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Sample records for generation safeguards initiative

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

    Energy Technology Data Exchange (ETDEWEB)

    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

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

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    Pepper,S.E.; Rosenthal, M.D.; Fishbone, L.G.; Occhogrosso, D.M.; Lockwood, D.; Carroll, C.J.; Dreicer, M.; Wallace, R.; Fankhauser, J.

    2009-07-12

    Brookhaven National Laboratory (BNL) hosted a Workshop on Enhanced Recruiting for International Safeguards October 22 and 23, 2008. The workshop was sponsored by DOE/NA-243 under the Next Generation Safeguards Initiative (NGSI). Placing well-qualified Americans in sufficient number and in key safeguards positions within the International Atomic Energy Agency’s (IAEA’s) Department of Safeguards is an important U.S. non-proliferation objective. The goal of the NGSI Workshop on Enhanced Recruiting for International Safeguards was to improve U.S. efforts to recruit U.S. citizens for IAEA positions in the Department of Safeguards. The participants considered the specific challenges of recruiting professional staff, safeguards inspectors, and managers. BNL’s International Safeguards Project Office invited participants from the U.S. Department of Energy, the IAEA, U.S. national laboratories, private industry, academia, and professional societies who are either experts in international safeguards or who understand the challenges of recruiting for technical positions. A final report for the workshop will be finalized and distributed in early 2009. The main finding of the workshop was the need for an integrated recruitment plan to take into account pools of potential candidates, various government and private agency stakeholders, the needs of the IAEA, and the NGSI human capital development plan. There were numerous findings related to and recommendations for maximizing the placement of U.S. experts in IAEA Safeguards positions. The workshop participants offered many ideas for increasing the pool of candidates and increasing the placement rate. This paper will provide details on these findings and recommendations

  3. Oak Ridge National Laboratory Next Generation Safeguards Initiative

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

    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

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

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    Pepper, Susan E. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    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.

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

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    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

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

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    Demuth, Scott F [Los Alamos National Laboratory; Budlong - Sylvester, Kory [Los Alamos National Laboratory; Lockwood, Dunbar [DOE/NA-243

    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.

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

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    Barefield Ii, James E [Los Alamos National Laboratory; Clegg, Samuel M [Los Alamos National Laboratory; Veirs, Douglas K [Los Alamos National Laboratory; Browne, Mike [Los Alamos National Laboratory; Lopez, Leon [Los Alamos National Laboratory; Martinez, Ron [Los Alamos National Laboratory; Le, Loan [Los Alamos National Laboratory; Lamontagne, Stephen A [DOE/NNSA/NA241; Veal, Kevin [NN/ADTR

    2009-01-01

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

  8. INL Human Resource Development and the Next-Generation Safeguards Initiative

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    Gouveia, Fernando; Metcalf, Richard Royce Madison

    2010-07-01

    It is the stated goal of the Next Generation Safeguards Initiative (NGSI) to promote the development of a strengthened nuclear safeguards base, one with the potential to advance the secure and peaceful implementation of nuclear energy world-wide. To meet this goal, the initiative, among other things, has sought to develop a revitalized effort to ensure the continued availability of next generation safeguards professionals. Accordingly, this paper serves to outline the human capital building strategies taken by Idaho National Laboratory (INL) in line with the NGSI. Various components are presented in detail, including INL’s efforts directed at university outreach, in particular the laboratory’s summer internship program, along with the development of various innovative training programs and long-term oriented strategies for student professional development. Special highlights include a video training series, developed by INL in cooperation with LLNL and other laboratories, which sought to expose students and entry-level professionals to the concept and practice of international nuclear safeguards.

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

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    Stevens, Rebecca S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hawkins Erpenbeck, Heather [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    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.

  10. Next Generation Safeguards Initiative: Overview and Policy Context of UF6 Cylinder Tracking Program

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    Boyer, Brian D [Los Alamos National Laboratory; Whitaker, J. Michael [ORNL; White-Horton, Jessica L. [ORNL; Durbin, Karyn R. [NNSA

    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.

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

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    Gilligan, Kimberly [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2014-01-01

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

  12. Safeguards First Principle Initiative (SFPI) Cost Model

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    Mary Alice Price

    2010-07-11

    The Nevada Test Site (NTS) began operating Material Control and Accountability (MC&A) under the Safeguards First Principle Initiative (SFPI), a risk-based and cost-effective program, in December 2006. The NTS SFPI Comprehensive Assessment of Safeguards Systems (COMPASS) Model is made up of specific elements (MC&A plan, graded safeguards, accounting systems, measurements, containment, surveillance, physical inventories, shipper/receiver differences, assessments/performance tests) and various sub-elements, which are each assigned effectiveness and contribution factors that when weighted and rated reflect the health of the MC&A program. The MC&A Cost Model, using an Excel workbook, calculates budget and/or actual costs using these same elements/sub-elements resulting in total costs and effectiveness costs per element/sub-element. These calculations allow management to identify how costs are distributed for each element/sub-element. The Cost Model, as part of the SFPI program review process, enables management to determine if spending is appropriate for each element/sub-element.

  13. Safeguards First Principles Initiative at the Nevada Test Site

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    Geneva Johnson

    2007-07-08

    The Material Control and Accountability (MC&A) program at the Nevada Test Site (NTS) was selected as a test bed for the Safeguards First Principles Initiative (SFPI). The implementation of the SFPI is evaluated using the system effectiveness model and the program is managed under an approved MC&A Plan. The effectiveness model consists of an evaluation of the critical elements necessary to detect, deter, and/or prevent the theft or diversion of Special Nuclear Material (SNM). The modeled results indicate that the MC&A program established under this variance is still effective, without creating unacceptable risk. Extensive performance testing is conducted through the duration of the pilot to ensure the protection system is effective and no material is at an unacceptable risk. The pilot was conducted from January 1, 2007, through May 30, 2007. This paper will discuss the following activities in association with SFPI: 1. Development of Timeline 2. Crosswalk of DOE Order and SFPI 3. Peer Review 4. Deviation 5. MC&A Plan and Procedure changes 6. Changes implemented at NTS 7. Training 8. Performance Test

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

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    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

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

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    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.

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

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    Durham, J. Matthew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Physics Division

    2016-11-17

    These are a set of slides for the development of a next-generation photon source white paper. The following topics are covered in these slides: Nuclear Safeguards; The Nuclear Fuel Cycle; Precise isotopic determination via NRF; UF6 Enrichment Assay; and Non-Destructive Assay of Spent Nuclear Fuel. In summary: A way to non-destructively measure precise isotopics of ~kg and larger samples has multiple uses in nuclear safeguards; Ideally this is a compact, fieldable device that can be used by international inspectors. Must be rugged and reliable; A next-generation source can be used as a testing ground for these techniques as technology develops.

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

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    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.

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

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    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.

  19. Active Interrogation Using Electronic Neutron Generators for Nuclear Safeguards Applications

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    David L. Chichester; Edward H. Seabury

    2008-08-01

    Active interrogation, a measurement technique which uses a radiation source to probe materials and generate unique signatures useful for characterizing those materials, is a powerful tool for assaying special nuclear material. The most commonly used technique for performing active interrogation is to use an electronic neutron generator as the probe radiation source. Exploiting the unique operating characteristics of these devices, including their monoenergetic neutron emissions and their ability to operate in pulsed modes, presents a number of options for performing prompt and delayed signature analyses using both photon and neutron sensors. A review of literature in this area shows multiple applications of the active neutron interrogation technique for performing nuclear nonproliferation measurements. Some examples include measuring the plutonium content of spent fuel, assaying plutonium residue in spent fuel hull claddings, assaying plutonium in aqueous fuel reprocessing process streams, and assaying nuclear fuel reprocessing facility waste streams to detect and quantify fissile material. This paper discusses the historical use of this technique and examines its context within the scope and challenges of next-generation nuclear fuel cycles and advanced concept nuclear fuel cycle facilities.

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

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    Williams, Richard Brady [Los Alamos National Laboratory; Browne, Michael C [Los Alamos National Laboratory; Parker, Robert F [Los Alamos National Laboratory; Ingegneri, Maurizio [IAEA

    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

  1. Safeguards Culture

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    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. Modeling and Simulation for Safeguards and Nonproliferation Workshop

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    Gilligan, Kimberly V. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Kirk, Bernadette Lugue [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    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.

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

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    Eipeldauer, Mary D [ORNL

    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.

  4. Achieving the Benefits of Safeguards by Design

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    Trond Bjornard; Robert Bean; David Hebditch; Jim Morgan; Bruce Meppen; Scott DeMuth; Michael Ehinger; John Hockert

    2008-07-01

    the design of nuclear facilities. This paper describes the work that has been completed in the development of a Safeguards by Design process for a project, illustrated by flow diagrams based upon the project phases described in U.S. Department of Energy Order 413.3A, Program and Project Management for the Acquisition of Capital Assets. The institutionalization of the Safeguards by Design process directly supports the goals of the Next Generation Safeguards Initiative and also aligns with goals and objectives of the International Atomic Energy Agency. Other benefits from institutionalizing this Safeguards by Design process are discussed within this paper.

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

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    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.

  6. The safeguards options study

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Mullen, M.F.; Olinger, C.T.; Stanbro, W.D. [Los Alamos National Lab., NM (United States); Olsen, A.P.; Roche, C.T.; Rudolph, R.R. [Argonne National Lab., IL (United States); Bieber, A.M.; Lemley, J. [Brookhaven National Lab., Upton, NY (United States); Filby, E. [Idaho National Engineering Lab., Idaho Falls, ID (United States)] [and others

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  8. Measuring Safeguards Culture

    Energy Technology Data Exchange (ETDEWEB)

    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.

  9. Training in Environmental Analyses for Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-09-01

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

  11. Improving the Safeguardability of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

  12. SAFEGUARDS ENVELOPE

    Energy Technology Data Exchange (ETDEWEB)

    Duc Cao; Richard Metcalf

    2010-07-01

    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 advanced statistical techniques that will be applied to real plant process monitoring (PM) data from the Idaho Chemical Processing Plant (ICPP). In a simulation based on this data, multi-tank and multi-attribute correlations were tested against synthetic diversion scenarios. Kernel regression smoothing was used to fit a curve to the historical data, and multivariable, residual analysis and cumulative sum techniques set parameters for operating conditions. Diversion scenarios were created and tested, showing improved results when compared with a previous study utilizing only one-variable Z-testing. A brief analysis of the impact of the safeguards optimization on the rest of plant efficiency, criticality concerns, and overall requirements is presented.

  13. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  14. Neutron flux from a 14‐MeV neutron generator with tungsten filter for research in NDA methods for nuclear safeguards and security

    OpenAIRE

    2009-01-01

    The Joint Research Centre has taken into operation a new experimental device designed for research in the fields of nuclear safeguards and security applications. The research projects currently undertaken include detection of shielded contraband materials, detection of fissile materials, and mass determination of small fissile materials in shielded containers. The device, called the Pulsed Neutron Interrogation Test Assembly (PUNITA), incorporates a pulsed 14‐MeV (D‐T) neutron generator and a...

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

    Energy Technology Data Exchange (ETDEWEB)

    Demuth, Scott F [Los Alamos National Laboratory; Mullen, Mark [Los Alamos National Laboratory

    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.

  16. Fish welfare assurance system: initial steps to set up an effective tool to safeguard and monitor farmed fish welfare at a company level.

    Science.gov (United States)

    van de Vis, J W; Poelman, M; Lambooij, E; Bégout, M-L; Pilarczyk, M

    2012-02-01

    The objective was to take a first step in the development of a process-oriented quality assurance (QA) system for monitoring and safeguarding of fish welfare at a company level. A process-oriented approach is focused on preventing hazards and involves establishment of critical steps in a process that requires careful control. The seven principles of the Hazard Analysis Critical Control Points (HACCP) concept were used as a framework to establish the QA system. HACCP is an internationally agreed approach for management of food safety, which was adapted for the purpose of safeguarding and monitoring the welfare of farmed fish. As the main focus of this QA system is farmed fish welfare assurance at a company level, it was named Fish Welfare Assurance System (FWAS). In this paper we present the initial steps of setting up FWAS for on growing of sea bass (Dicentrarchus labrax), carp (Cyprinus carpio) and European eel (Anguilla anguilla). Four major hazards were selected, which were fish species dependent. Critical Control Points (CCPs) that need to be controlled to minimize or avoid the four hazards are presented. For FWAS, monitoring of CCPs at a farm level is essential. For monitoring purposes, Operational Welfare Indicators (OWIs) are needed to establish whether critical biotic, abiotic, managerial and environmental factors are controlled. For the OWIs we present critical limits/target values. A critical limit is the maximum or minimum value to which a factor must be controlled at a critical control point to prevent, eliminate or reduce a hazard to an acceptable level. For managerial factors target levels are more appropriate than critical limits. Regarding the international trade of farmed fish products, we propose that FWAS needs to be standardized in aquaculture chains. For this standardization a consensus on the concept of fish welfare, methods to assess welfare objectively and knowledge on the needs of farmed fish are required.

