguards application to the site will allow resolution of issues which arise. This is especially true for geological repositories because of the large amount of material to be safeguarded and the materials` inaccessibility following repository closure. Further, these unique features of geological repositories may require the IAEA to reexamine its present safeguard philosophy with respect to the roles of Containment and Surveillance (C/S) and Material Control and Accountancy (MC and A). In light of these issues, a C/S based international safeguard concept for Yucca Mountain has been developed and is presented here, using the DOE`s baseline conceptual design of the Yucca Mountain site.

  10. 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.

  11. Swedish experiences in implementing national and international safeguards

    SciTech Connect (OSTI)

    Nilsson, A. ); Elborn, M. ); Grahn, P. )

    1991-01-01

    This paper reports that international safeguards have been applied in Sweden since the early 70s. Experiences have been achieved from exclusive bilateral and trilateral control followed by NPT safeguards in 1975. The Swedish State System for accountancy and Control (SSAC) includes all regulations that follows from prevailing obligations regarding the peaceful uses of nuclear material. The system has been developed in cooperation between the national authority, the Swedish Nuclear Power Inspectorate (SKI) and the Swedish nuclear industry. The paper presents experiences from the practical implementation of the SSAC and the IAEA safeguards system, gained by the SKI and the nuclear industry, respectively. Joint approaches and solutions to some significant safeguards issues are presented. The cooperation between the nuclear industry and the authority in R and D activities, in particular with respect to the Swedish Support Program is highlighted, e.g. the use of nuclear facilities in development or training tasks. some of the difficulties encountered with the system are also touched upon.

  12. 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.

  13. 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.

  14. 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.

  15. 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

  16. 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

  17. Petascale Initiative

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

    Petascale Initiative Exascale Computing APEX Home » R & D » Archive » Petascale Initiative Petascale Initiative Alice Koniges (third from left) led the Computational Science and Engineering Petascale Initiative, which paired post-doctoral researchers with high-impact projects at NERSC. Post-docs pictured above are (from left) are Jihan Kim, Filipe Maia, Robert Preissl, Brian Austin, Wangyi (Bobby) Liu , Kirsten Fagnan and Praveen Narayanan. (Not pictured: Christos Kavouklis, Xuefei

  18. Neutron Generators for Spent Fuel Assay

    SciTech Connect (OSTI)

    Ludewigt, Bernhard A

    2010-12-30

    The Next Generation Safeguards Initiative (NGSI) of the U.S. DOE has initiated a multi-lab/university collaboration to quantify the plutonium (Pu) mass in, and detect the diversion of pins from, spent nuclear fuel (SNF) assemblies with non-destructive assay (NDA). The 14 NDA techniques being studied include several that require an external neutron source: Delayed Neutrons (DN), Differential Die-Away (DDA), Delayed Gammas (DG), and Lead Slowing-Down Spectroscopy (LSDS). This report provides a survey of currently available neutron sources and their underlying technology that may be suitable for NDA of SNF assemblies. The neutron sources considered here fall into two broad categories. The term 'neutron generator' is commonly used for sealed devices that operate at relatively low acceleration voltages of less than 150 kV. Systems that employ an acceleration structure to produce ion beam energies from hundreds of keV to several MeV, and that are pumped down to vacuum during operation, rather than being sealed units, are usually referred to as 'accelerator-driven neutron sources.' Currently available neutron sources and future options are evaluated within the parameter space of the neutron generator/source requirements as currently understood and summarized in section 2. Applicable neutron source technologies are described in section 3. Commercially available neutron generators and other source options that could be made available in the near future with some further development and customization are discussed in sections 4 and 5, respectively. The pros and cons of the various options and possible ways forward are discussed in section 6. Selection of the best approach must take a number of parameters into account including cost, size, lifetime, and power consumption, as well as neutron flux, neutron energy spectrum, and pulse structure that satisfy the requirements of the NDA instrument to be built.

  19. 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.

  20. 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.

  1. 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

  2. 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

  3. 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

  4. 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 3

  5. 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).

  6. Nuclear Materials Safeguards and Security Upgrade Project | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration 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. 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

  8. Selected topics in special nuclear materials safeguard system design

    SciTech Connect (OSTI)

    King, L.L.; Thatcher, C.D.; Clarke, J.D. ); Rodriguez, M.P. )

    1991-01-01

    During the past two decades the improvements in circuit integration have given rise to many new applications in digital processing technology by continuously reducing the unit cost of processing power. Along with this increase in processing power a corresponding decrease in circuit volume has been achieved. Progress has been so swift that new classes of applications become feasible every 2 or 3 years. This is especially true in the application of proven new technology to special nuclear materials (SNM) safeguard systems. Several areas of application were investigated in establishing the performance requirements for the SNM safeguard system. These included the improvements in material control and accountability and surveillance by using multiple sensors to continuously monitor SNM inventory within the selected value(s); establishing a system architecture to provide capabilities needed for present and future performance requirements; and limiting operating manpower exposure to radiation. This paper describes two selected topics in the application of state-of-the-art, well-proven technology to SNM safeguard system design.

  9. 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.

  10. Differential Die-Away Instrument: Report on Fuel Assembly Mock-up Measurements with Neutron Generator

    SciTech Connect (OSTI)

    Goodsell, Alison Victoria; Swinhoe, Martyn Thomas; Henzl, Vladimir; Rael, Carlos D.; Desimone, David J.

    2014-09-18

    Fresh fuel experiments for the differential die-away (DDA) project were performed using a DT neutron generator, a 15x15 PWR fuel assembly, and nine 3He detectors in a water tank inside of a shielded cell at Los Alamos National Laboratory (LANL). Eight different fuel enrichments were created using low enriched (LEU) and depleted uranium (DU) dioxide fuel rods. A list-mode data acquisition system recorded the time-dependent signal and analysis of the DDA signal die-away time was performed. The die-away time depended on the amount of fissile material in the fuel assembly and the position of the detector. These experiments were performed in support of the spent nuclear fuel Next Generation Safeguards Initiative DDA project. Lessons learned from the fresh fuel DDA instrument experiments and simulations will provide useful information to the spent fuel project.

  11. Projects & Initiatives

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

    Expand Finance & Rates Involvement & Outreach Expand Involvement & Outreach Doing Business Expand Doing Business Skip navigation links Initiatives Columbia River Treaty Non...

  12. 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

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

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

    ... Posting notices * Security badges and credentials 4. Safeguards and security personnel ... validation testing * Maintenance * Posting notices * Security badges and credentials g. ...

  14. 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.

  15. 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...

  16. The first 50 years: A review of the Department of Energy domestic safeguards and security program

    SciTech Connect (OSTI)

    Desmond, W.J.; Zack, N.R.; Tape, J.W.

    1997-12-01

    World War II not only brought the United States rapidly into the nuclear age, but it also brought a new term, {open_quotes}safeguards.{close_quotes} By that time, physical security was an already established activity that dealt with the protection of possessions such as property, vehicles, and other valuables. A secret nuclear project under a stadium at the University of Chicago would add a new dimension to physical security. Similarly, a community known only by its post office box at a location 27 miles from Santa Fe, New Mexico (PO Box 1663) would initiate new programs to protect information and technology while their programs changed the science and warfare around the world. The Manhattan Project and what was to become the Los Alamos Scientific Laboratory (now Los Alamos National Laboratory) would extend the applications of physical security and, soon to be implemented, safeguards to produce important technical advances for the protection, accounting, control, and nonproliferation of fissile nuclear materials. Security for nuclear materials and weapons information began as a foremost consideration with the start of the nuclear programs in the early 1940s. In the 1960s, the Atoms for Peace Program promoted the peaceful use of nuclear energy and made the US a supplier of nuclear materials and peaceful-use nuclear technology to other states. This program also changed the focus on nuclear materials from that of worldwide control to inspection by an independent agency, the proposed International Atomic Energy Agency. At this same time the nuclear weapons states increased from three to five. Other nations worked to obtain a nuclear weapons capability, resulting in increasing concerns about nuclear proliferation.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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)

  2. 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.

  3. 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,

  4. 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.

  5. National Nuclear Security Administration ENERGY U.S. DEPARTMENT OF

    National Nuclear Security Administration (NNSA)

    Operating Efficiently / Engaging Globally FY 2013 Annual Report Table of Contents 1 Operating Efficiently / Engaging Globally 2 Office of Nonproliferation and International Security 4 Office of Nuclear Safeguards and Security 5 Next Generations Safeguards Initiative (NGSI) 6 International Nuclear Safeguards Engagement Program (INSEP): First Engagement with Burma 7 Safeguards Technology Development 9 Safeguards Policy: IAEA Transit Matching Workshop 10 International Nuclear Security (INS) 12

  6. 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

  7. 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.