  17. Integrating Safeguards and Security with Safety into Design

    Energy Technology Data Exchange (ETDEWEB)

    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.

  18. Regional Cooperation to Strengthen Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Minnini, Margot; Elkhamri, Oksana O.

    2016-06-06

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

  19. IAEA safeguards and non-proliferation

    Energy Technology Data Exchange (ETDEWEB)

    Harry, R.J.S.

    1995-02-01

    An overview is given of efforts to contain the nuclear weapons proliferation during half a century of man-controlled nuclear fission. An initial policy of denial did not work, a following period of cooperation needed a gradual strengthening of international assurances on the peaceful character of the flourishing use of nuclear techniques for power generation and of other applications. The focus of the nuclear weapon proliferation concern changed from the highly developed states to developing states. The Non-Proliferation Treaty laid the basis for a unique system of voluntarily accepted international inspections to verify the peaceful use of nuclear energy. The IAEA got the task to implement this `Full Scope Safeguards` on all nuclear material and all nuclear activities in the non-nuclear weapon states. Thanks to the structure of the IAEA, in which both proponent and states with a critical attitude take part in the decision making process on the IAEA execution of its tasks, a balanced, and widely acceptable system emerged. International developments necessitated additional improvements of the non-proliferation system. The increase of strength of sub-national groups triggered international cooperation on physical protection, about a quarter of a century ago. More recently, it appeared that NPT states with assumed nuclear weapon ambitions operated in the margins between the interpretation of IAEA safeguards and the spirit and purpose of NPT. Improvements of the IAEA safeguards and a stronger cooperation between states, including the constraints which exporting states have imposed on nuclear supplies, strengthen the safeguards system. The important reductions in the two largest nuclear weapon arsenals lead, together with the delay in the fast breeder implementation, to large stockpiles of nuclear weapon usable materials. Also in this areas new internationally credible assurances have to be obtained, that these materials will never return to nuclear weapon applications.

  20. Future challenges and DOE/NNSA-JAEA cooperation for the development of advanced safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Stevens, Rebecca S [Los Alamos National Laboratory; Mc Clelland - Kerr, John [NNSA-NA-242; Senzaki, Masao [JAEA; Hori, Masato [JAEA

    2009-01-01

    The United States Department of Energy/National Nuclear Security Administration (DOE/NNSA) has been cooperating with Japan on nuclear safeguards for over thirty years. DOE/NNSA has collaborated with the Japan Atomic Energy Agency (JAEA) and its predecessors in addressing the need for innovative solutions to nuclear transparency and verification issues in one of the world's most advanced nuclear fuel cycle states. This collaboration includes over ninety activities that have involved nearly every facility in the JAEA complex and many national laboratories in the U.S. complex. The partnership has yielded new technologies and approaches that have benefited international safeguards not only in Japan, but around the world. The International Atomic Energy Agency uses a number of safeguards solutions developed under this collaboration to improve its inspection efforts in Japan and elsewhere. Japanese facilities serve as test beds for emerging safeguards technologies and are setting the trend for new nuclear energy and fuel cycle development worldwide. The collaboration continues to be an essential component of U.S. safeguards outreach and is integral to the DOE/NNSA's Next Generation Safeguards Initiative. In addition to fostering international safeguards development, the cooperation is an opportunity for U.S. scientists to work in facilities that have no analog in the United States, thus providing crucial real-life experience for and aiding development of the next generation of U.S. safeguards specialists. It is also an important element of promoting regional transparency thereby building confidence in the peaceful nature of nuclear programs in the region. The successes engendered by this partnership provide a strong basis for addressing future safeguards challenges, in Japan and elsewhere. This paper summarizes these challenges and the associated cooperative efforts that are either underway or anticipated.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  2. Neutron flux from a 14-MeV neutron generator with tungsten filter for research in NDA methods for nuclear safeguards and security

    Science.gov (United States)

    Rennhofer, H.; Pedersen, B.; Crochemore, J.-M.

    2009-12-01

    The Joint Research Centre has taken into operation a new experimental device designed for research in the fields of nuclear safeguards and security applications. The research projects currently undertaken include detection of shielded contraband materials, detection of fissile materials, and mass determination of small fissile materials in shielded containers. The device, called the Pulsed Neutron Interrogation Test Assembly (PUNITA), incorporates a pulsed 14-MeV (D-T) neutron generator and a large graphite mantle surrounding the sample cavity. By pulsing the neutron generator with a frequency in the range of 10 to 150 Hz, a sample may be interrogated first by fast neutrons and a few hundred micro-seconds later by a pure thermal neutron flux. The permanent detection systems incorporated in PUNITA include 3He neutrons detectors, HPGe gamma detectors, and lanthanum bromide scintillation detectors. We have studied the effects of placing a tungsten liner around the neutron generator target. The 14-MeV neutrons induce (n, 2n) and (n, 3n) reactions. In addition the mean neutron energy emitted from generator/tungsten assembly is reduced to about 1 MeV. Both of these effects increase the thermal neutron flux in the sample cavity. The paper describes the observed advantages of the tungsten liner with respect to increase in thermal flux, and better shielding capabilities of the nearby gamma and neutron detectors.

  3. Nuclear safeguards technology handbook

    Energy Technology Data Exchange (ETDEWEB)

    1977-12-01

    The purpose of this handbook is to present to United States industrial organizations the Department of Energy's (DOE) Safeguards Technology Program. The roles and missions for safeguards in the U.S. government and application of the DOE technology program to industry safeguards planning are discussed. A guide to sources and products is included. (LK)

  4. Safeguards-by-Design: An Element of 3S Integration

    Energy Technology Data Exchange (ETDEWEB)

    R. S. Bean; T. A. Bjornard; D. J. Hebdich

    2009-04-01

    In 2008, the “20/20 Vision for the Future” background report by the IAEA Director General identified the possibility of integrating certain activities related to safeguards, safety, and security. Later in the year, the independent Commission report prepared at the request of the IAEA Director General noted that the Agency’s roles in nuclear safeguards, safety, and security (3S) complement and can mutually reinforce each other. Safeguards-by-design (SBD) is a practical measure that strengthens 3S integration, especially for the stage of nuclear facility design and construction, but also with ramifications for other stages of the facility life-cycle. This paper describes the SBD concept, with examples for diverse regulatory environments, being developed in the U.S under the U.S. Department of Energy (DOE) Next Generation Safeguards Initiative and the Advanced Fuel Cycle Initiative. This is compared with related international SBD work performed in the recent IAEA workshop on “Facility Design and Plant Operation Features that Facilitate the Implementation of IAEA Safeguards”. Potential future directions for further development of SBD and its integration within 3S are identified.

  5. Fish welfare assurance system: initial steps to set up an effective tool to safeguard and monitor farmed fish welfare at a company level

    NARCIS (Netherlands)

    Vis, van de J.W.; Poelman, M.; Lambooij, E.; Bégout, M.L.; Pilarczyk, M.

    2012-01-01

    The objective was to take a first step in the development of a process-oriented quality assurance (QA) system for monitoring and safeguarding of fish welfare at a company level. A process-oriented approach is focused on preventing hazards and involves establishment of critical steps in a process tha

  6. Implementing Safeguards-by-Design

    Energy Technology Data Exchange (ETDEWEB)

    Trond Bjornard; Robert Bean; Phillip Casey Durst; John Hockert; James Morgan

    2010-02-01

    Life-cycle cost analysis can be a useful tool in safeguards design. • An important obstacle to straight forward application of life-cycle cost analysis is that there is no single organization responsible for the entire life-cycle cost of the facility. • The Safeguards Effectiveness Report (SGER) is proposed as a focus for the safeguards design activities, and is intended to be a living document that contains increasing safeguards relevant scope and content as the facility design emerges. Further work is required in a number of areas. The authors note that other studies supported by NGSI are addressing the development of requirements and performance criteria, as well as contributing to the design toolkit through the development of technology, methodology, and safeguards guidelines for designers. With respect to further development of the SBD design process, the authors recommend: • In the short term, conduct a workshop with interested industry representatives, to ensure that their perspectives and needs are factored into further development. • In the short term, provide NGSI SBD project documents to IAEA, and support them in the conduct of an ‘SBD Workshop II.” • In the medium term, continue to support the SBD demonstration work started with the Next Generation Nuclear Plant project. • In the longer term, conduct further studies to examine the integration of SBD into projects with concurrent consideration of physical security and safety.

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

    Energy Technology Data Exchange (ETDEWEB)

    Richard Metcalf; Robert Bean

    2009-10-01

    Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA’s Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility’s general character, purpose, capacity, and location; (2) Description of the facility’s layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards

  8. Nuclear safeguards; Salvaguardias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zurron, O.

    2015-07-01

    Safeguards control at the Juzbado Plant is implemented through the joint IAEA/EURATOM partnership approach in force within the European Union for all nuclear facilities. this verification agreement is designed to minimize burden on the operators whilst ensuring that both inspectorate achieve the objectives related to their respective safeguards regimes. This paper outlines the safeguards approaches followed by the inspectorate and the particularities of the Juzbado Plants nuclear material accountancy and control system. (Authors)

  9. Suggested safeguards an

    African Journals Online (AJOL)

    MJM Venter

    ... COORDINATION. (FACILITATION OR CASE MANAGEMENT) IN SOUTH AFRICA ... SUGGESTED SAFEGUARDS AND LIMITATIONS FOR EFFECTIVE AND .... professional practice.27 They have to assess the situation; educate the parents.

  10. A Legal Analysis of Safeguard Measures in the European Community

    Directory of Open Access Journals (Sweden)

    Guang Ma

    2006-12-01

    -compatibility in the European Community's safeguards, especially in terms of non-parallelism, the simultaneous imposition of a provisional safeguard measure at the initiation of a safeguard investigation, the vague meaning of regional safeguards, and so on.

  11. The Prototype Development for The Second Generation CBERS Initiates

    Institute of Scientific and Technical Information of China (English)

    SunQing

    2005-01-01

    It's reported that the concept for the second generation CBERS-CBERS-03 & 04 to be jointly developed by China Academy of Space Technology (CAST) and INPE went through the assessment by China Aerospace Science and Technology Corporation (CASC) at the beginning of the year. It means that the prototype development of CBERS-03 & 04 has been initiated.

  12. Strenghening Safeguards Authorities and Institutions

    Energy Technology Data Exchange (ETDEWEB)

    Goodman,M.; Lockwood, d.; Rosenthal, M.D.; Tape, J.W.

    2008-06-06

    The International Atomic Energy Agency (IAEA) safeguards system has changed in major ways from the establishment of the IAEA in 1957 until the present. Changes include strengthening the legal framework of safeguards; improvements in concepts and approaches for safeguards implementation; and significant improvements in the technical tools available to inspectors. In this paper, we explore three broad areas related to strengthening safeguards authorities and institutions: integrated safeguards and State-Level Approaches; special inspections; and NPT withdrawal and the continuation of safeguards.

  13. Nuclear Resonance Fluorescence for Safeguards Applications

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Pepper, Susan E. [Brookhaven National Lab. (BNL), Upton, NY (United States); Pickett, Chris A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Queirolo, Al [Brookhaven National Lab. (BNL), Upton, NY (United States); Bachner, Katherine M. [Brookhaven National Lab. (BNL), Upton, NY (United States); Worrall, Louise G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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

  16. Initial data generating bounded solutions of linear discrete equations

    Directory of Open Access Journals (Sweden)

    Jaromír Baštinec

    2006-01-01

    Full Text Available A lot of papers are devoted to the investigation of the problem of prescribed behavior of solutions of discrete equations and in numerous results sufficient conditions for existence of at least one solution of discrete equations having prescribed asymptotic behavior are indicated. Not so much attention has been paid to the problem of determining corresponding initial data generating such solutions. We fill this gap for the case of linear equations in this paper. The initial data mentioned are constructed with use of two convergent monotone sequences. An illustrative example is considered, too.

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

    Energy Technology Data Exchange (ETDEWEB)

    Gallucci, N. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    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.