  8. 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.

  9. 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)

  10. 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).

  11. 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.

  12. 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.

  13. Monolithic exploding foil initiator

    DOE Patents [OSTI]

    Welle, Eric J; Vianco, Paul T; Headley, Paul S; Jarrell, Jason A; Garrity, J. Emmett; Shelton, Keegan P; Marley, Stephen K

    2012-10-23

    A monolithic exploding foil initiator (EFI) or slapper detonator and the method for making the monolithic EFI wherein the exploding bridge and the dielectric from which the flyer will be generated are integrated directly onto the header. In some embodiments, the barrel is directly integrated directly onto the header.

  14. Implementation of remove monitoring in facilities under safeguards with unattended systems

    SciTech Connect (OSTI)

    Beddingfield, David H; Nordquist, Heather A; Umebayaashi, Eiji

    2009-01-01

    Remote monitoring is being applied by the International Atomic Energy Agency (IAEA) at nuclear facilities around the world. At the Monju Reactor in Japan we have designed, developed and implemented a remote monitoring approach that can serve as a model for applying remote monitoring to facilities that are already under full-scope safeguards using unattended instrumentation. Remote monitoring implementations have historically relied upon the use of specialized data collection hardware and system design features that integrate remote monitoring into the safeguards data collection system. The integration of remote monitoring and unattended data collection increases the complexity of safeguards data collection systems. This increase in complexity necessarily produces a corresponding reduction of system reliability compared to less-complex unattended monitoring systems. At the Monju facility we have implemented a remote monitoring system that is decoupled from the activity of safeguards data collection. In the completed system the function of remote data transfer is separated from the function of safeguards data collection. As such, a failure of the remote monitoring function cannot produce an associated loss of safeguards data, as is possible with integrated remote-monitoring implementations. Currently, all safeguards data from this facility is available to the IAEA on a 24/7 basis. This facility employs five radiation-based unattended systems, video surveillance and numerous optical seal systems. The implementation of remote monitoring at this facility, while increasing the complexity of the safeguards system, is designed to avoid any corresponding reduction in reliability of the safeguards data collection systems by having decoupled these functions. This design and implementation can serve as a model for implementation of remote monitoring at nuclear facilities that currently employ unattended safeguards systems.

  15. 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.

  16. 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.

  17. SCB initiator

    DOE Patents [OSTI]

    Bickes Jr., Robert W.; Renlund, Anita M.; Stanton, Philip L.

    1994-11-01

    A detonator for high explosives initiated by mechanical impact includes a cylindrical barrel, a layer of flyer material mechanically covering the barrel at one end, and a semiconductor bridge ignitor including a pair of electrically conductive pads connected by a semiconductor bridge. The bridge is in operational contact with the layer, whereby ignition of said bridge forces a portion of the layer through the barrel to detonate the explosive. Input means are provided for igniting the semiconductor bridge ignitor.

  18. SCB initiator

    DOE Patents [OSTI]

    Bickes, Jr., Robert W. (Albuquerque, NM); Renlund, Anita M. (Albuquerque, NM); Stanton, Philip L. (Albuquerque, NM)

    1994-01-01

    A detonator for high explosives initiated by mechanical impact includes a cylindrical barrel, a layer of flyer material mechanically covering the barrel at one end, and a semiconductor bridge ignitor including a pair of electrically conductive pads connected by a semiconductor bridge. The bridge is in operational contact with the layer, whereby ignition of said bridge forces a portion of the layer through the barrel to detonate the explosive. Input means are provided for igniting the semiconductor bridge ignitor.

  19. 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.

  20. 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.

  1. 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.

  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. 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.

  4. Development of Metallic Magnetic Calorimeters for Nuclear Safeguards Applications

    SciTech Connect (OSTI)

    Bates, Cameron Russell

    2015-03-11

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

  5. 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 countrys safeguards agreement with the

  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. 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.

  8. 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.

  9. 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)

  10. Clean Electricity Initiatives in California

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

    Edward Randolph Director, Energy Division California Public Utilities Commission July 14, 2014 2014 EIA Energy Conference Clean Electricity Policy Initiatives In California (Partial) * Wholesale Renewables : - Renewables Portfolio Standard - Feet in Tariffs (RAM & ReMAT) - All source procurement (under development) * Customer Renewable Generation - California Solar Initiative - Net Energy Metering - Green Tariffs - Energy Efficiency - Demand Response - Rate Reform - Storage - Retirement of

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

    National Nuclear Security Administration (NNSA)

    Peaceful Nuclear Energy Infrastructure | National Nuclear Security Administration | (NNSA) U.S. and Tunisia to Cooperate on Nuclear Safeguards, Nonproliferation and Peaceful Nuclear Energy Infrastructure September 22, 2010 VIENNA, AUSTRIA -The National Nuclear Security Administration (NNSA) today announced that it has signed a Memorandum of Cooperation on nuclear safeguards and other nonproliferation topics with the Tunisia Ministry of Higher Education. NNSA Administrator Thomas D'Agostino

  12. Lessons from post-war Iraq for the international full-scope safeguards regime

    SciTech Connect (OSTI)

    Scheinman, L.

    1993-04-01

    The discovery after the Gulf War of the extensive Iraqi nuclear weapon program severely shook public confidence in the nuclear non-proliferation regime in general, and the safeguards program of the IAEA under the nuclear Non-Proliferation Treaty, in particular. Iraq provided the justification for evaluating the safeguards regime under new political circumstances, so that appropriate corrective measures could be taken when necessary. It is now up to the individual states within the international system to take advantage of this opportunity.

  13. 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

  14. 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,

  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. 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.

  18. 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.

  19. 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.

  20. 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

  1. Microdrill Initiative - Initial Market Evaluation

    SciTech Connect (OSTI)

    Spears & Associates, Inc

    2003-07-01

    The U.S. Department of Energy (DOE) is launching a major research and development initiative to create a small, fast, inexpensive and environmentally friendly rig for drilling 5000 feet boreholes to investigate potential oil and gas reservoirs. DOE wishes to get input from petroleum industry operators, service companies and equipment suppliers on the operation and application of this coiled-tubing-based drilling unit. To that end, DOE has asked Spears & Associates, Inc. (SAI) to prepare a special state-of-the-market report and assist during a DOE-sponsored project-scoping workshop in Albuquerque near the end of April 2003. The scope of the project is four-fold: (1) Evaluate the history, status and future of demand for very small bore-hole drilling; (2) Measure the market for coiled tubing drilling and describe the state-of-the-art; (3) Identify companies and individuals who should have an interest in micro drilling and invite them to the DOE workshop; and (4) Participate in 3 concurrent workshop sessions, record and evaluate participant comments and report workshop conclusions.

  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

  3. 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

  4. Initial CTBT international monitoring system security findings and recommendations

    SciTech Connect (OSTI)

    Craft, R.L.; Draelos, T.J.

    1996-08-01

    An initial security evaluation of the proposed International Monitoring System (IMS) suggests safeguards at various points in the IMS to provide reliable information to the user community. Modeling the IMS as a network of information processing nodes provides a suitable architecture for assessing data surety needs of the system. The recommendations in this paper include the use of public-key authentication for data from monitoring stations and for commands issued to monitoring stations. Other monitoring station safeguards include tamper protection of sensor subsystems, preservation of data (i.e. short-term archival), and limiting the station`s network services. The recommendations for NDCs focus on the need to provide a backup to the IDC for data archival and data routing. Safeguards suggested for the IDC center on issues of reliability. The production of event bulletins should employ {open_quotes}two-man{close_quotes} procedures. As long as the data maintains its integrity, event bulletins can be produced by NDCs as well. The effective use of data authentication requires a sound key management system. Key management systems must be developed for the authentication of data, commands, and event bulletins if necessary. It is recommended that the trust placed in key management be distributed among multiple parties. The recommendations found in this paper offer safeguards for identified vulnerabilities in the IMS with regard to data surety. However, several outstanding security issues still exist. These issues include the need to formalize and obtain a consensus on a threat model and a trust model for the IMS. The final outstanding security issue that requires in-depth analysis concerns the IDC as a potential single point of failure in the current IMS design.

  5. Determining Spent Nuclear Fuel's Plutonium Content, Initial Enrichment, Burnup, and Cooling Time

    SciTech Connect (OSTI)

    Cheatham, Jesse R; Francis, Matthew W

    2011-01-01

    The Next Generation of Safeguards Initiative is examining nondestructive assay techniques to determine the total plutonium content in spent nuclear fuel. The goal of this research was to develop new techniques that can independently verify the plutonium content in a spent fuel assembly without relying on an operator's declarations. Fundamentally this analysis sought to answer the following questions: (1) do spent fuel assemblies contain unique, identifiable isotopic characteristics as a function of their burnup, cooling time, and initial enrichment; (2) how much variation can be seen in spent fuel isotopics from similar and dissimilar reactor power operations; and (3) what isotopes (if any) could be used to determine burnup, cooling time, and initial enrichment? To answer these questions, 96,000 ORIGEN cases were run that simulated typical two-cycle operations with burnups ranging from 21,900 to 72,000 MWd/MTU, cooling times from 5 to 25 years, and initial enrichments between 3.5 and 5.0 weight percent. A relative error coefficient was determined to show how numerically close a reference solution has to be to another solution for the two results to be indistinguishable. By looking at the indistinguishable solutions, it can be shown how a precise measurement of spent fuel isotopics can be inconclusive when used in the absence of an operator's declarations. Using this Method of Indistinguishable Solutions (MIS), we evaluated a prominent method of nondestructive analysis - gamma spectroscopy. From this analysis, a new approach is proposed that demonstrates great independent forensic examination potential for spent nuclear fuel by examining both the neutron emissions of Cm-244 and the gamma emissions of Cs-134 and Eu-154.

  6. Research Initiative Will Demonstrate Low Temperature Geothermal...

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

    Research Initiative Will Demonstrate Low Temperature Geothermal Electrical Power Generation Systems ... with the Office of Fossil Energy (FE) to demonstrate the ...

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. Inspection of the safeguards, security, and safety of special nuclear materials

    SciTech Connect (OSTI)

    Not Available

    1980-05-29

    The Department of Energy's responsibilities for improving the procedures for the safety and security of special nuclear materials, principally uranium and plutonium, are discussed. Findings focus on the functions performed by the Office of Safeguards and Security of the Office of the Assistant Secretary for Defense Programs, and the Operational and Environmental Safety Division of the Office of the Assistant Secretary for Environment. Recommendations range from modifying budget formats with the Office of the Controller so that they reflect total expenditures for safeguarding special nuclear materials to reducing the risk of internal theft or diversion of nuclear materials. We also recommend that policy statements, annual and semi-annual reports, and design guidelines relating to the entire program of security and safety of special nuclear materials be completed as soon as possible. In addition, continuous effort is needed to ensure the autonomy of safeguards offices within field offices.

  15. Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the US Department of Energy. Quarter ending June 30, 1996

    SciTech Connect (OSTI)

    Davis, B.; Davis, G.; Johnson, D; Mansur, D.L.; Ruhter, W.D.; Strait, R.S.

    1996-07-01

    LLNL carries out safeguards and security activities for DOE Office of Safeguards and Security (OSS) and other organizations, both within and outside DOE. This document summarizes activities conducted for OSS during this quarter. LLNL is supporting OSS in six areas: safeguards technology, safeguards and materials accountability, computer security/distributed system, complex-wide access control, standardization of security systems, and information technology & security center. This document describes the activities in each of these six areas.

  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 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.

  18. Report on the NGS3 Working Group on Safeguards by Design For Aqueous Reprocessing Plants

    SciTech Connect (OSTI)

    Johnson, Shirley J.; Ehinger, Michael; Schanfein, Mark

    2011-02-01

    The objective of the Working Group on SBD for Aqueous Reprocessing Facilities was to provide recommendations, for facility operators and designers, which would aid in the coordination and integration of nuclear material accountancy and the safeguards requirements of all concerned parties - operators, state/regional authorities, and the IAEA. The recommendations, which are to be provided to the IAEA, are intended to assist in optimizing facility design and operating parameters to ensure the safeguardability of the facility while minimizing impact on the operations. The one day Working Group session addressed a wide range of design and operating topics.

  19. 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.

  20. MIVS Mark V; The development of a computer assisted safeguards review station

    SciTech Connect (OSTI)

    Kadner, S. )

    1991-01-01

    This paper reports on the development and fielding of video recorder based surveillance systems, with associated high capacity scene storage capability, that have increased inspector visual review requirements. A clear need for decreasing inspector review participation while assuring no resulting degradation of technical and safeguards analyses has been demonstrated. A development utilizing a general purpose microcomputer based platform with video recorder control capabilities and analog to digital conversion of visual scene content is described. Such a system may be used to safeguard nuclear facilities.

  1. 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

  2. NGSS Professional Development Series | Argonne National Laboratory

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

    (NNSA) Nonproliferation and Arms Control / International Nuclear Safeguards NGSI Safeguards by Design NNSA's Next Generation Safeguards Initiative (NGSI) sponsors a project promoting international Safeguards by Design (SBD). The International Atomic Energy Agency (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,

  3. Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

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

    Favalli, Andrea; Vo, D.; Grogan, Brandon R.; Jansson, Peter; Liljenfeldt, Henrik; Mozin, Vladimir; Schwalbach, P.; Sjoland, A.; Tobin, Stephen J.; Trellue, Holly; et al

    2016-02-26

    The purpose of the Next Generation Safeguards Initiative (NGSI)–Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuelmore » assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute 137Cs count rate and the 154Eu/137Cs, 134Cs/137Cs, 106Ru/137Cs, and 144Ce/137Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity’s behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. Furthermore, the results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.« less

  4. Explosive laser light initiation of propellants

    DOE Patents [OSTI]

    Piltch, M.S.

    1993-05-18

    A improved initiator for artillery shell using an explosively generated laser light to uniformly initiate the propellent. A small quantity of a high explosive, when detonated, creates a high pressure and temperature, causing the surrounding noble gas to fluoresce. This fluorescence is directed into a lasing material, which lases, and directs laser light into a cavity in the propellant, uniformly initiating the propellant.

  5. Electric generator

    DOE Patents [OSTI]

    Foster, Jr., John S.; Wilson, James R.; McDonald, Jr., Charles A.

    1983-01-01

    1. In an electrical energy generator, the combination comprising a first elongated annular electrical current conductor having at least one bare surface extending longitudinally and facing radially inwards therein, a second elongated annular electrical current conductor disposed coaxially within said first conductor and having an outer bare surface area extending longitudinally and facing said bare surface of said first conductor, the contiguous coaxial areas of said first and second conductors defining an inductive element, means for applying an electrical current to at least one of said conductors for generating a magnetic field encompassing said inductive element, and explosive charge means disposed concentrically with respect to said conductors including at least the area of said inductive element, said explosive charge means including means disposed to initiate an explosive wave front in said explosive advancing longitudinally along said inductive element, said wave front being effective to progressively deform at least one of said conductors to bring said bare surfaces thereof into electrically conductive contact to progressively reduce the inductance of the inductive element defined by said conductors and transferring explosive energy to said magnetic field effective to generate an electrical potential between undeformed portions of said conductors ahead of said explosive wave front.

  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. 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.

  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. 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.

  10. 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.

  11. 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

  12. Proof of Concept Simulations of the Multi-Isotope Process Monitor: An Online, Nondestructive, Near-Real-Time Safeguards Monitor for Nuclear Fuel Reprocessing Facilities

    SciTech Connect (OSTI)

    Orton, Christopher R.; Fraga, Carlos G.; Christensen, Richard; Schwantes, Jon M.

    2011-02-11

    The International Atomic Energy Agency (IAEA) will require the development of advanced technologies to effectively safeguard nuclear material at increasingly large-scale nuclear recycling facilities. Ideally, the envisioned technologies would be capable of nondestructive, near-real-time, autonomous process monitoring. This paper describes recent results from model simulations designed to test the Multi-Isotope Process (MIP) monitor, a novel approach to safeguarding reprocessing plants. The MIP monitor combines the detection of intrinsic gamma ray signatures emitted from process solutions with multivariate analysis to detect off-normal conditions in process streams nondestructively and in near-real-time. Three computer models including ORIGEN-ARP, AMUSE, and SYNTH were used in series to predict spent nuclear fuel composition, estimate element partitioning during separation, and simulate spectra from product and raffinate streams using a variety of gamma detectors, respectively. Simulations were generated for fuel with various irradiation histories and under a variety of plant operating conditions. Principal component analysis (PCA) was applied to the simulated gamma spectra to investigate pattern variations as a function of acid concentration, burnup, and cooling time. Hierarchical cluster analysis (HCA) and partial least squares (PLS) were also used in the analysis. The MIP monitor was found to be sensitive to induced variations of several operating parameters including distinguishing ±2.5% variation from normal process acid concentrations. The ability of PLS to predict burnup levels from simulated spectra was also demonstrated to be within 3.5% of measured values.