  18. Establishment of national safeguards system and assistance to IAEA safeguards inspection

    Energy Technology Data Exchange (ETDEWEB)

    Park, Wan Sou; Kwack, Eun Ho; Park, Chan Sik; Lee, Jae Sung; Jeong, Mi Young

    1995-12-01

    In Korea, 17 nuclear facilities are currently under IAEA`s safeguards and it is expected that more than 25 nuclear facilities will be under IAEA`s safeguards in the year 2000 according to nuclear R and D and industry expansion. In connection with unlimited extension of NPT in 1995 and IAEA`s measures to strengthen the safeguards like `Programme 93+2`, the international non-proliferation regime will be strengthened more and nuclear advanced countries will require the transparency and credibility of nuclear activities in recipient countries instead of transferring advanced nuclear technologies and nuclear material. In 1995, the Korean Government had revised the Atomic Energy Law to control increasing nuclear facilities and nuclear material effectively and to establish international transparency and credibility. In the revised Atomic Energy Law, it is provided that the national inspection, other than IAEA inspection, will be started from 1996. Currently, necessary arrangements for national inspection are being prepared by MOST and TCNC at KAERI. However, the safeguards system in Korea is still beginning stage, Korea`s safeguards activity was passive and fragmentary that leads non-attainment of safeguards goal in many facilities. The reasons were; absence of systematic safeguards system(SSAC); lack of understanding safeguards concepts; lack of manpower, designated organization for safeguards, etc. As Korea ranked world top 10 nuclear power generation country and has a plan to be a nuclear advanced country, Korea should have appropriate safeguards system and should not spare necessary assistance to that system. (author). 19 tabs., 2 figs.

  19. AFCI Safeguards Enhancement Study: Technology Development Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    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.

  20. Strengthening regional safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Palhares, L.; Almeida, G.; Mafra, O. [Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, Rio de Janeiro (Brazil)] [and others

    1996-08-01

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

  1. Technology development for safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ho Dong; Kang, H. Y.; Song, D. Y. [and others

    2005-04-01

    The objective of this project are to establish the safeguards technology of the nuclear proliferation resistance to the facilities which handle with high radioactivity nuclear materials like the spent fuel, to provide the foundation of the technical independency for the establishment of the effective management of domestic spent fuels, and to construct the base of the early introduction of the key technology relating to the back-end nuclear fuel cycle through the development of the safeguards technology of the DFDF of the nuclear non-proliferation. The essential safeguards technologies of the facility such as the measurement and account of nuclear materials and the C/S technology were carried out in this stage (2002-2004). The principal results of this research are the development of error reduction technology of the NDA equipment and a new NDA system for the holdup measurement of process materials, the development of the intelligent surveillance system based on the COM, the evaluation of the safeguardability of the Pyroprocessing facility which is the core process of the nuclear fuel cycle, the derivation of the research and development items which are necessary to satisfy the safeguards criteria of IAEA, and the presentation of the direction of the technology development relating to the future safeguards of Korea. This project is the representative research project in the field of the Korea's safeguards. The safeguards technology and equipment developed while accomplishing this project can be applied to other nuclear fuel cycle facilities as well as DFDF and will be contributed to increase the international confidence in the development of the nuclear fuel cycle facility of Korea and its nuclear transparency.

  2. International safeguards data authentication

    Energy Technology Data Exchange (ETDEWEB)

    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.

  3. Safeguards and physics measurements

    Energy Technology Data Exchange (ETDEWEB)

    Carchon, R

    2002-04-01

    SCK-CEN's programme on safeguards and physics measurements involves gamma and neutron dosimetry, calibrations and irradiations, electronic support, metrology of various samples including internal contamination of human beings, of waste barrels and of fissile materials, neutron activation analysis, and radioisotope source preparation. The document reports on the main activities and achievements of the sections 'Instrumentation, Calibration and Dosimetry' and 'Safeguards and Nuclear Physics Measurements'.

  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

    Energy Technology Data Exchange (ETDEWEB)

    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. Initial steps of supercontinuum generation in photonic crystal fibers

    DEFF Research Database (Denmark)

    Hilligsøe, Karen Marie; Paulsen, H.N.; Thøgersen, J.;

    2003-01-01

    The onset of supercontinuum generation in a photonic crystal fiber is investigated experimentally and numerically as a function of pump wavelength and intensity with 100-fs pulses. Soliton formation is found to be the determining factor in the initial step. The formation and behavior of a blueshi...... of a blueshifted, nonsolitonic component, emitted as the soliton evolves towards the stable regime, is investigated and the role of phase matching through higher-order dispersion is highlighted. Good agreement between experiments and simulations is obtained....

  6. Initial transient process in a simple helical flux compression generator

    Institute of Scientific and Technical Information of China (English)

    Yang Xian-Jun

    2006-01-01

    An analytical scheme on the initial transient process in a simple helical flux compression generator, which includes the distributions of both the magnetic field in the hollow of an armature and the conducting current density in the stator, is developed by means of a diffusion equation. A relationship between frequency of the conducting current, root of the characteristic function of Bessel equation and decay time in the armature is given. The skin depth in the helical stator is calculated and is compared with the approximate one which is widely used in the calculation of magnetic diffusion. Our analytical results are helpful to understanding the mechanism of the loss of magnetic flux in both the armature and stator and to suggesting an optimal design for improving performance of the helical flux compression generator.

  7. Mechanisms of sharp wave initiation and ripple generation.

    Science.gov (United States)

    Schlingloff, Dániel; Káli, Szabolcs; Freund, Tamás F; Hájos, Norbert; Gulyás, Attila I

    2014-08-20

    Replay of neuronal activity during hippocampal sharp wave-ripples (SWRs) is essential in memory formation. To understand the mechanisms underlying the initiation of irregularly occurring SWRs and the generation of periodic ripples, we selectively manipulated different components of the CA3 network in mouse hippocampal slices. We recorded EPSCs and IPSCs to examine the buildup of neuronal activity preceding SWRs and analyzed the distribution of time intervals between subsequent SWR events. Our results suggest that SWRs are initiated through a combined refractory and stochastic mechanism. SWRs initiate when firing in a set of spontaneously active pyramidal cells triggers a gradual, exponential buildup of activity in the recurrent CA3 network. We showed that this tonic excitatory envelope drives reciprocally connected parvalbumin-positive basket cells, which start ripple-frequency spiking that is phase-locked through reciprocal inhibition. The synchronized GABA(A) receptor-mediated currents give rise to a major component of the ripple-frequency oscillation in the local field potential and organize the phase-locked spiking of pyramidal cells. Optogenetic stimulation of parvalbumin-positive cells evoked full SWRs and EPSC sequences in pyramidal cells. Even with excitation blocked, tonic driving of parvalbumin-positive cells evoked ripple oscillations. Conversely, optogenetic silencing of parvalbumin-positive cells interrupted the SWRs or inhibited their occurrence. Local drug applications and modeling experiments confirmed that the activity of parvalbumin-positive perisomatic inhibitory neurons is both necessary and sufficient for ripple-frequency current and rhythm generation. These interneurons are thus essential in organizing pyramidal cell activity not only during gamma oscillation, but, in a different configuration, during SWRs.

  8. Safeguards by Design Challenge

    Energy Technology Data Exchange (ETDEWEB)

    Alwin, Jennifer Louise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-13

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

  9. Staging Mixed-Initiative Dialogs by Program Generation and Transformation

    CERN Document Server

    Perugini, Saverio

    2011-01-01

    Specifying and implementing flexible human-computer dialogs, such as those used in ATMs, airport and train kiosks, and apps for smart phones and similar devices, is challenging because of the numerous and varied directions in which each user might steer a dialog, all of which must be captured in a specification and implementation of it. The purpose of this research is to improve dialog specification and implementation. To do so we enriched a notation based on concepts from programming languages, including currying and partial evaluation, for specifying a variety of unsolicited reporting, mixed-initiative dialogs in a concise representation which serves as a plan for implementing the dialog. We also built a dialog mining system which extracts specifications in this notation from dialog requirements. To demonstrate that the structure of a dialog specification in this notation provides a design for its implementation, we built a system which automatically generates an implementation (called a stager) for it give...

  10. Automating Initial Guess Generation for High Fidelity Trajectory Optimization Tools

    Science.gov (United States)

    Villa, Benjamin; Lantoine, Gregory; Sims, Jon; Whiffen, Gregory

    2013-01-01

    Many academic studies in spaceflight dynamics rely on simplified dynamical models, such as restricted three-body models or averaged forms of the equations of motion of an orbiter. In practice, the end result of these preliminary orbit studies needs to be transformed into more realistic models, in particular to generate good initial guesses for high-fidelity trajectory optimization tools like Mystic. This paper reviews and extends some of the approaches used in the literature to perform such a task, and explores the inherent trade-offs of such a transformation with a view toward automating it for the case of ballistic arcs. Sample test cases in the libration point regimes and small body orbiter transfers are presented.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  12. Resourcing Future Generations - Challenges for geoscience: a new IUGS initiative

    Science.gov (United States)

    Oberhänsli, Roland; Lambert, Ian

    2014-05-01

    In a world with rapidly increasing population and technological development new space based remote sensing tools allowed for new discoveries and production of water, energy- and mineral-resources, including minerals, soils and construction materials. This has impact on politics, socio-economic development and thus calls for a strong involvement of geosciences because one of humanities biggest challenges will be, to rise living standards particularly in less developed countries. Any growth will lead to an increase of demand for natural resources. But especially for readily available mineral resources supply appears to be limited. Particularly demand for so called high-tech commodities - platinum group or rare earth elements - increased. This happened often faster than new discoveries were made. All this, while areas available for exploration decreased as the need for urban and agricultural use increased. Despite strong efforts in increasing efficiency of recycling, shortage in some commodities has to be expected. A major concern is that resources are not distributed evenly on our planet. Thus supplies depend on political stability, socio-economic standards and pricing. In the light of these statements IUGS is scoping a new initiative, Resourcing Future Generations (RFG), which is predicated on the fact that mining will continue to be an essential activity to meet the needs of future generations. RFG is aimed at identifying and addressing key challenges involved in securing natural resources to meet global needs post-2030. We consider that mineral resources should be the initial focus, but energy, soils, water resources and land use should also be covered. Addressing the multi-generational needs for mineral and other natural resources requires data, research and actions under four general themes: 1. Comprehensive evaluation and quantification of 21st century supply and demand. 2. Enhanced understanding of subsurface as it relates to mineral (energy and groundwater

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

    Energy Technology Data Exchange (ETDEWEB)

    Gilligan, Kimberly V. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Nuclear Security and Isotope Technology Division; Gaudet, Rachel N. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Nuclear Security and Isotope Technology Division

    2016-09-30

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

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

    Energy Technology Data Exchange (ETDEWEB)

    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

  15. Developing the information management system for safeguards national inspection

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. J.; Jeon, I.; Park, W. S.; Min, K. S. [KAERI, Taejon (Korea, Republic of)

    2003-10-01

    The inspection information management system for safeguards national inspection is aimed to do the national safeguards inspection with efficiency, and to decrease the inspector's load to write inspection report by systematizing the inspection jobs and sharing the inspection data. National safeguards inspection is consisted two large jobs. The first is the national safeguards supporting job of managing to support the national inspection mission. The other is the writing a national inspection report after completing the national inspection. Before the developing of inspection information management system, the official tools(spread sheet, word processor) are usually used. But there is problem to share the data, to produce the statistics data. To solve the these problem, we developed the inspection information management system that process the job from initial to final inspection work, and opened user education. This paper explain the procedure of developing the inspection information management system for safeguards national inspection.

  16. Technology transfer significance of the International Safeguards Project Office

    Energy Technology Data Exchange (ETDEWEB)

    Marcuse, W.; Waligura, A.J.

    1988-06-01

    The safeguards implemented by the International Atomic Energy Agency (IAEA) are of major importance to the non-proliferation objectives of the United States of America and other nations of the world. Assurance of safeguards effectiveness is mandatory to continued peaceful use of nuclear power. To enhance the ability of the IAEA to apply safeguards effectively, and to ensure that the IAEA does not lack technical assistance in critical areas, the US Congress has made available a special authorization for a Program for Technical Assistance to IAEA Safeguards (POTAS). This substantial program of technology transfer was initiated in 1976. The United States Departments of State and Energy, the Arms control and Disarmament Agency and the Nuclear Regulatory Commission have each accepted responsibility for parts of the Program for Technical Assistance to IAEA Safeguards. Funding is provided by state through the Foreign Assistance Act. This report provides a discussion of this program.