  13. 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

  14. 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

  15. Boron-10 ABUNCL Prototype Initial Testing

    SciTech Connect (OSTI)

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

    2012-12-01

    The Department of Energy Office of Nuclear Safeguards and Security (NA-241) is supporting the project Coincidence Counting With Boron-Based Alternative Neutron Detection Technology at Pacific Northwest National Laboratory (PNNL) for the development of a 3He proportional counter alternative neutron coincidence counter. The goal of this project is to design, build and demonstrate a system based upon 10B-lined proportional tubes in a configuration typical for 3He-based coincidence counter applications. This report provides results of initial testing of an Alternative Boron-Based Uranium Neutron Coincidence Collar (ABUNCL) design built by General Electric Reuter-Stokes. Several configurations of the ABUNCL models, which use 10B-lined proportional counters in place of 3He proportional counters for the neutron detection elements, were previously reported. The ABUNCL tested is of a different design than previously modeled. Initial experimental testing of the as-delivered passive ABUNCL was performed, and modeling will be conducted. Testing of the system reconfigured for active testing will be performed in the near future, followed by testing with nuclear fuel.

  16. Feasibility Study of Economics and Performance of Biomass Power Generation at the Former Farmland Industries Site in Lawrence, Kansas. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites

    SciTech Connect (OSTI)

    Tomberlin, G.; Mosey, G.

    2013-03-01

    Under the RE-Powering America's Land initiative, the U.S. Environmental Protection Agency (EPA) provided funding to the National Renewable Energy Laboratory (NREL) to support a feasibility study of biomass renewable energy generation at the former Farmland Industries site in Lawrence, Kansas. Feasibility assessment team members conducted a site assessment to gather information integral to this feasibility study. Information such as biomass resources, transmission availability, on-site uses for heat and power, community acceptance, and ground conditions were considered.

  17. The President's Manufacturing Initiative

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

    The President's Manufacturing Initiative Manufacturing Initiative Roadmap Workshop on Roadmap Workshop on Manufacturing R&D for Manufacturing R&D for the Hydrogen Economy the ...

  18. Boron-10 ABUNCL Prototype Models And Initial Active Testing

    SciTech Connect (OSTI)

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

    2013-04-23

    The Department of Energy Office of Nuclear Safeguards and Security (NA-241) is supporting the project Coincidence Counting With Boron-Based Alternative Neutron Detection Technology at Pacific Northwest National Laboratory (PNNL) for the development of a 3He proportional counter alternative neutron coincidence counter. The goal of this project is to design, build and demonstrate a system based upon 10B-lined proportional tubes in a configuration typical for 3He-based coincidence counter applications. This report provides results from MCNPX model simulations and initial testing of the active mode variation of the Alternative Boron-Based Uranium Neutron Coincidence Collar (ABUNCL) design built by General Electric Reuter-Stokes. Initial experimental testing of the as-delivered passive ABUNCL was previously reported.

  19. 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

  20. WCI - World Consensus Initiative

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

    World Consensus Initiative 2005 Workshop Recap WCI 2004 Website WCI Book Contributed Papers

  1. DOE Exascale Initiative | Department of Energy

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

    Exascale Initiative (pdf) (1.27 MB) More Documents & Publications Report of the Task Force on Next Generation High Performance Computing Class Patent Waiver W(C)2012-003 Volume 4

  2. 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.

  3. 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.

  4. Evaluating safeguards effectiveness against protracted theft of special nuclear material by insiders

    SciTech Connect (OSTI)

    Al-Ayat, R.A.; Sicherman, A. )

    1991-01-01

    The new draft DOE Material Control and Accountability Order 5633.3 requires that facilities handling special nuclear material (SNM) evaluate their effectiveness against protracted theft of SNM. Protracted theft means repeated thefts of small quantities of material to accumulate a goal quantity. In this paper the authors discuss issues regarding the evaluation of safeguards and describe how we are augmenting the Analytic System and Software for Evaluating Safeguards and Security (ASSESS) to provide the user with a tool for evaluating effectiveness against protracted theft. Currently, the Insider module of ASSESS focuses on evaluating the timely detection of abrupt theft attempts by various types of single nonviolent insiders. In this paper we describe the approach we're implementing to augment ASSESS to handle various cases of protracted theft attempts.

  5. 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 designers 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.

  6. 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 designers 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.

  7. Direct Measurement of Initial Enrichment and Burn-up of Spent Fuel Assembly with a Differential Die-Away Technique Based Instrument

    SciTech Connect (OSTI)

    Henzl, Vladimir; Swinhoe, Martyn T.; Tobin, Stephen J.

    2012-07-16

    A key objective of the Next Generation Safeguards Initiative (NGSI) is to utilize non-destructive assay (NDA) techniques to determine the elemental plutonium (Pu) content in a commercial-grade nuclear spent fuel assembly (SFA). In the third year of the NGSI Spent Fuel NDA project, the research focus is on the integration of a few NDA techniques. One of the reoccurring challenges to the accurate determination of Pu content has been the explicit dependence of the measured signal on the presence of neutron absorbers which build up in the assembly in accordance with its operating and irradiation history. The history of any SFA is often summarized by the parameters of burn-up (BU), initial enrichment (IE) and cooling time (CT). While such parameters can typically be provided by the operator, the ability to directly measure and verify them would significantly enhance the autonomy of the IAEA inspectorate. Within this paper, we demonstrate that an instrument based on a Differential Die-Away technique is in principle capable of direct measurement of IE and, should the CT be known, also the BU.

  8. 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

  9. Safeguarding Nuclear Fuel Processing | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Safeguarding Nuclear Fuel Processing Laboratory Policy (LP) LP Home About Laboratory Appraisal Process Laboratory Planning Process Laboratory Directed Research and Development (LDRD) Frequently Asked Questions Impact Legislative History Program Contacts Management & Operating (M&O) Contracts Technology Transfer Strategic Partnership Projects (SPP) Contact Information Laboratory Policy U.S. Department of Energy SC-32/Forrestal Building 1000 Independence Ave., SW Washington, DC 20585 P:

  10. 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

  11. 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.

  12. 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.

  13. 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.

  14. Opportunities to more fully utilize safeguards information reported to the IAEA at Gas Centrifuge Enrichment Plants

    SciTech Connect (OSTI)

    Garner, James R; Whitaker, J Michael

    2015-01-01

    In an effort to increase transparency and to strengthen IAEA safeguards, more countries are adopting practices that provide the IAEA with more timely, safeguards-relevant information to confirm nuclear operations are as declared. At Gas Centrifuge Enrichment Plants (GCEPs) potential examples include installing unattended IAEA instruments that transmit selected information back to Vienna, instruments that collect and store measurement information on-site, and daily facility operator submissions of material receipts, shipments, or utilization of key operational systems (e.g., UF6 feed stations) to on-site mail boxes. Recently the IAEA has implemented the use of on-site mailbox systems supplemented with short notice or unannounced inspections to maintain effectiveness without significantly increasing the number of inspection days. While these measures significantly improves the IAEA’s effectiveness, we have identified several opportunities for how the use of this information could be improved and how some additional information would further improve safeguards. This paper presents concepts for how the safeguards information currently collected at GCEPs could be more effectively utilized through enhancing the way that raw data is displayed visually so that it is more intuitive to the inspector and provides for more effective inspection planning and execution, comparing information with previous IAEA inspection activities (lists of previous verified inventory), through comparing data with operator supplied data when inspectors arrive (notional inventory change reports), and through evaluating the data over time to provide even greater confidence in the data and operations as declared in between inspections. This paper will also discuss several potential improvements to the submissions themselves, such as including occupancy information about product and tails stations and including weight information for each station.

  15. 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

  16. 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.

  17. NEGATIVE GATE GENERATOR

    DOE Patents [OSTI]

    Jones, C.S.; Eaton, T.E.