  17. The future of IAEA safeguards: challenges and responses

    Energy Technology Data Exchange (ETDEWEB)

    Pilat, Joseph F [Los Alamos National Laboratory; Budlong - Sylvester, Kory W [Los Alamos National Laboratory

    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

  18. The future of IAEA safeguards: challenges and responses

    Energy Technology Data Exchange (ETDEWEB)

    Pilat, Joseph F [Los Alamos National Laboratory; Budlong - Sylvester, Kory W [Los Alamos National Laboratory

    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

  19. Separations and safeguards model integration.

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin B.; Zinaman, Owen

    2010-09-01

    Research and development of advanced reprocessing plant designs can greatly benefit from the development of a reprocessing plant model capable of transient solvent extraction chemistry. This type of model can be used to optimize the operations of a plant as well as the designs for safeguards, security, and safety. Previous work has integrated a transient solvent extraction simulation module, based on the Solvent Extraction Process Having Interaction Solutes (SEPHIS) code 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 goal of this work was to strengthen the integration by linking more variables between the two codes. The results from this integrated model show expected operational performance through plant transients. Additionally, ORIGEN source term files were integrated into the SSPM to provide concentrations, radioactivity, neutron emission rate, and thermal power data for various spent fuels. This data was used to generate measurement blocks that can determine the radioactivity, neutron emission rate, or thermal power of any stream or vessel in the plant model. This work examined how the code could be expanded to integrate other separation steps and benchmark the results to other data. Recommendations for future work will be presented.

  20. Feasibility of x ray fluorescence for spent fuel safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Freeman, Corey Ross [Los Alamos National Laboratory; Mozin, Vladimir [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Fensin, Michael L [Los Alamos National Laboratory; White, Julia M [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Stafford, Alissa [TAMU; Charlton, William [TAMU

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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).

  3. SARS: Safeguards Accounting and Reporting Software

    Science.gov (United States)

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

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

  4. Technology Development of Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ho Dong; Kang, H. Y.; Ko, W. I. (and others)

    2007-04-15

    The objective of this project is to perform R and D on the essential technologies in nuclear material measurement and surveillance and verification system, and to improve the state of being transparent on the nuclear material management of DUPIC Fuel Development Facility (DFDF) through the evaluation of safeguard ability on non-proliferation fuel cycle and nuclear proliferation resistance. Nuclear material position scan system for the reduction of measurement error was developed for the spatial distribution search of spent fuel in DUPIC facility. Web-based realtime remote monitoring system was designed and constructed for satisfying the IAEA's performance criteria of continuous monitoring, and also developed a software for the function of remote control and message. And diversion paths in a proliferation resistant pyroprocess for SFR were analyzed and its protecting system against the diversion paths were suggested for enhancing proliferation resistance of advanced nuclear fuel cycle. These results could be used for planning the further R and D items in the area of safeguards. Those R and D results mentioned above would be helpful for increasing Korean nuclear transparency in the future.

  5. Strengthening IAEA Safeguards for Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Reid, Bruce D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Anzelon, George A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Budlong-Sylvester, Kory [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-01

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

  6. Generation and initial characterization of FDD knock in mice.

    Directory of Open Access Journals (Sweden)

    Luca Giliberto

    Full Text Available BACKGROUND: Mutations in the integral membrane protein 2B, also known as BRI(2, a type II trans-membrane domain protein cause two autosomal dominant neurodegenerative diseases, Familial British and Danish Dementia. In these conditions, accumulation of a C-terminal peptide (ABri and ADan cleaved off from the mutated precursor protein by the pro-protein convertase furin, leads to amyloid deposition in the walls of blood vessels and parenchyma of the brain. Recent advances in the understanding of the generation of amyloid in Alzheimer's disease has lead to the finding that BRI(2 interacts with the Amyloid Precursor Protein (APP, decreasing the efficiency of APP processing to generate Abeta. The interaction between the two precursors, APP and BRI(2, and possibly between Abeta and ABri or ADan, could be important in influencing the rate of amyloid production or the tendency of these peptides to aggregate. METHODOLOGY/PRINCIPAL FINDINGS: We have generated the first BRI(2 Danish Knock-In (FDD(KI murine model of FDD, expressing the pathogenic decamer duplication in exon 6 of the BRI(2 gene. FDD(KI mice do not show any evident abnormal phenotype, with normal brain histology and no detectable amyloid deposition in blood vessel walls or parenchyma. CONCLUSIONS/SIGNIFICANCE: This new murine mouse model will be important to further understand the interaction between APP and BRI(2, and to provide insights into the molecular basis of FDD.

  7. Generating optimal initial conditions for smooth particle hydrodynamics (SPH) simulations

    Energy Technology Data Exchange (ETDEWEB)

    Diehl, Steven [Los Alamos National Laboratory; Rockefeller, Gabriel M [Los Alamos National Laboratory; Fryer, Christopher L [Los Alamos National Laboratory

    2008-01-01

    We present a new optimal method to set up initial conditions for Smooth Particle Hydrodynamics Simulations, which may also be of interest for N-body simulations. This new method is based on weighted Voronoi tesselations (WVTs) and can meet arbitrarily complex spatial resolution requirements. We conduct a comprehensive review of existing SPH setup methods, and outline their advantages, limitations and drawbacks. A serial version of our WVT setup method is publicly available and we give detailed instruction on how to easily implement the new method on top of an existing parallel SPH code.

  8. Integrating security analysis and safeguards software engineering

    Energy Technology Data Exchange (ETDEWEB)

    Spencer, D.D.; Axline, R.M.

    1989-01-01

    These initiatives will work together to provide more secure safeguards software, as well as other critical systems software. The resulting design tools and methodologies, the evolving guidelines for software security, and the adversary-resistant software components will be applied to the software design at each stage to increase the design's inherent security and to make the design easier to analyze. The resident hardware monitor or other architectural innovations will provide complementary additions to the design to remove some of the burden of security from the software. The security analysis process, supported by new analysis methodologies and tools, will be applied to the software design as it evolves in an attempt to identify and remove vulnerabilities at the earliest possible point in the safeguards system life cycle. The result should be better and more verifiably secure software systems.

  9. Los Alamos safeguards program overview and NDA in safeguards

    Energy Technology Data Exchange (ETDEWEB)

    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.

  10. Artificial Intelligence Application in Power Generation Industry: Initial considerations

    Science.gov (United States)

    Ismail, Rahmat Izaizi B.; Ismail Alnaimi, Firas B.; AL-Qrimli, Haidar F.

    2016-03-01

    With increased competitiveness in power generation industries, more resources are directed in optimizing plant operation, including fault detection and diagnosis. One of the most powerful tools in faults detection and diagnosis is artificial intelligence (AI). Faults should be detected early so correct mitigation measures can be taken, whilst false alarms should be eschewed to avoid unnecessary interruption and downtime. For the last few decades there has been major interest towards intelligent condition monitoring system (ICMS) application in power plant especially with AI development particularly in artificial neural network (ANN). ANN is based on quite simple principles, but takes advantage of their mathematical nature, non-linear iteration to demonstrate powerful problem solving ability. With massive possibility and room for improvement in AI, the inspiration for researching them are apparent, and literally, hundreds of papers have been published, discussing the findings of hybrid AI for condition monitoring purposes. In this paper, the studies of ANN and genetic algorithm (GA) application will be presented.

  11. Investigation of novel spent fuel verification system for safeguard application

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Haneol; Yim, Man-Sung [KAIST, Daejeon (Korea, Republic of)

    2016-10-15

    Radioactive waste, especially spent fuel, is generated from the operation of nuclear power plants. The final stage of radioactive waste management is disposal which isolates radioactive waste from the accessible environment and allows it to decay. The safety, security, and safeguard of a spent fuel repository have to be evaluated before its operation. Many researchers have evaluated the safety of a repository. These researchers calculated dose to public after the repository is closed depending on their scenario. Because most spent fuel repositories are non-retrievable, research on security or safeguards of spent fuel repositories have to be performed. Design based security or safeguard have to be developed for future repository designs. This study summarizes the requirements of future spent fuel repositories especially safeguards, and suggests a novel system which meets the safeguard requirements. Applying safeguards to a spent fuel repository is becoming increasingly important. The future requirements for a spent fuel repository are suggested by several expert groups, such as ASTOR in IAEA. The requirements emphasizes surveillance and verification. The surveillance and verification of spent fuel is currently accomplished by using the Cerenkov radiation detector while spent fuel is being stored in a fuel pool. This research investigated an advanced spent fuel verification system using a system which converts spent fuel radiation into electricity. The system generates electricity while it is conveyed from a transportation cask to a disposal cask. The electricity conversion system was verified in a lab scale experiment using an 8.51GBq Cs-137 gamma source.

  12. Automatic Generation of Printed Catalogs: An Initial Attempt

    Directory of Open Access Journals (Sweden)

    Jared Camins-Esakov

    2010-06-01

    Full Text Available Printed catalogs are useful in a variety of contexts. In special collections, they are often used as reference tools and to commemorate exhibits. They are useful in settings, such as in developing countries, where reliable access to the Internet—or even electricity—is not available. In addition, many private collectors like to have printed catalogs of their collections. All the information needed for creating printed catalogs is readily available in the MARC bibliographic records used by most libraries, but there are no turnkey solutions available for the conversion from MARC to printed catalog. This article describes the development of a system, available on github, that uses XSLT, Perl, and LaTeX to produce press-ready PDFs from MARCXML files. The article particularly focuses on the two XSLT stylesheets which comprise the core of the system, and do the "heavy lifting" of sorting and indexing the entries in the catalog. The author also highlights points where the data stored in MARC bibliographic records requires particular "massaging," and suggests improvements for future attempts at automated printed catalog generation.

  13. Integrated safeguards and facility design and operations

    Energy Technology Data Exchange (ETDEWEB)

    Tape, J.W.; Coulter, C.A.; Markin, J.T.; Thomas, K.E.

    1987-01-01

    The integration of safeguards functions to deter or detect unauthorized actions by insiders requires careful communication and management of safeguards-relevant information on a timely basis. The separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification and careful attention to management of information can result in effective safeguards integration. Whether designing new systems or analyzing existing ones, understanding the interface between facility operations and safeguards is critical to cost-effective integrated safeguards systems that meet modern standards of performance.

  14. Development of DUPIC safeguards technology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. D.; Ko, W. I.; Song, D. Y. [and others

    2000-03-01

    During the first phase of R and D program conducted from 1997 to 1999, nuclear material safeguards studies system were performed on the technology development of DUPIC safeguards system such as nuclear material measurement in bulk form and product form, DUPIC fuel reactivity measurement, near-real-time accountancy, and containment and surveillance system for effective and efficient implementation of domestic and international safeguards obligation. For the nuclear material measurement system, the performance test was finished and received IAEA approval, and now is being used in DUPIC Fuel Fabrication Facility(DFDF) for nuclear material accounting and control. Other systems being developed in this study were already installed in DFDF and being under performance test. Those systems developed in this study will make a contribution not only to the effective implementation of DUPIC safeguards, but also to enhance the international confidence build-up in peaceful use of spent fuel material. (author)

  15. A free topology safeguards network

    Energy Technology Data Exchange (ETDEWEB)

    Kadner, S.P.; Resnik, W.M. [Aquila Technologies Group, Inc., Albuquerque, NM (United States); Schurig, A. [Communications Foundation, Orem, UT (United States)

    1995-12-31

    Free Topology Network technology provides cost reduction benefits as well as flexibility in safeguards applications. Power line communications technologies have proven viability for transmission and reception of safeguards data, including surveillance photographs, the source of the largest data files. In the future, enhancements will be made to the technology that should boost both performance and flexibility. Work is already underway to achieve higher data rates over power line communications eventually, it should be possible to reach data rates of one million bits per second or higher. Also, the use of technologies such as Novell Embedded Systems Technology (NEST) and Echelon LON technology will allow a greater number of safeguards technologies to become resident on the Free Topology Safeguards Network.

  16. Us-Japan cooperation on safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Beddingfield, David H [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Hori, Masato [JAEA; Kawakubo, Yoko [JAEA; Mcclelland - Kerr, J [NNSA

    2009-01-01

    There is a long history of collaborative safeguards development between the United States and Japan. Japan has built, and continues to expand, the largest civil nuclear fuel cycle under full-scope IAEA safeguards in world. This development has posed unique challenges to the international safeguards system. Safeguards developments made through the US-Japan cooperation to address these unique challenges have significantly impacted the technologies deployed for international safeguards applications around the world.

  17. Designing Data Protection Safeguards Ethically

    Directory of Open Access Journals (Sweden)

    Ugo Pagallo

    2011-03-01

    Full Text Available Since the mid 1990s, lawmakers and scholars have worked on the idea of embedding data protection safeguards in information and communication technology (ICT with the aim to access and control personal data in compliance with current regulatory frameworks. This effort has been strengthened by the capacities of computers to draw upon the tools of artificial intelligence (AI and operations research. However, work on AI and the law entails crucial ethical issues concerning both values and modalities of design. On one hand, design choices might result in conflicts of values and, vice versa, values may affect design features. On the other hand, the modalities of design cannot only limit the impact of harm-generating behavior but also prevent such behavior from occurring via self-enforcement technologies. In order to address some of the most relevant issues of data protection today, the paper suggests we adopt a stricter, yet more effective version of “privacy by design.” The goal should be to reinforce people’s pre-existing autonomy, rather than having to build it from scratch.

  18. Strengthening IAEA Safeguards for Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Reid, Bruce D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Anzelon, George A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Budlong-Sylvester, Kory [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-01

    During their December 10-11, 2013, workshop in Grenoble France, which focused on the history and future of safeguarding research reactors, the United States, France and the United Kingdom (UK) agreed to conduct a joint study exploring ways to strengthen the IAEA’s safeguards approach for declared research reactors. This decision was prompted by concerns about: 1) historical cases of non-compliance involving misuse (including the use of non-nuclear materials for production of neutron generators for weapons) and diversion that were discovered, in many cases, long after the violations took place and as part of broader pattern of undeclared activities in half a dozen countries; 2) the fact that, under the Safeguards Criteria, the IAEA inspects some reactors (e.g., those with power levels under 25 MWt) less than once per year; 3) the long-standing precedent of States using heavy water research reactors (HWRR) to produce plutonium for weapons programs; 4) the use of HEU fuel in some research reactors; and 5) various technical characteristics common to some types of research reactors that could provide an opportunity for potential proliferators to misuse the facility or divert material with low probability of detection by the IAEA. In some research reactors, for example, such characteristics include rapid on-line refueling, and a core design with room for such a large number of assemblies or targets that it is difficult to detect diversion or undeclared irradiation. In addition, infrastructure associated with research reactors, such as hot cells, where plutonium could be separated, could pose a safeguards challenge because, in some cases, they are not declared (because they are not located in the facility or because nuclear materials are not foreseen to be processed inside) and may not be accessible to inspectors in States without an Additional Protocol in force.

  19. 78 FR 56690 - Seneca Generation, LLC; Supplemental Notice That Initial Market-Based Rate Filing Includes...

    Science.gov (United States)

    2013-09-13

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Seneca Generation, LLC; Supplemental Notice That Initial Market- Based Rate...-referenced proceeding, of Seneca Generation, LLC's application for market-based rate authority, with...

  20. Effect of Initial Frequency Chirp on Supercontinuum Generation in Dispersion-flattened Fibers

    Institute of Scientific and Technical Information of China (English)

    CHEN Yong-zhu; LI Yong-yao; YU Zhi-qiang Yu; FENG Ming-neng

    2009-01-01

    . Supercontinuum generation in dispersion-flattened fibers is studied theoretically. It is found that the flat spectral width of the supercontinuum generation in normal dispersion-flattened fiber can be increased from 66 nm to over 100 nm when the absolute value of the initial frequency chirps is increased from zero to 10. It is further found that initial frequency chirps are adverse to flat and wideband supercontinuum generation in anomalous dispersion-flattened fiber, and when the absolute value of the frequency chirps is increased to a certain degree, supercontinuum spectrum even can not be achieved.

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

    Energy Technology Data Exchange (ETDEWEB)

    PEPPER,S.; QUEIROLO, A.; ZENDEL, M.; WHICHELLO, J.; ANNESE, C.; GRIEBE, J.; GRIEBE, R.

    2007-11-13

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

  2. ACO-Initialized Wavelet Neural Network for Vibration Fault Diagnosis of Hydroturbine Generating Unit

    Directory of Open Access Journals (Sweden)

    Zhihuai Xiao

    2015-01-01

    Full Text Available Considering the drawbacks of traditional wavelet neural network, such as low convergence speed and high sensitivity to initial parameters, an ant colony optimization- (ACO- initialized wavelet neural network is proposed in this paper for vibration fault diagnosis of a hydroturbine generating unit. In this method, parameters of the wavelet neural network are initialized by the ACO algorithm, and then the wavelet neural network is trained by the gradient descent algorithm. Amplitudes of the frequency components of the hydroturbine generating unit vibration signals are used as feature vectors for wavelet neural network training to realize mapping relationship from vibration features to fault types. A real vibration fault diagnosis case result of a hydroturbine generating unit shows that the proposed method has faster convergence speed and stronger generalization ability than the traditional wavelet neural network and ACO wavelet neural network. Thus it can provide an effective solution for online vibration fault diagnosis of a hydroturbine generating unit.

  3. 21 CFR 312.88 - Safeguards for patient safety.

    Science.gov (United States)

    2010-04-01

    ... initial human testing (§ 312.23), and the monitoring of adverse drug experiences through the requirements... application (§ 314.50 of this chapter), and postmarketing adverse reaction reporting (§ 314.80 of this chapter). ... 21 Food and Drugs 5 2010-04-01 2010-04-01 false Safeguards for patient safety. 312.88 Section...

  4. Remote instrumentation and safeguards monitoring for the star project

    Energy Technology Data Exchange (ETDEWEB)

    Buettner, H M; Labiak, W; Spiridon, A

    2000-06-15

    A part of the Nuclear Energy Research Initiative (NERI) is the development of the Small Transportable Autonomous Reactor (STAR) for deployment in countries that do not have a nuclear industry. STARs would have an output of from 100 to 150 MW electric, would be fueled in the country of manufacture, and after 15 to 20 years of operation the reactor core would be returned to the country of manufacture for refueling. A candidate STAR design can be found in (Greenspan, 2000). This paper describes the design of the control and monitoring system that might be used. There are two unique features to this system. One is that the monitored information will be transmitted to a remote site for two purposes, safeguards, and allowing experts a great distance away direct access to view the reactor's operating parameters. The second feature is safeguards sensors will be designed into the system and there will monitoring of the safeguards aspects of the system for tampering. Any safeguards anomalies will be sent to the remote site as alarms. Encrypted satellite communications will be used to transmit the data. These features allow the STAR to be operated by a small staff and will reduce the costs of safeguards monitoring by reducing the number of plant visits by inspectors.

  5. Remote instrumentation and safeguards monitoring for the star project

    Energy Technology Data Exchange (ETDEWEB)

    Buettner, H M; Labiak, W; Spiridon, A

    2000-06-15

    A part of the Nuclear Energy Research Initiative (NERI) is the development of the Small Transportable Autonomous Reactor (STAR) for deployment in countries that do not have a nuclear industry. STARs would have an output of from 100 to 150 MW electric, would be fueled in the country of manufacture, and after 15 to 20 years of operation the reactor core would be returned to the country of manufacture for refueling. A candidate STAR design can be found in (Greenspan, 2000). This paper describes the design of the control and monitoring system that might be used. There are two unique features to this system. One is that the monitored information will be transmitted to a remote site for two purposes, safeguards, and allowing experts a great distance away direct access to view the reactor's operating parameters. The second feature is safeguards sensors will be designed into the system and there will monitoring of the safeguards aspects of the system for tampering. Any safeguards anomalies will be sent to the remote site as alarms. Encrypted satellite communications will be used to transmit the data. These features allow the STAR to be operated by a small staff and will reduce the costs of safeguards monitoring by reducing the number of plant visits by inspectors.

  6. Korean safeguards experience and its perspective

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, W.K. [Korea Atomic Energy Research Inst., Daejon (Korea, Republic of). Technology Center for Nuclear Control

    1995-07-01

    This paper presents an overview of Korean safeguards implementation. The Korean safeguards program has been influenced by a wide range of international and national developments. The Joint Declaration for Denuclearization in the Korean peninsula and the recent establishment of the technology Center for Nuclear Control are the most prominent factors to have a major impact on Korean safeguards. Their influences, as well as the general status of safeguards in Korea, are described.

  7. Instrument development for safeguards measurements

    Energy Technology Data Exchange (ETDEWEB)

    Zebarth, M.; Davidson, D.; Koskelo, M.; Gardner, G. [Canberra Nuclear Products Group, Meriden, CT (United States)

    1996-12-31

    New safeguards requirements, such as those resulting from industrial reprocessing activities, makes the faster and more accurate determination of the uranium enrichment and/or the isotopic composition of plutonium essential in measuring the fissile mass. In response to these needs, Canberra has developed several improved safeguards systems in the last few years. In this paper, we will present an overview of our newest safeguards systems and the improvements they contain. The portable systems include the U-Pu InSpector, the IMCA and the JSR-14 systems. All combine automatic control of acquisition electronics and rapid analysis with an integrated software package for ease of use. The U-Pu InSpector incorporates the MGA code used by the IAEA and Euratom for plutonium analysis. The IMCA complies with IAEA PMCN and PMCG procedures for uranium analysis. With the JSR-14, we are currently developing the procedures to provide compliance with the IAEA neutron counting procedures. In addition to portable safeguards systems, Canberra has designed and installed many installed systems such as the WDAS and PSMC systems at PNC Tokai in Japan, and the large unattended neutron/gamma systems at Cogema La Hague and the Melox reprocessing facility in France. (author)

  8. Safeguards Technology Strategic Planning Pentachart

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, C. J. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2017-05-25

    Builds on earlier strategic planning workshops conducted for SGIT, SGTS, and SGCP. Many of recommendations from these workshops have been successfully implemented at the IAEA. Provide a context for evaluating new approaches for anticipated safeguards challenges of the future. Approach used by government and military to plan for an uncertain future. Uses consensus decision-making.

  9. Safeguards against Takeover after Volkswagen

    DEFF Research Database (Denmark)

    Werlauff, Erik

    2009-01-01

    The article analyses the significance of the European Court's decision on the effects of the rules on the free movement of capital on the takeover safeguards in Volkswagen AG for restrictions on the right to vote, ownership ceilings, division into A and B share classes, increased majority...

  10. Safeguards Envelope Progress FY08

    Energy Technology Data Exchange (ETDEWEB)

    Robert Bean; Richard Metcalf; Aaron Bevill

    2008-09-01

    The Safeguards Envelope Project met its milestones by creating a rudimentary safeguards envelope, proving the value of the approach on a small scale, and determining the most appropriate path forward. The Idaho Chemical Processing Plant’s large cache of reprocessing process monitoring data, dubbed UBER Data, was recovered and used in the analysis. A probabilistic Z test was used on a Markov Monte Carlo simulation of expected diversion data when compared with normal operating data. The data regarding a fully transient event in a tank was used to create a simple requirement, representative of a safeguards envelope, whose impact was a decrease in operating efficiency by 1.3% but an increase in material balance period of 26%. This approach is operator, state, and international safeguards friendly and should be applied to future reprocessing plants. Future requirements include tank-to-tank correlations in reprocessing facilities, detailed operations impact studies, simulation inclusion, automated optimization, advanced statistics analysis, and multi-attribute utility analysis.

  11. Safeguarding health care workers.

    Science.gov (United States)

    Benton, David; Williamson, Lindsey

    2014-12-01

    Editor's note: The International Council of Nurses (ICN) is a federation of more than 130 international nursing organizations. We invited the ICN to contribute a periodic column highlighting some of its initiatives to address global nursing issues. For more information, see the ICN Web site at www.icn.ch.

  12. Initial performance of the PIGMI prototype. [Pion Generator for Medical Irradiations

    Energy Technology Data Exchange (ETDEWEB)

    Stovall, J.E.

    1979-01-01

    The PIGMI (Pion Generator for Medical Irradiations) program at LASL is an accelerator development program aimed at completing the design of an accelerator suitable for use as a pion generator in a hospital-based radiotherapy program. The major thrust of the program has been the design of a 7 MeV prototype accelerator which emphasizes compactness, economy of construction, and operation and reliability. To achieve these goals the design of the prototype has exploited a number of innovations in proton linac technology. An overview of the program discussing the major innovative features of the prototype is presented. The initial operating experience is discussed and initial performance measurements are presented.