    1958-02-01

    This patent relates to pulse generating circuits and more particularly to rectangular pulse generators. The pulse generator of the present invention incorporates thyratrons as switching elements to discharge a first capacitor through a load resistor to initiate and provide the body of a Pulse, and subsequently dlscharge a second capacitor to impress the potential of its charge, with opposite potential polarity across the load resistor to terminate the pulse. Accurate rectangular pulses in the millimicrosecond range are produced across a low impedance by this generator.

  18. 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.

  19. 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.

  20. 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.

  1. INTERNATIONAL ATOMIC ENERGY AGENCY (IAEA) SAFEGUARDS DURING STABILIZATION AT HANFORD PLUTONIUM FINISHING PLANT (PFP)

    SciTech Connect (OSTI)

    MCRAE, L.P.

    2004-06-30

    The Vault at the Plutonium Finishing Plan (PFP) became subject to the International Atomic Energy Agency (IAEA) safeguards beginning in 1994 as part of the US excess fissile material program. The inventory needed to be stabilized and repackaged for long-term storage to comply with Defense Nuclear Facility Safety Board Recommendation 94-1. In 1998, the United States began negotiations with IAEA to develop methods to maintain safeguards during stabilization and repackaging of this material. The Design Information Questionnaire was revised and submitted to the IAEA in 2002 describing modification to the facility to accommodate the stabilization process line. The operation plan for 2003 was submitted describing the proposed schedules for removing materials for stabilization. Stabilization and repackaging activities for the safeguarded plutonium began in January 2003 and were completed in December 2003. The stabilization was completed in five phases. IAEA containment and surveillance measures were maintained until the material was removed by phase for stabilization and repackaging. Following placement of the repackaged material into the storage vault, the IAEA conducted inventory change verification measurements, and re-established containment and surveillance. Plant activities and the impacts on operations are described.

  2. 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

  3. Nanostructure-initiator mass spectrometry biometrics

    DOE Patents [OSTI]

    Leclerc, Marion; Bowen, Benjamin; Northen, Trent

    2015-09-08

    Several embodiments described herein are drawn to methods of identifying an analyte on a subject's skin, methods of generating a fingerprint, methods of determining a physiological change in a subject, methods of diagnosing health status of a subject, and assay systems for detecting an analyte and generating a fingerprint, by nanostructure-initiator mass spectrometry (NIMS).

  4. 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

  5. Advances in passive neutron instruments for safeguards use

    SciTech Connect (OSTI)

    Menlove, H.O.; Krick, M.S.; Langner, D.G.; Miller, M.C.; Stewart, J.E.

    1994-02-01

    Passive neutron and other nondestructive assay techniques have been used extensively by the International Atomic Energy Agency to verify plutonium metal, powder, mixed oxide, pellets, rods, assemblies, scrap, and liquids. Normally, the coincidence counting rate is used to measure the {sup 240}Pu-effective mass and gamma-ray spectrometry or mass spectrometry is used to verify the plutonium isotopic ratios. During the past few years, the passive neutron detectors have been installed in plants and operated in the unattended/continuous mode. These radiation data with time continuity have made it possible to use the totals counting rate to monitor the movement of nuclear material. Monte Carlo computer codes have been used to optimize the detector designs for specific applications. The inventory sample counter (INVS-III) has been designed to have a higher efficiency (43%) and a larger uniform counting volume than the original INVS. Data analyses techniques have been developed, including the ``known alpha`` and ``known multiplication`` methods that depend on the sample. For scrap and other impure or poorly characterized samples, we have developed multiplicity counting, initially implemented in the plutonium scrap multiplicity counter. For large waste containers such as 200-L drums, we have developed the add-a-source technique to give accurate corrections for the waste-matrix materials. This paper summarizes recent developments in the design and application of passive neutron assay systems.

  6. Keck Futures Initiative

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

    National Academies Keck Futures Initiative Complex Systems Conference, November 12 - 15, 2008 Challa Kumar(second from left) was invited to attend 1st National Academies Keck Futures Initiative Complex Systems Conference

  7. Scram signal generator

    DOE Patents [OSTI]

    Johanson, Edward W.; Simms, Richard

    1981-01-01

    A scram signal generating circuit for nuclear reactor installations monitors a flow signal representing the flow rate of the liquid sodium coolant which is circulated through the reactor, and initiates reactor shutdown for a rapid variation in the flow signal, indicative of fuel motion. The scram signal generating circuit includes a long-term drift compensation circuit which processes the flow signal and generates an output signal representing the flow rate of the coolant. The output signal remains substantially unchanged for small variations in the flow signal, attributable to long term drift in the flow rate, but a rapid change in the flow signal, indicative of a fast flow variation, causes a corresponding change in the output signal. A comparator circuit compares the output signal with a reference signal, representing a given percentage of the steady state flow rate of the coolant, and generates a scram signal to initiate reactor shutdown when the output signal equals the reference signal.

  8. Scram signal generator

    DOE Patents [OSTI]

    Johanson, E.W.; Simms, R.

    A scram signal generating circuit for nuclear reactor installations monitors a flow signal representing the flow rate of the liquid sodium coolant which is circulated through the reactor, and initiates reactor shutdown for a rapid variation in the flow signal, indicative of fuel motion. The scram signal generating circuit includes a long-term drift compensation circuit which processes the flow signal and generates an output signal representing the flow rate of the coolant. The output signal remains substantially unchanged for small variations in the flow signal, attributable to long term drift in the flow rate, but a rapid change in the flow signal, indicative of a fast flow variation, causes a corresponding change in the output signal. A comparator circuit compares the output signal with a reference signal, representing a given percentage of the steady state flow rate of the coolant, and generates a scram signal to initiate reactor shutdown when the output signal equals the reference signal.

  9. Ohio Fuel Cell Initiative

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

    Top 5 Fuel Cell States: Why Local Policies Mean Green Growth Jun 21 st , 2011 2 * Ohio Fuel Cell Initiative * Ohio Fuel Cell Coalition * Accomplishments * Ohio Successes Discussion Areas 3 Ohio's Fuel Cell Initiative * Announced on 5/9/02 * Part of Ohio Third Frontier Initiative * $85 million investment to date * Core focus areas: 1) Expand the state's research capabilities; 2) Participate in demonstration projects; and 3) Expand the fuel cell industry in Ohio 4 OHIO'S FUEL CELL INITIATIVE

  10. DOE TEAM Initiative

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

    Presented by: Geoffrey C. Bell, PE Geoffrey C. Bell, PE High Tech Buildings High Tech Buildings ~ ~ Berkeley Fume Hood Berkeley Fume Hood ~ ~ Aerosol Duct Sealing Aerosol Duct Sealing DOE TEAM Initiative DOE TEAM Initiative Facilities and Environmental Energy Technologies Facilities and Environmental Energy Technologies 1 Facilities and Environmental Energy Technologies Facilities and Environmental Energy Technologies 2 DOE TEAM Initiative DOE TEAM Initiative High Tech Buildings High Tech

  11. Wind Integration Initiatives

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

    Expand Projects & Initiatives Finance & Rates Expand Finance & Rates Involvement & Outreach Expand Involvement & Outreach Doing Business Expand Doing Business...

  12. APEC Smart Grid Initiative

    SciTech Connect (OSTI)

    Bloyd, Cary N.

    2012-03-01

    This brief paper describes the activities of the Asia Pacific Economic Cooperation (APEC) Smart Grid Initiative (ASGI) which is being led by the U.S. and developed by the APEC Energy Working Group. In the paper, I describe the origin of the initiative and briefly mention the four major elements of the initiative along with existing APEC projects which support it.

  13. Compact Mesh Generator

    Energy Science and Technology Software Center (OSTI)

    2007-02-02

    The CMG is a small, lightweight, structured mesh generation code. It features a simple text input parser that allows setup of various meshes via a small set of text commands. Mesh generation data can be output to text, the silo file format, or the API can be directly queried by applications. It can run serially or in parallel via MPI. The CMG includes the ability to specify varius initial conditions on a mesh via meshmore » tags.« less

  14. Feasibility Study of Economics and Performance of Geothermal Power Generation at the Lakeview Uranium Mill Site in Lakeview, Oregon. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites

    SciTech Connect (OSTI)

    Hillesheim, M.; Mosey, G.