  13. IMPROVING INITIAL GENERATIONS IN PSO ALGORITHM FOR TRANSPORTATION NETWORK DESIGN PROBLEM

    Directory of Open Access Journals (Sweden)

    Navid Afkar

    2015-02-01

    Full Text Available Transportation Network Design Problem (TNDP aims to select the best project sets among a number of new projects. Recently, metaheuristic methods are applied to solve TNDP in the sense of finding better solutions sooner. PSO as a metaheuristic method is based on stochastic optimization and is a parallel revolutionary computation technique. The PSO system initializes with a number of random solutions and seeks for optimal solution by improving generations. This paper studies the behavior of PSO on account of improving initial generation and fitness value domain to find better solutions in comparison with previous attempts.

  14. Immigrant Generation and Sexual Initiation Among a Diverse Racial/Ethnic Group of Urban Youth.

    Science.gov (United States)

    Coleman-Minahan, Kate; Chavez, Marisol; Bull, Sheana

    2016-04-21

    Foreign-born youth have a lower risk of sexual initiation than native born youth, yet most research has focused on Latinos. An ethnically diverse sample of 200, 14-21 year-old youth were surveyed in Denver in 2014. We used logistic regression models to predict the odds of intentions to have sex and sexual experience, adding covariates that could account for differences in outcomes by immigrant generation. First generation youth were less likely to intend to have sex and to have sexual experience than third generation youth after controlling for racial/ethnic group, suggesting that first generation immigrants of multiple racial/ethnic groups, not just Latinos alone, have a lower risk for sexual initiation. Having a supportive community reduced the odds of sexual intentions and sexual experience. Our findings support future research using a larger sample of black, white, and Asian immigrant youth to corroborate and to explore reasons behind these associations.

  15. Safeguards instrumentation: a computer-based catalog

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  17. Simulation Enabled Safeguards Assessment Methodology

    Energy Technology Data Exchange (ETDEWEB)

    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.

  18. Development of DUPIC safeguards technology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. D.; Kang, H. Y.; Ko, W. I. [and others

    2002-05-01

    DUPIC safeguards R and D in the second phase has focused on the development of nuclear material measurement system and its operation and verification, the development of nuclear material control and accounting system, and the development of remote and unmanned containment/surveillance system. Of them, the nuclear material measurement system was authenticated from IAEA and officially used for IAEA and domestic safeguards activities in DFDF. It was also verified that the system could be used for quality control of DUPIC process. It is recognised that the diagnostic software using neural network and remote and unmanned containment/surveillance system developed here could be key technologies to go into remote and near-real time monitoring system. The result of this project will eventually contribute to similar nuclear fuel cycles like MOX and pyroprocessing facility as well as the effective implementation of DUPIC safeguards. In addition, it will be helpful to enhance international confidence build-up in the peaceful use of spent fuel material.

  19. Safeguards Envelope Progress FY10

    Energy Technology Data Exchange (ETDEWEB)

    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.

  20. Nuclear material safeguards for enrichments plants: Part 4, Gas Centrifuge Enrichment Plant: Diversion scenarios and IAEA safeguards activities: Safeguards training course

    Energy Technology Data Exchange (ETDEWEB)

    1988-10-01

    This publication is Part 4 of a safeguards training course in Nuclear Material Safeguards for enrichment plants. This part of the course deals with diversion scenarios and safeguards activities at gas centrifuge enrichment plants.

  1. FY16 Safeguards Technology Cart-Portable Mass Spectrometer Project Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, Cyril V. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Whitten, William B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-02-01

    The Oak Ridge National Laboratory project for the Next Generation Safeguards Initiative Safeguards Technology Development Subprogram has been involved in the development of a cart portable mass spectrometer based on a Thermo ITQ ion trap mass spectrometer (referred to simply as the ITQ) for the field analysis of 235U/238U ratios in UF6. A recent discovery of the project was that combining CO2 with UF6 and introducing the mixture to the mass spectrometer (MS) appeared to increase the ionization efficiency and, thus, reduce the amount of UF6 needed for an analysis while also reducing the corrosive effects of the sample. However, initial experimentation indicated that mixing parameters should be closely controlled to ensure reproducible results. To this end, a sample manifold (SM) that would ensure the precise mixing of UF6 and CO2 was designed and constructed. A number of experiments were outlined and conducted to determine optimum MS and SM conditions which would provide the most stable isotope ratio analysis. The principal objective of the project was to provide a retrofit ITQ mass spectrometer operating with a SM capable of achieving a variation in precision of less than 1% over 1 hour of sampling. This goal was achieved by project end with a variation in precision of 0.5 to 0.8% over 1 hour of sampling.

  2. Comparison of initial seed electron generation mechanisms in kinetic simulations of positive streamers

    Science.gov (United States)

    Moore, Christopher; Fierro, Andrew; Jorgenson, Roy; Biedermann, Laura; Clem, Paul; Hjalmarson, Harold; Hopkins, Matthew; Martinez, Raymond

    2016-09-01

    Positive streamer simulations typically resort to initiation by artificially seeding a small region with an initial plasma. However, in order to simulate observed variations in breakdown voltages and times in pulsed voltage experiments, a more physical model for the generation of the initial plasma/electrons is necessary. This work will investigate several models of generating the initial seed plasma in an air-filled gap with a dielectric present: a ``typical'' artificial initial plasma, ionization of the background air due to cosmic rays, field emission from the dielectric, and simulation of radiation incident on surfaces prior to applying the voltage resulting in diffuse e- and O2-densities. 2D axisymmetric PIC-DSMC simulations using a detailed e--air collision model including field-dependent detachment and photon transport will be compared to experiments of an air gap with a dielectric cylinder and a 10 GV/s applied potential. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000.

  3. Initiation processes for run-off generated debris flows in the Wenchuan earthquake area of China

    Science.gov (United States)

    Hu, W.; Dong, X. J.; Xu, Q.; Wang, G. H.; van Asch, T. W. J.; Hicher, P. Y.

    2016-01-01

    The frequency of huge debris flows greatly increased in the epicenter area of the Wenchuan earthquake. Field investigation revealed that runoff during rainstorm played a major role in generating debris flows on the loose deposits, left by coseismic debris avalanches. However, the mechanisms of these runoff-generated debris flows are not well understood due to the complexity of the initiation processes. To better understand the initiation mechanisms, we simulated and monitored the initiation process in laboratory flume test, with the help of a 3D laser scanner. We found that run-off incision caused an accumulation of material down slope. This failed as shallow slides when saturated, transforming the process into debris in a second stage. After this initial phase, the debris flow volume increased rapidly by a chain of subsequent cascading processes starting with collapses of the side walls, damming and breaching, leading to a rapid widening of the erosion channel. In terms of erosion amount, the subsequent mechanisms were much more important than the initial one. The damming and breaching were found to be the main reasons for the huge magnitude of the debris flows in the post-earthquake area. It was also found that the tested material was susceptible to excess pore pressure and liquefaction in undrained triaxial, which may be a reason for the fluidization in the flume tests.

  4. Initial Object Segmentation for Video Object Plane GenerationUsing Cellular Neural Networks

    Institute of Scientific and Technical Information of China (English)

    王慧; 杨高波; 张兆杨

    2003-01-01

    MPEG-4 is a basic tool for interactivity and manipulation of video sequences. Video object segmentation is a key issue in defining the content of any video sequence, which is often divided into two steps: initial object segmentation and object tracking. In this paper, an initial object segmentation method for video object plane(VOP) generation using color information is proposed. Based on 3 by 3 linear templates, a cellular neural network (CNN) is used to implemented object segmentation. The Experimental results arepresented to verify the efficiency and robustness of this approach.

  5. Influence of Initial Pulse Chirp on Rainbow-Like Supercontinuum Generation from Filamentation in Air

    Institute of Scientific and Technical Information of China (English)

    HAO Zuo-Qiang; ZHANG Jie; ZHANG Zhe; LU Xin; JIN Zhan; ZHONG Jia-Yong; LIU Yun-Quan; WANG Zhao-Hua

    2008-01-01

    @@ Supercontinuum (SC) generation from laser filamentation in air is found to depend strongly on the pulse duration.Rainbow-like SC generation is observed only for a pulse of appropriate negative chirp that agrees with the predictions put forward by Golubtsov et al. [Quantum Electron. 33 (2003) 525]. The conversion efficiency of an 800-nm laser light to rainbow-like SC is found to be the highest for 257fs pulses with an initial negative chirp.A larger chirp will lead to ffiamentation surviving at longer distance.

  6. A GRADUATE CERTIFICATE PROGRAM IN NUCLEAR SAFEGUARDS TECHNOLOGY.

    Energy Technology Data Exchange (ETDEWEB)

    FISHBONE, L.; SISKIND, B.; PEPPER, S.

    2005-07-10

    While there are a number of university graduate-education programs that address non-proliferation and safeguards policy issues; there are none in the United States that train students in the specific technical aspects of nuclear safeguards. Formal education of this kind is necessary to sustain the flow of technically trained individuals to diverse programs in safeguards, nonproliferation, and national security. In response to this need, the University of Missouri-Columbia, with assistance from Brookhaven National Laboratory, is initiating a Graduate Certificate Program in Nuclear Safeguards Technology: Students seeking advanced degrees in a variety of technical areas will complete a required sequence of courses in order to receive the certification. Required course work covers topics such as Nuclear Material Control and Accountability (MC&A), Physical Protection (PP); nuclear measurements, and a variety of other relevant subjects. Laboratory-based instruction will be included which will utilize the University of Missouri Research Reactor(MURR). MURR is the largest university-based research reactor and has extensive laboratory resources including a Canberra Aquila MPC&A Operational Monitoring demonstration system.

  7. IMPROVING INITIAL GENERATIONS IN PSO ALGORITHM FOR TRANSPORTATION NETWORK DESIGN PROBLEM

    OpenAIRE

    2015-01-01

    Transportation Network Design Problem (TNDP) aims to select the best project sets among a number of new projects. Recently, metaheuristic methods are applied to solve TNDP in the sense of finding better solutions sooner. PSO as a metaheuristic method is based on stochastic optimization and is a parallel revolutionary computation technique. The PSO system initializes with a number of random solutions and seeks for optimal solution by improving generations. This paper studies the be...

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

    Energy Technology Data Exchange (ETDEWEB)

    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

  9. 21 CFR 26.21 - Safeguard clause.

    Science.gov (United States)

    2010-04-01

    ... OF PHARMACEUTICAL GOOD MANUFACTURING PRACTICE REPORTS, MEDICAL DEVICE QUALITY SYSTEM AUDIT REPORTS... Specific Sector Provisions for Pharmaceutical Good Manufacturing Practices § 26.21 Safeguard clause....

  10. Optical assay technology for safeguards

    Energy Technology Data Exchange (ETDEWEB)

    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.

  11. Assess How Changes in Fuel Cycle Operation Impact Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Tobin, Stephen Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Nuclear Engineering and Nonproliferation Division; Adigun, Babatunde John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Nuclear Engineering and Nonproliferation Division; Fugate, Michael Lynn [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Nuclear Engineering and Nonproliferation Division; Trellue, Holly Renee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Nuclear Engineering and Nonproliferation Division; Sprinkle, James K. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Nuclear Engineering and Nonproliferation Division

    2016-10-31

    In this report two research topics of interest to Concepts and Approaches are investigated. The motivation of joining them into one project is that both require (1) the simulation of fuel irradiation in a reactor and (2) the transport of gamma and neutron irradiation from the fuel to safeguards detectors. In the next two subsections the merits of each of the two safeguards applications are further introduced. Given the cumulative impact of the enhancements listed above, it is not surprising that both fuel assembly design and fuel assembly irradiation optimization have improved over the past 50+ years. The purpose of the research summarized in this sub-­section is to investigate what, if any, consequence this evolution in reactor operation might have for nuclear safeguards. It is anticipated that the burnup and isotopics of the spent fuel should exhibit less variation over the decades as reactor operators irradiate each assembly to the optimum amount. In contrast, older spent fuel is anticipated to vary more in burnup and resulting isotopics for a given initial enrichment. Continuing with this thesis, modern fuel should be more uniform in composition, and thus, measured safeguards results should be easier to interpret than results from older spent fuel. With spent fuel ponds filling up, interim and long-­term storage of spent fuel will need to be addressed. Additionally after long periods of storage, spent fuel is no longer self-­protecting and as such the IAEA will categorize it as more attractive; in approximately 20 years many of the assemblies from early commercial cores will no longer be considered self-­protecting. This study will assess how more recent changes in the reactor operation could impact the interpretation of safeguards measurements.

  12. Technology development for DUPIC process safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Hong, J. S.; Kim, H. D.; Lee, Y. G.; Kang, H. Y.; Cha, H. R.; Byeon, K. H.; Park, Y. S.; Choi, H. N. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-07-01

    As the strategy for DUPIC(Direct Use of spent PWR fuel In CANDU reactor) process safeguards, the neutron detection method was introduced to account for nuclear materials in the whole DUPIC process by selectively measuring spontaneous fission neutron signals from {sup 244}Cm. DSNC was designed and manufactured to measure the account of curium in the fuel bundle and associated process samples in the DUPIC fuel cycle. The MCNP code had response profile along the length of the CANDU type fuel bundle. It was found experimentally that the output signal variation due to the overall azimuthal asymmetry was less than 0.2%. The longitudinal detection efficiency distribution at every position including both ends was kept less than 2% from the average value. Spent fuel standards almost similar to DUPIC process material were fabricated from a single spent PWR fuel rod and the performance verification of the DSNC is in progress under very high radiation environment. The results of this test will be eventually benchmarked with other sources such as code simulation, chemical analysis and gamma analysis. COREMAS-DUPIC has been developed for the accountability management of nuclear materials treated by DUPIC facility. This system is able to track the controlled nuclear materials maintaining the material inventory in near-real time and to generate the required material accountability records and reports. Concerning the containment and surveillance technology, a focused R and D effort is given to the development of unattended continuous monitoring system. Currently, the component technologies of radiation monitoring and surveillance have been established, and continued R and D efforts are given to the integration of the components into automatic safeguards diagnostics. (author).

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

    Energy Technology Data Exchange (ETDEWEB)

    Frazar, Sarah L.; Winters, Samuel T.; Kreyling, Sean J.; Joslyn, Cliff A.; West, Curtis L.; Schanfein, Mark J.; Sayre, Amanda M.

    2017-07-17

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

  14. 22 CFR 9.13 - Safeguarding.

    Science.gov (United States)

    2010-04-01

    ... persons are contained in Volume 12 of the Department's Foreign Affairs Manual. ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Safeguarding. 9.13 Section 9.13 Foreign Relations DEPARTMENT OF STATE GENERAL SECURITY INFORMATION REGULATIONS § 9.13 Safeguarding. Specific...

  15. 32 CFR 887.2 - Safeguarding certificates.

    Science.gov (United States)

    2010-07-01

    ... costly to the Air Force. To keep requests for CILs at a minimum: (a) Personnel officers will tell members of the importance of safeguarding the original certificates. (b) Persons who issue CILs will type or stamp across the lower margin “THIS IS AN IMPORTANT RECORD—SAFEGUARD IT” (if it is not printed on...

  16. A Safeguard System for Induced Pluripotent Stem Cell-Derived Rejuvenated T Cell Therapy

    Directory of Open Access Journals (Sweden)

    Miki Ando

    2015-10-01

    Full Text Available The discovery of induced pluripotent stem cells (iPSCs has created promising new avenues for therapies in regenerative medicine. However, the tumorigenic potential of undifferentiated iPSCs is a major safety concern for clinical translation. To address this issue, we demonstrated the efficacy of suicide gene therapy by introducing inducible caspase-9 (iC9 into iPSCs. Activation of iC9 with a specific chemical inducer of dimerization (CID initiates a caspase cascade that eliminates iPSCs and tumors originated from iPSCs. We introduced this iC9/CID safeguard system into a previously reported iPSC-derived, rejuvenated cytotoxic T lymphocyte (rejCTL therapy model and confirmed that we can generate rejCTLs from iPSCs expressing high levels of iC9 without disturbing antigen-specific killing activity. iC9-expressing rejCTLs exert antitumor effects in vivo. The system efficiently and safely induces apoptosis in these rejCTLs. These results unite to suggest that the iC9/CID safeguard system is a promising tool for future iPSC-mediated approaches to clinical therapy.

  17. Reduction of Error in Handoff Initiation Time Calculation for Next-Generation Wireless Systems

    Directory of Open Access Journals (Sweden)

    Debabrata Sarddar

    2010-09-01

    Full Text Available Recent research in wireless communications technologies has focused to the development of Next-generation wireless systems (NGWS which integrate various existing wireless networks technologies, each of which is optimized for some specific services such as WLANs, WiMAX, General Packet Radio Service (GPRS and Universal Mobile Telecommunications System (UMTS. The most important and challenging issue is to realize seamless handoffs with small handoff latency and packet loss to ensure the Quality of Service (QoS in NGWS. In this paper, we propose a handoff management architecture using relative signal strength of the present and neighboring base stations to calculate the handoff initiation time. To take the right decision of handoff initiation time we use mobile’s speed, handoff signaling delayinformation and also the size of the present and neighboring celland reduce the errors associated with them. The performance analysis shows that the approach ensures successful handoff and reduces call blocking probability.

  18. Next generation experiments and models for shock initiation and detonation of solid explosives

    Energy Technology Data Exchange (ETDEWEB)

    Tarver, C M

    1999-06-01

    Current phenomenological hydrodynamic reactive flow models, such as Ignition and Growth and Johnson- Tang-Forest, when normalized to embedded gauge and laser velocimetry data, have been very successful in predicting shock initiation and detonation properties of solid explosives in most scenarios. However, since these models use reaction rates based on the compression and pressure of the reacting mixture, they can not easily model situations in which the local temperature, which controls the local reaction rate, changes differently from the local pressure. With the advent of larger, faster, parallel computers, microscopic modeling of the hot spot formation processes and Arrhenius chemical kinetic reaction rates that dominate shock initiation and detonation can now be attempted. Such a modeling effort can not be successful without nanosecond or better time resolved experimental data on these processes. The experimental and modeling approaches required to build the next generation of physically realistic reactive flow models are discussed.

  19. Systems biology of coagulation initiation: kinetics of thrombin generation in resting and activated human blood.

    Directory of Open Access Journals (Sweden)

    Manash S Chatterjee

    Full Text Available Blood function defines bleeding and clotting risks and dictates approaches for clinical intervention. Independent of adding exogenous tissue factor (TF, human blood treated in vitro with corn trypsin inhibitor (CTI, to block Factor XIIa will generate thrombin after an initiation time (T(i of 1 to 2 hours (depending on donor, while activation of platelets with the GPVI-activator convulxin reduces T(i to ∼20 minutes. Since current kinetic models fail to generate thrombin in the absence of added TF, we implemented a Platelet-Plasma ODE model accounting for: the Hockin-Mann protease reaction network, thrombin-dependent display of platelet phosphatidylserine, VIIa function on activated platelets, XIIa and XIa generation and function, competitive thrombin substrates (fluorogenic detector and fibrinogen, and thrombin consumption during fibrin polymerization. The kinetic model consisting of 76 ordinary differential equations (76 species, 57 reactions, 105 kinetic parameters predicted the clotting of resting and convulxin-activated human blood as well as predicted T(i of human blood under 50 different initial conditions that titrated increasing levels of TF, Xa, Va, XIa, IXa, and VIIa. Experiments with combined anti-XI and anti-XII antibodies prevented thrombin production, demonstrating that a leak of XIIa past saturating amounts of CTI (and not "blood-borne TF" alone was responsible for in vitro initiation without added TF. Clotting was not blocked by antibodies used individually against TF, VII/VIIa, P-selectin, GPIb, protein disulfide isomerase, cathepsin G, nor blocked by the ribosome inhibitor puromycin, the Clk1 kinase inhibitor Tg003, or inhibited VIIa (VIIai. This is the first model to predict the observed behavior of CTI-treated human blood, either resting or stimulated with platelet activators. CTI-treated human blood will clot in vitro due to the combined activity of XIIa and XIa, a process enhanced by platelet activators and which proceeds

  20. International safeguards for reprocessing plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kratzer, M.; Scheinman, L.; Sievering, N.; Wonder, E.; Lipman, D.; Immerman, W.; Elliott, J.M.; Crane, F.

    1981-04-01

    Proliferation risks inherent in reprocessing show the need to employ technically effective safeguards which can detect, with a high degree of assurance and on a timely basis, the diversion of significant quantities of fissionable material. A balance must be struck between what is technically feasible and effective and what is institutionally acceptable. Purpose of this report is to examine the several technical approaches to safeguards in light of their prospective acceptability. This study defines the economic, political and institutional nature of the safeguards problem; surveys generically alternative technical approaches to international safeguards including their effectiveness and relative development; characterizes the institutional implications and uncertainties associated with the acceptance and implementation of each technical alternative; and integrates these assessments into a set of overall judgments on feasible directions for reprocessing plant safeguards systems.

  1. Safeguards technology and computer security training

    Energy Technology Data Exchange (ETDEWEB)

    Hunteman, W.J.; Zack, N.R.

    1992-01-01

    The Los Alamos National Laboratory Safeguards Systems Group provides a variety of training services to the federal government and its contractors. The US Department of Energy sponsors a Safeguards Technology Training Program at Los Alamos in which seminars are offered concerning materials accounting for nuclear safeguards, measurement control for materials accounting, and variance propagation and systems analysis. These seminars provide guidance and techniques for accounting for nuclear material, developing and quantifying quality nuclear material measurements, and assessing overall accounting system performance. The Safeguards Systems Group also provides training in computer and data security applications; i.e., a workshop and the Los Alamos Vulnerability/Risk Assessment System (LAVA), computer system security officer training, and nuclear material safeguards for managers training, which are available on request. This paper describes the purpose, content, and expected benefits of the training activities that can be applied at nuclear materials facilities or where there are computer and/or data security concerns.

  2. Safeguards technology and computer security training

    Energy Technology Data Exchange (ETDEWEB)

    Hunteman, W.J.; Zack, N.R.

    1992-09-01

    The Los Alamos National Laboratory Safeguards Systems Group provides a variety of training services to the federal government and its contractors. The US Department of Energy sponsors a Safeguards Technology Training Program at Los Alamos in which seminars are offered concerning materials accounting for nuclear safeguards, measurement control for materials accounting, and variance propagation and systems analysis. These seminars provide guidance and techniques for accounting for nuclear material, developing and quantifying quality nuclear material measurements, and assessing overall accounting system performance. The Safeguards Systems Group also provides training in computer and data security applications; i.e., a workshop and the Los Alamos Vulnerability/Risk Assessment System (LAVA), computer system security officer training, and nuclear material safeguards for managers training, which are available on request. This paper describes the purpose, content, and expected benefits of the training activities that can be applied at nuclear materials facilities or where there are computer and/or data security concerns.

  3. Safeguards and retrievability from waste forms

    Energy Technology Data Exchange (ETDEWEB)

    Danker, W.

    1996-05-01

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

  4. Wave generation by fracture initiation and propagation in geomaterials with internal rotations

    Science.gov (United States)

    Esin, Maxim; Pasternak, Elena; Dyskin, Arcady; Xu, Yuan

    2016-04-01

    Crack or fracture initiation and propagation in geomaterials are sources of waves and is important in both stability and fracture (e.g. hydraulic fracture) monitoring. Many geomaterials consist of particles or other constituents capable of rotating with respect to each other, either due to the absence of the binder phase (fragmented materials) or due to extensive damage of the cement between the constituents inflicted by previous loading. In investigating the wave generated in fracturing it is important to distinguish between the cases when the fracture is instantaneously initiated to its full length or propagates from a smaller initial crack. We show by direct physical experiments and discrete element modelling of 2D arrangements of unbonded disks that under compressive load fractures are initiated instantaneously as a result of the material instability and localisation. Such fractures generate waves as a single impulse impact. When the fractures propagate, they produce a sequence of impulses associated with the propagation steps. This manifests itself as acoustic (microseismic) emission whose temporal pattern contains the information of the fracture geometry, such as fractal dimension of the fracture. The description of this process requires formulating criteria of crack growth capable of taking into account the internal rotations. We developed an analytical solution based on the Cosserat continuum where each point of body has three translational and three rotational degrees of freedom. When the Cosserat characteristic lengths are comparable with the grain sizes, the simplified equations of small-scale Cosserat continuum can be used. We established that the order of singularity of the main asymptotic term for moment stress is higher than the order of singularity for conventional stress. Therefore, the mutual rotation of particles and related bending and/or twisting of the bonds between the particles represent an unconventional mechanism of crack propagation.

  5. Runoff-generated debris flows: observations and modeling of surge initiation, magnitude, and frequency

    Science.gov (United States)

    Kean, Jason W.; McCoy, Scott W.; Tucker, Gregory E.; Staley, Dennis M.; Coe, Jeffrey A.