    2013-11-01

    The U.S. Environmental Protection Agency (EPA), in accordance with the RE-Powering America's Land initiative, selected the Lakeview Uranium Mill site in Lakeview, Oregon, for a feasibility study of renewable energy production. The EPA contracted with the National Renewable Energy Laboratory (NREL) to provide technical assistance for the project. The purpose of this report is to describe an assessment of the site for possible development of a geothermal power generation facility and to estimate the cost, performance, and site impacts for the facility. In addition, the report recommends development pathways that could assist in the implementation of a geothermal power system at the site.

  15. N-1: Safeguards Science and Technology Group, Tour Areas

    SciTech Connect (OSTI)

    Geist, William H.

    2012-05-09

    Group N-1 develops and provides training on nondestructive assay (NDA) technologies intended for nuclear material accounting and control to fulfill both international and domestic obligations. The N-1 group is located at Technical Area (TA)-35 in Buildings 2 and 27. Visitors to the area can observe developed and fielded NDA technologies, as well as the latest research efforts to develop the next generation of NDA technologies. Several areas are used for NDA training. The N-1 School House area typically is used for basic training on neutron- and gamma-ray-based NDA techniques. This area contains an assortment of gamma-ray detector systems, including sodium iodide and high-purity germanium and the associated measurement components. Many types of neutron assay systems are located here, including both standard coincidence and multiplicity counters. The N-1 School House area is also used for holdup training; located here are the mock holdup assemblies and associated holdup measurement tools. Other laboratory areas in the N-1 space are used for specialized training, such as waste NDA, calorimetry, and advanced gamma-ray NDA. Also, many research laboratories in the N-1 space are used to develop new NDA technologies. The calorimetry laboratory is used to develop and evaluate new technologies and techniques that measure the heat signature from nuclear material to determine mass. The micro calorimetry laboratory is being used to develop advanced technologies that can measure gamma rays with extremely high resolution. This technique has been proven in the laboratory setting, and the team is now working to cultivate a field-capable system. The N-1 group also develops remote and unattended systems for the tracking and control of nuclear material. A demonstration of this technology is located within one of the laboratory spaces. The source tracker software was developed by N-1 to monitor the locations and quantities of nuclear materials. This software is currently used to track

  16. Initial Radionuclide Inventories

    SciTech Connect (OSTI)

    H. Miller

    2004-09-19

    The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement, currently identified as

  17. Initial Radionuclide Inventories

    SciTech Connect (OSTI)

    Miller, H

    2005-07-12

    The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement, currently identified as

  18. 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)

  19. 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.

  20. 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

  1. Progress in Initiator Modeling

    SciTech Connect (OSTI)

    Hrousis, C A; Christensen, J S

    2009-05-04

    There is great interest in applying magnetohydrodynamic (MHD) simulation techniques to the designs of electrical high explosive (HE) initiators, for the purpose of better understanding a design's sensitivities, optimizing its performance, and/or predicting its useful lifetime. Two MHD-capable LLNL codes, CALE and ALE3D, are being used to simulate the process of ohmic heating, vaporization, and plasma formation in the bridge of an initiator, be it an exploding bridgewire (EBW), exploding bridgefoil (EBF) or slapper type initiator. The initiation of the HE is simulated using Tarver Ignition & Growth reactive flow models. 1-D, 2-D and 3-D models have been constructed and studied. The models provide some intuitive explanation of the initiation process and are useful for evaluating the potential impact of identified aging mechanisms (such as the growth of intermetallic compounds or powder sintering). The end product of this work is a simulation capability for evaluating margin in proposed, modified or aged initiation system designs.

  2. Initiatives | Department of Energy

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

    Initiatives Initiatives Through a variety of cross-cutting program initiatives, the Office of International Affairs (IA) responds to the most pressing global energy challenges, ranging from energy security and market volatility to long-term efforts to reduce carbon pollution and the impacts of climate change. IA has the primary responsibility for coordinating the efforts of diverse elements in the Department to ensure a unified voice in our international energy policy. This page highlights some

  3. 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.

  4. 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.

  5. 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.

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

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

    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

  7. 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

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

    SciTech Connect (OSTI)

    Ivan R. Thomas

    2010-07-01

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

  9. Supplemental Report on Nuclear Safeguards Considerations for the Pebble Bed Modular Reactor (PBMR)

    SciTech Connect (OSTI)

    Moses, David Lewis; Ehinger, Michael H

    2010-05-01

    Recent reports by Department of Energy National Laboratories have discussed safeguards considerations for the low enriched uranium (LEU) fueled Pebble Bed Modular Reactor (PBMR) and the need for bulk accountancy of the plutonium in used fuel. These reports fail to account effectively for the degree of plutonium dilution in the graphitized-carbon pebbles that is sufficient to meet the International Atomic Energy Agency's (IAEA's) 'provisional' guidelines for termination of safeguards on 'measured discards.' The thrust of this finding is not to terminate safeguards but to limit the need for specific accountancy of plutonium in stored used fuel. While the residual uranium in the used fuel may not be judged sufficiently diluted to meet the IAEA provisional guidelines for termination of safeguards, the estimated quantities of {sup 232}U and {sup 236}U in the used fuel at the target burn-up of {approx}91 GWD/MT exceed specification limits for reprocessed uranium (ASTM C787) and will require extensive blending with either natural uranium or uranium enrichment tails to dilute the {sup 236}U content to fall within specification thus making the PBMR used fuel less desirable for commercial reprocessing and reuse than that from light water reactors. Also the PBMR specific activity of reprocessed uranium isotopic mixture and its A{sub 2} values for effective dose limit if released in a dispersible form during a transportation accident are more limiting than the equivalent values for light water reactor spent fuel at 55 GWD/MT without accounting for the presence of the principal carry-over fission product ({sup 99}Tc) and any possible plutonium contamination that may be present from attempted covert reprocessing. Thus, the potentially recoverable uranium from PBMR used fuel carries reactivity penalties and radiological penalties likely greater than those for reprocessed uranium from light water reactors. These factors impact the economics of reprocessing, but a more significant

  10. TVA- Solar Solutions Initiative

    Broader source: Energy.gov [DOE]

    Solar Solutions Initiative (SSI) is a pilot program that offers additional financial incentives for Solar PV systems participating in the Renewable Standard Offer program. Applications for new...

  11. About the Initiative

    SciTech Connect (OSTI)

    Not Available

    2007-06-01

    This factsheet gives an overview of the Solar America Initiative (SAI), including goals, research and development strategy, market transformation strategy, and benefits to nation.

  12. Salt Waste Processing Initiatives

    Office of Environmental Management (EM)

    Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 ...

  13. National Laboratory Impact Initiative

    Broader source: Energy.gov [DOE]

    The National Laboratory Impact Initiative supports the relationship between the Office of Energy Efficiency & Renewable Energy and the national laboratory enterprise.  The national laboratories...

  14. Near Real-Time Nondestructive Active Inspection Technologies Utilizing Delayed γ-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 γ-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 γ-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 γ-ray spectroscopy for fissionable material assay.

  15. National Nanotechnology Initiative

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

    National Nanotechnology Initiative (NNI) Basic Energy Sciences (BES) BES Home About Research Materials Sciences & Engineering (MSE) Chemical Sciences, Geosciences, and Biosciences (CSGB) Accelerator and Detector Research Research Conduct Policies DOE Energy Innovation Hubs Energy Frontier Research Centers National Nanotechnology Initiative (NNI) Nanomaterials ES&H Facilities Science Highlights Benefits of BES Funding Opportunities Basic Energy Sciences Advisory Committee (BESAC)

  16. Initiatives | Argonne National Laboratory

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

    ATLAS Support Center Center for Computational Excellence Coordinating Panel for Advanced Detectors Publications News & Events Upcoming Events Press Releases Feature Stories In the News Videos Downloads About HEP at Work Career Opportunities Staff Directory About HEP at Work Career Opportunities Staff Directory Argonne National Laboratory High Energy Physics Research Facilities Capabilities Initiatives Publications News & Events Initiatives ATLAS Support Center Center for Computational

  17. Generation Planning (pbl/generation)

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

    Generation Hydro Power Wind Power Monthly GSP BPA White Book Dry Year Tools Firstgov Generation Planning Thumbnail image of BPA White Book BPA White Book (1998-2014) Draft Dry...

  18. 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

  19. 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.

  20. 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.

  1. 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.

  2. Breckinridge Project, initial effort

    SciTech Connect (OSTI)

    1982-01-01

    The project cogeneration plant supplies electric power, process steam and treated boiler feedwater for use by the project plants. The plant consists of multiple turbine generators and steam generators connected to a common main steam header. The major plant systems which are required to produce steam, electrical power and treated feedwater are discussed individually. The systems are: steam, steam generator, steam generator fuel, condensate and feedwater deaeration, condensate and blowdown collection, cooling water, boiler feedwater treatment, coal handling, ash handling (fly ash and bottom ash), electrical, and control system. The plant description is based on the Phase Zero design basis established for Plant 31 in July of 1980 and the steam/condensate balance as presented on Drawing 31-E-B-1. Updating of steam requirements as more refined process information becomes available has generated some changes in the steam balance. Boiler operation with these updated requirements is reflected on Drawing 31-D-B-1A. The major impact of updating has been that less 600 psig steam generated within the process units requires more extraction steam from the turbine generators to close the 600 psig steam balance. Since the 900 psig steam generation from the boilers was fixed at 1,200,000 lb/hr, the additional extraction steam required to close the 600 psig steam balance decreased the quantity of electrical power available from the turbine generators. In the next phase of engineering work, the production of 600 psig steam will be augmented by increasing convection bank steam generation in the Plant 3 fired heaters by 140,000 to 150,000 lb/hr. This modification will allow full rated power generation from the turbine generators.

  3. MARTINI event generator for heavy quarks: Initialization, parton...

    Office of Scientific and Technical Information (OSTI)

    Publication Date: 2012-09-10 OSTI Identifier: 1103304 Type: Publisher's Accepted Manuscript Journal Name: Physical Review C Additional Journal Information: Journal Volume: 86; ...

  4. 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

  5. Network support for system initiated checkpoints

    DOE Patents [OSTI]

    Chen, Dong; Heidelberger, Philip

    2013-01-29

    A system, method and computer program product for supporting system initiated checkpoints in parallel computing systems. The system and method generates selective control signals to perform checkpointing of system related data in presence of messaging activity associated with a user application running at the node. The checkpointing is initiated by the system such that checkpoint data of a plurality of network nodes may be obtained even in the presence of user applications running on highly parallel computers that include ongoing user messaging activity.

  6. Distributed Generation

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

    Untapped Value of Backup Generation While new guidelines and regulations such as IEEE (Institute of Electrical and Electronics Engineers) 1547 have come a long way in addressing interconnection standards for distributed generation, utilities have largely overlooked the untapped potential of these resources. Under certain conditions, these units (primarily backup generators) represent a significant source of power that can deliver utility services at lower costs than traditional centralized

  7. Distributed Generation

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

    and regulations such as IEEE (Institute of Electrical and Electronics Engineers) 1547 have come a long way in addressing interconnection standards for distributed generation, ...

  8. 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...

  9. Generation Inputs Workshop June 25, 2014

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

    Inputs Workshop 25 June 2014 BPA's Centralized Wind Power Forecasting Initiative Scott Winner June 25, 2014 Generation Inputs Workshop Predecisional. For Discussion Purposes Only....

  10. Proliferation resistance: issues, initiatives and evaluation

    SciTech Connect (OSTI)

    Pilat, Joseph F

    2009-01-01

    The vision of a nuclear renaissance has highlighted the issue of proliferation resistance. The prospects for a dramatic growth in nuclear power may depend on the effectiveness of, and the resources devoted to, plans to develop and implement technologies and approaches that strengthen proliferation resistance. The GenIV International Forum (GIF) and others have devoted attention and resources to proliferation resistance. However, the hope of finding a way to make the peaceful uses of nuclear energy resistant to proliferation has reappeared again and again in the history of nuclear power with little practical consequence. The concept of proliferation resistance has usually focused on intrinsic (technological) as opposed to extrinsic (institutional) factors. However, if there are benefits that may yet be realized from reactors and other facilities designed to minimize proliferation risks, it is their coupling with effective safeguards and other nonproliferation measures that likely will be critical. Proliferation resistance has also traditionally been applied only to state threats. Although there are no technologies that can wholly eliminate the risk of proliferation by a determined state, technology can play a limited role in reducing state threats and perhaps in eliminating many non-state threats. These and other issues are not academic. They affect efforts to evaluate proliferation resistance, including the methodology developed by GIF's Proliferation Resistance and Physical Protection (PR&PP) Working Group as well as the proliferation resistance initiatives that are being pursued or may be developed in the future. This paper will offer a new framework for thinking about proliferation resistance issues, including the ways the output of the methodology could be developed to inform the decisions that states, the International Atomic Energy (IAEA) and others will have to make in order to fully realize the promise of a nuclear renaissance.

  11. Green Button Initiative Growing

    Broader source: Energy.gov [DOE]

    The Green Button initiative, which is the common-sense idea that electricity customers should be able to securely download their own energy usage information from their utility websites, is continuing to gain traction across the country.

  12. Strategic Initiatives Work Group

    Broader source: Energy.gov [DOE]

    The Work Group, comprised of members representing DOE, contractor and worker representatives, provides a forum for information sharing; data collection and analysis; as well as, identifying best practices and initiatives to enhance safety performance and safety culture across the Complex.

  13. Structured Innovation Initiative Workshop

    Broader source: Energy.gov [DOE]

    Following Water Power Week in Washington, D.C, the U.S. Department of Energy (DOE) will conduct a workshop on the Structured Innovation Initiative, similar to the workshop recently held in Edinburgh, Scotland during ICOE 2016.

  14. Initiatives | Department of Energy

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

    Initiatives Initiatives The Office of Energy Policy & Systems Analysis (EPSA) responds to the most pressing domestic energy challenges, delivering unbiased energy analysis to the Department of Energy's leadership on existing and prospective energy-related policies, focusing in part on integrative analysis of energy systems. EPSA also includes the Secretariat of the Quadrennial Energy Review, which has primary responsibility for supporting the White House interagency process and providing to

  15. 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

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

    SciTech Connect (OSTI)

    OCCHIOGROSSO, D.; PEPPER, S.

    2006-07-16

    The International Atomic Energy Agency (IAEA) relies on its member states to assist with recruiting qualified individuals for positions within the IAEA's secretariat. It is likewise important to the U.S. government for U.S. citizens to take positions with the IAEA to contribute to its success. It is important for persons within and outside the U.S. nuclear and safeguards industries to become aware of the job opportunities available at the IAEA and to be informed of important vacancies as they arise. The International Safeguards Project Office (ISPO) at Brookhaven National Laboratory (BNL) is tasked by the U.S. government with recruiting candidates for positions within the Department of Safeguards at the IAEA and since 1998, has been actively seeking methods for improving outreach. In addition, ISPO has been working more closely with the IAEA Division of Personnel. ISPO staff members attend trade shows to distribute information about IAEA opportunities. The shows target the nuclear industry as well as shows that are unrelated to the nuclear industry. ISPO developed a web site that provides information for prospective candidates. They have worked with the IAEA to understand its recruitment processes, to make suggestions for improvements, and to understand employment benefits so they can be communicated to potential U.S. applicants. ISPO is also collaborating with a State Department working group that is focused on increasing U.S. representation within the United Nations as a whole. Most recently Secretary of State Condoleezza Rice issued a letter to all Federal Agency heads encouraging details and transfers of their employees to international organizations to the maximum extent feasible and with due regard to their manpower requirements. She urged all federal agencies to review their detail and transfer policies and practices to ensure that employment in international organizations is promoted in a positive and active manner. In addition, she wrote that it is

  17. 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

  18. Carbon Capture Simulation Initiative

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

    Capture R&D Carbon Capture R&D DOE's Carbon Capture Program, administered by the Office of Fossil Energy and the National Energy Technology Laboratory, is conducting research and development activities on Second Generation and Transformational carbon capture technologies that have the potential to provide step-change reductions in both cost and energy penalty as compared to currently available First Generation technologies. The Carbon Capture Program consists of two core research

  19. Research Initiative Will Demonstrate Low Temperature Geothermal Electrical

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

    Power Generation Systems Using Oilfield Fluids | Department of Energy Research Initiative Will Demonstrate Low Temperature Geothermal Electrical Power Generation Systems Using Oilfield Fluids Research Initiative Will Demonstrate Low Temperature Geothermal Electrical Power Generation Systems Using Oilfield Fluids October 6, 2009 - 1:51pm Addthis The U.S. Department of Energy's (DOE) Geothermal Technologies Office (GTO) is announcing a new collaboration with the Office of Fossil Energy (FE) to

  20. 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.

  1. 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.

  2. Optical assay technology for safeguards. Quarterly report, October 1--December 31, 1991

    SciTech Connect (OSTI)

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

    1992-12-01

    Research conducted in the Ames Laboratory Nuclear Safeguards and Security Program during the period October 1, 1991 to December 31, 1991 is reviewed. Current work in applying optical spectroscopy to the determination of actinide and related elements in the gas phase is discussed. The major portion of this report is devoted to a description of a successful modification to a high-temperature heat pipe oven described in a previous report. High-resolution spectra of rare earth elements volatilized in this oven, measured using Doppler-free spectroscopy (i.e., saturated absorption spectroscopy) are presented along with a comparison of the spectrum of samarium measured with Doppler-free and ordinary techniques. Rare earth elements have strong spectral similarities to the actinide elements and it is clear from work that Doppler-free methods applied to the actinides will be very selective and capable of isotopic resolution.

  3. 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.

  4. 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.

  5. 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.

  6. Safeguards considerations related to the decontamination and decommissioning of former nuclear weapons facilities

    SciTech Connect (OSTI)

    Crawford, D.

    1995-12-31

    In response to the post-Cold War environment and the changes in the U. S. Department of Energy defense mission, many former nuclear operations are being permanently shut down. These operations include facilities where nuclear materials production, processing, and weapons manufacturing have occurred in support of the nation`s defense industry. Since defense-related operations have ceased, many of the classification and sensitive information concerns do not exist. However, nuclear materials found at these sites are of interest to the DOE from environmental, safety and health, and materials management perspectives. Since these facilities played a role in defense activities, the nuclear materials found at these facilities are considered special nuclear materials, primarily highly enriched uranium and/or plutonium. Consequently, these materials pose significant diversion, theft, and sabotage threats, and significant nuclear security issues exist that must be addressed. This paper focuses on the nuclear materials protection issues associated with facility decommissioning and decontamination, primarily safeguards.

  7. 2007 Initial Allocation Awards

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

    7 Awards 2007 Initial Allocation Awards The following table lists the initial allocation awards for NERSC for the 2007 allocation year (Jan 9, 2007 through Jan 7, 2008). The list is in alphabetical order by the last name of the Principal Investigator. Note - Letters following the repository name indicate the following: 'I' DOE ASCR INCITE award 'S' NERSC Startup award A B C D E F G H I J K L M N O P Q R S T U V W X Y Z Principal Site Request Repo SP HPSS Project Title Investigator Id Hours SRUs

  8. Clean Coal Power Initiative

    SciTech Connect (OSTI)

    Doug Bartlett; Rob James; John McDermott; Neel Parikh; Sanjay Patnaik; Camilla Podowski

    2006-03-31

    This report is the fifth quarterly Technical Progress Report submitted by NeuCo, Incorporated, under Award Identification Number, DE-FC26-04NT41768. This award is part of the Clean Coal Power Initiative (''CCPI''), the ten-year, $2B initiative to demonstrate new clean coal technologies in the field. This report is one of the required reports listed in Attachment B Federal Assistance Reporting Checklist, part of the Cooperative Agreement. The report covers the award period January 1, 2006 - March 31, 2006 and NeuCo's efforts within design, development, and deployment of on-line optimization systems during that period.

  9. RCRA facility stabilization initiative

    SciTech Connect (OSTI)

    Not Available

    1995-02-01

    The RCRA Facility Stabilization Initiative was developed as a means of implementing the Corrective Action Program`s management goals recommended by the RIS for stabilizing actual or imminent releases from solid waste management units that threaten human health and the environment. The overall goal of stabilization is to, as situations warrant, control or abate threats to human health and/or the environment from releases at RCRA facilities, and/or to prevent or minimize the further spread of contamination while long-term remedies are pursued. The Stabilization initiative is a management philosophy and should not be confused with stabilization technologies.

  10. 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

  11. National Lab Impact Initiative

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

    Lab Impact Initiative Energy Efficiency & Renewable Energy EERE National Lab Impact Summit Driving American Energy Innovation and Competitiveness May 4, 2016 | 7:30 am-7:00 pm National Renewable Energy Laboratory Golden, Colorado EERE National Lab Impact Summit // i ` http://www.cyclotronroad.org/home TABLE OF CONTENTS Department of Energy National Lab Abbreviations .........................................................................................................ii Welcome Letter

  12. Clean Energy Manufacturing Initiative

    SciTech Connect (OSTI)

    2013-04-01

    The initiative will strategically focus and rally EERE’s clean energy technology offices and Advanced Manufacturing Office around the urgent competitive opportunity for the United States to be the leader in the clean energy manufacturing industries and jobs of today and tomorrow.

  13. DOE Science Education Initiative Announced Today | Jefferson Lab

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

    Science Education Initiative Announced Today Huntington Middle School students confer during JLab's inaugural Virginia Regional Middle School Science Bowl. DOE Science Education Initiative Announced Today July 8, 2004 Today, U.S. Secretary of Energy Spencer Abraham announced that the U.S. Department of Energy (DOE) and its national laboratories are launching an initiative to promote science literacy and help develop the next generation of scientists and engineers. The initiative features a

  14. PULSE GENERATOR

    DOE Patents [OSTI]

    Roeschke, C.W.

    1957-09-24

    An improvement in pulse generators is described by which there are produced pulses of a duration from about 1 to 10 microseconds with a truly flat top and extremely rapid rise and fall. The pulses are produced by triggering from a separate input or by modifying the current to operate as a free-running pulse generator. In its broad aspect, the disclosed pulse generator comprises a first tube with an anode capacitor and grid circuit which controls the firing; a second tube series connected in the cathode circuit of the first tube such that discharge of the first tube places a voltage across it as the leading edge of the desired pulse; and an integrator circuit from the plate across the grid of the second tube to control the discharge time of the second tube, determining the pulse length.

  15. Microwave generator

    DOE Patents [OSTI]

    Kwan, T.J.T.; Snell, C.M.

    1987-03-31

    A microwave generator is provided for generating microwaves substantially from virtual cathode oscillation. Electrons are emitted from a cathode and accelerated to an anode which is spaced apart from the cathode. The anode has an annular slit there through effective to form the virtual cathode. The anode is at least one range thickness relative to electrons reflecting from the virtual cathode. A magnet is provided to produce an optimum magnetic field having the field strength effective to form an annular beam from the emitted electrons in substantial alignment with the annular anode slit. The magnetic field, however, does permit the reflected electrons to axially diverge from the annular beam. The reflected electrons are absorbed by the anode in returning to the real cathode, such that substantially no reflexing electrons occur. The resulting microwaves are produced with a single dominant mode and are substantially monochromatic relative to conventional virtual cathode microwave generators. 6 figs.

  16. Green Initiatives and Contracting

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

    GSA Is Now Training Contracting Officers In Green Purchasing Green Purchasing for the Federal Acquisition Work Force * introduction to the federal green purchasing program * assists learners with identifying green products * discusses factors that shape federal green purchasing initiatives https://cae.gsa.gov 2 "There's some challenges here" "Environmental Aisle" in the GSA Advantage electronic-purchasing website for federal buyers to find green products Environmental

  17. OSM's reforestation initiative

    SciTech Connect (OSTI)

    Boyce, J.S.

    1999-07-01

    Implementation of the Surface Mining Control and Reclamation Act (SMCRA) has discouraged reforestation in some situations where reforestation would be desirable. OSM is engaged in an initiative to increase the amount of mined land reclaimed to forest where appropriate. The authors are seeking to determine those elements of the Federal/State regulator programs that discourage reforestation and find ways to offset these impacts. Potential factors militating against reforestation are identified and possible solutions are discussed.

  18. Asset Revitalization Initiative ARI

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

    Asset Revitalization Initiative ( ARI ) Mission * Community * Reuse ARI is a DOE-wide effort to advance the beneficial reuse of the agency's unique and diverse mix of assets, including land, facilities, infrastructure, equipment, technologies, natural resources, and highly skilled workforce. ARI promotes an efficient business environment to encourage collaboration between public and private resources. ARI integrates DOE missions with community interests. ARI is... Our Vision By 2020: Operations

  19. Voluntary Initiative: Partnerships Toolkit

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

    Voluntary Initiative: Partnerships Toolkit BETTER BUILDINGS RESIDENTIAL NETWORK Residential energy efficiency programs are delivered by many different types of organizations and their partners, including utilities, state and local governments, non-profit organizations, and for-profit companies, but no matter which sector delivers the program, the need to work in partnership with different entities can make or break program success. Definition Partnerships are relationships between two or more

  20. 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.