    2013-01-01

    Runoff during intense rainstorms plays a major role in generating debris flows in many alpine areas and burned steeplands. Yet compared to debris flow initiation from shallow landslides, the mechanics by which runoff generates a debris flow are less understood. To better understand debris flow initiation by surface water runoff, we monitored flow stage and rainfall associated with debris flows in the headwaters of two small catchments: a bedrock-dominated alpine basin in central Colorado (0.06 km2) and a recently burned area in southern California (0.01 km2). We also obtained video footage of debris flow initiation and flow dynamics from three cameras at the Colorado site. Stage observations at both sites display distinct patterns in debris flow surge characteristics relative to rainfall intensity (I). We observe small, quasiperiodic surges at low I; large, quasiperiodic surges at intermediate I; and a single large surge followed by small-amplitude fluctuations about a more steady high flow at high I. Video observations of surge formation lead us to the hypothesis that these flow patterns are controlled by upstream variations in channel slope, in which low-gradient sections act as “sediment capacitors,” temporarily storing incoming bed load transported by water flow and periodically releasing the accumulated sediment as a debris flow surge. To explore this hypothesis, we develop a simple one-dimensional morphodynamic model of a sediment capacitor that consists of a system of coupled equations for water flow, bed load transport, slope stability, and mass flow. This model reproduces the essential patterns in surge magnitude and frequency with rainfall intensity observed at the two field sites and provides a new framework for predicting the runoff threshold for debris flow initiation in a burned or alpine setting.

  6. KaTie: for parton-level event generation with k_T-dependent initial states

    CERN Document Server

    van Hameren, A

    2016-01-01

    KaTie is a parton-level event generator for hadron scattering processes that can deal with partonic initial-state momenta with an explicit transverse momentum dependence causing them to be space-like. Provided with the necessary transverse momentum dependent parton density functions, it calculates the off-shell matrix elements and performs the phase space importance sampling to produce weighted events, for example in the Les Houches Event File format. It can deal with arbitrary processes within the Standard Model, for up to four final-state particles and beyond. Furthermore, it can produce events for single-parton scattering as well as for multi-parton scattering.

  7. Computation of the initially unknown boundaries of flow fields generated by local exhaust hoods.

    Science.gov (United States)

    Anastas, M Y

    1991-09-01

    Local exhaust hoods are important in controlling contaminants in the workplace. To predict hood effectiveness, it is important to have knowledge of the airflow field that it generates. Currently, there are theoretical models adequate for predicting the flow fields of hoods with flanged openings. These models are solutions of Laplace's equation in terms of the velocity potential. Comparison of experimental and theoretical values of air velocities show good agreement. With the exception of the plain slot, no such models are available for plain hoods or other hoods with complex geometries. This paper explores the feasibility of approximating the equal air velocity contours for any local exhaust hood by assuming that these contours are also equipotential contours. A slot configuration, for which an analytical model is available, was used to evaluate the accuracy of the assumption. Starting with a good approximation for the 15% velocity contour, three other boundaries were generated. The procedure used in generating boundaries after the initial one involved solution of Laplace's equation, assuming constant potential along the boundary and adjustment of boundary location on the basis of differences between the calculated value of the normal derivative of the velocity potential at a point on the boundary and the specified value (15%). The next-to-last boundary generated by the procedure exhibited an oscillation in the values of the normal derivative, which was detrimental to the desired solution. Possible causes for this oscillation and possible refinements in the procedure are discussed.

  8. Computation of the initially unknown boundaries of flow fields generated by local exhaust hoods

    Energy Technology Data Exchange (ETDEWEB)

    Anastas, M.Y. (National Institute for Occupational Safety and Health, Cincinnati OH (United States))

    1991-09-01

    Local exhaust hoods are important in controlling contaminants in the workplace. To predict hood effectiveness, it is important to have knowledge of the airflow field that it generates. Currently, there are theoretical models adequate for predicting the flow fields of hoods with flanged openings. These models are solutions of Laplace's equation in terms of the velocity potential. Comparison of experimental and theoretical values of air velocities show good agreement. With the exception of the plain slot, no such models are available for plain hoods or other hoods with complex geometries. This paper explores the feasibility of approximating the equal air velocity contours for any local exhaust hood by assuming that these contours are also equipotential contours. A slot configuration, for which an analytical model is available, was used to evaluate the accuracy of the assumption. Starting with a good approximation for the 15% velocity contour, three other boundaries were generated. The procedure used in generating boundaries after the initial one involved solution of Laplace's equation, assuming constant potential along the boundary and adjustment of boundary location on the basis of differences between the calculated value of the normal derivative of the velocity potential at a point on the boundary and the specified value (15%). The next-to-last boundary generated by the procedure exhibited an oscillation in the values of the normal derivative, which was detrimental to the desired solution. Possible causes for this oscillation and possible refinements in the procedure are discussed.

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

    Energy Technology Data Exchange (ETDEWEB)

    Durbin, Samuel G. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lindgren, Eric Richard [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jones, Robert [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Ketusky, Edward [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); England, Jeffrey [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Scherer, Carolynn [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Miller, Michael. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rauch, Eric [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scaglione, John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dunn, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-05-01

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

  10. Semiautomatic transfer function initialization for abdominal visualization using self-generating hierarchical radial basis function networks.

    Science.gov (United States)

    Selver, M Alper; Güzeliş, Cüneyt

    2009-01-01

    As being a tool that assigns optical parameters used in interactive visualization, Transfer Functions (TF) have important effects on the quality of volume rendered medical images. Unfortunately, finding accurate TFs is a tedious and time consuming task because of the trade off between using extensive search spaces and fulfilling the physician's expectations with interactive data exploration tools and interfaces. By addressing this problem, we introduce a semi-automatic method for initial generation of TFs. The proposed method uses a Self Generating Hierarchical Radial Basis Function Network to determine the lobes of a Volume Histogram Stack (VHS) which is introduced as a new domain by aligning the histograms of slices of a image series. The new self generating hierarchical design strategy allows the recognition of suppressed lobes corresponding to suppressed tissues and representation of the overlapping regions which are parts of the lobes but can not be represented by the Gaussian bases in VHS. Moreover, approximation with a minimum set of basis functions provides the possibility of selecting and adjusting suitable units to optimize the TF. Applications on different CT and MR data sets show enhanced rendering quality and reduced optimization time in abdominal studies.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    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

  12. Development of DUPIC safeguards neutron counter

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Gil; Cha, Hong Ryul; Kim, Ho Dong; Hong, Jong Sook; Kang, Hee Young

    1999-08-01

    KAERI, in cooperation with LANL, developed DSNC (DUPIC Safeguards Neutron Counter) for safeguards implementing on DUPIC process which is under development by KAERI for direct use of spent PWR fuel in CANDU reactors. DSNC is a well-type neutron coincidence counter with substantial shielding to protect system from high gamma radiation of spent fuel. General development procedures in terms of design, manufacturing, fabrication, cold and hot test, performance test for DSNC authentication by KAERI-IAEA-LANL are described in this report. It is expected that the techniques related DSNC development and associated neutron detection and evaluation method could be applied for safeguards improvement. (Author). 20 refs., 16 tabs. 98 figs.

  13. Development of DUPIC safeguards neutron counter

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Gil; Cha, Hong Ryul; Kim, Ho Dong; Hong, Jong Sook; Kang, Hee Young

    1999-08-01

    KAERI, in cooperation with LANL, developed DSNC (DUPIC Safeguards Neutron Counter) for safeguards implementing on DUPIC process which is under development by KAERI for direct use of spent PWR fuel in CANDU reactors. DSNC is a well-type neutron coincidence counter with substantial shielding to protect system from high gamma radiation of spent fuel. General development procedures in terms of design, manufacturing, fabrication, cold and hot test, performance test for DSNC authentication by KAERI-IAEA-LANL are described in this report. It is expected that the techniques related DSNC development and associated neutron detection and evaluation method could be applied for safeguards improvement. (Author). 20 refs., 16 tabs. 98 figs.

  14. IAEA Safeguards: Past, Present, and Future

    Energy Technology Data Exchange (ETDEWEB)

    Santi, Peter A. [Los Alamos National Laboratory; Hypes, Philip A. [Los Alamos National Laboratory

    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.

  15. A status of installation and operational experience of safeguards equipment for DFDF safeguards implementation

    Energy Technology Data Exchange (ETDEWEB)

    Cha, H. Y.; Ko, W. I.; Song, D. Y.; Kang, H. Y.; Lee, S. Y.; Kim, H. D. [KAERI, Taejon (Korea, Republic of)

    2001-05-01

    DUPIC Fuel Fabrication Facility (DFDF) fabricates CANDU-type fuel directly out of spent PWR fuel material with no alternation of composition of spent fuel throughout the whole process. DFDF belong to 'Other Facilities' among the 13 facilities types under IAEA safeguards criteria and is a unique facility type in the world because the DUPIC process has no separation activity of fission products from process materials. For the IAEA safeguards implementation of DFDF, facility was developed the DUPIC Safeguards Neutron Counter (DSNC) and DUPIC Safeguards Neutron Monitor(DSNM) for accountancy of SNM in DUPIC fuel and a monitoring of DUPIC fuel, respectively. These instruments were used jointly between IAEA and facility operator authorized by IAEA and installed at DFDF. And facility operator and IAEA also installed and operated the surveillance systems for DFDF surveillance each other. This paper describes the status of installation and operational experience of safeguards equipment for DFDF safeguards implementation.

  16. A technique for generating consistent ice sheet initial conditions for coupled ice-sheet/climate models

    Directory of Open Access Journals (Sweden)

    J. G. Fyke

    2013-04-01

    Full Text Available A new technique for generating ice sheet preindustrial 1850 initial conditions for coupled ice-sheet/climate models is developed and demonstrated over the Greenland Ice Sheet using the Community Earth System Model (CESM. Paleoclimate end-member simulations and ice core data are used to derive continuous surface mass balance fields which are used to force a long transient ice sheet model simulation. The procedure accounts for the evolution of climate through the last glacial period and converges to a simulated preindustrial 1850 ice sheet that is geometrically and thermodynamically consistent with the 1850 preindustrial simulated CESM state, yet contains a transient memory of past climate that compares well to observations and independent model studies. This allows future coupled ice-sheet/climate projections of climate change that include ice sheets to integrate the effect of past climate conditions on the state of the Greenland Ice Sheet, while maintaining system-wide continuity between past and future climate simulations.

  17. SAFEGUARD: An Assured Safety Net Technology for UAS

    Science.gov (United States)

    Dill, Evan T.; Young, Steven D.; Hayhurst, Kelly J.

    2016-01-01

    As demands increase to use unmanned aircraft systems (UAS) for a broad spectrum of commercial applications, regulatory authorities are examining how to safely integrate them without loss of safety or major disruption to existing airspace operations. This work addresses the development of the Safeguard system as an assured safety net technology for UAS. The Safeguard system monitors and enforces conformance to a set of rules defined prior to flight (e.g., geospatial stay-out or stay-in regions, speed limits, altitude limits). Safeguard operates independently of the UAS autopilot and is strategically designed in a way that can be realized by a small set of verifiable functions to simplify compliance with regulatory standards for commercial aircraft. A framework is described that decouples the system from any other devices on the UAS as well as introduces complementary positioning source(s) for applications that require integrity and availability beyond what the Global Positioning System (GPS) can provide. Additionally, the high level logic embedded within the software is presented, as well as the steps being taken toward verification and validation (V&V) of proper functionality. Next, an initial prototype implementation of the described system is disclosed. Lastly, future work including development, testing, and system V&V is summarized.

  18. Determining information management needs for enhanced international safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Badalamente, R.V. [Pacific Northwest Lab., Richland, WA (United States); DeLand, S.M. [Sandia National Labs., Albuquerque, NM (United States); Whiteson, R. [Los Alamos National Lab., NM (United States); Anzelon, G. [Lawrence Livermore National Lab., CA (United States)

    1994-08-01

    The Safeguards Information Management System initiative is a program of the Department of Energy`s (DOE) Office of Arms Control and Nonproliferation aimed at supporting the International Atomic Energy Agency`s (IAEA) efforts to strengthen safeguards through the enhancement of information management capabilities. The DOE hopes to provide the IAEA with the ability to correlate and analyze data from existing and new sources of information, including publicly available information, information on imports and exports, design information, environmental monitoring data, and non-safeguards information. The first step in this effort is to identify and define IAEA requirements. In support of this, we have created a users` requirements document based on interviews with IAEA staff that describes the information management needs of the end user projected by the IAEA, including needs for storage, retrieval, analysis, communication, and visualization of data. Also included are characteristics of the end user and attributes of the current environment. This paper describes our efforts to obtain the required information. We discuss how to accurately represent user needs and involve users for an international organization with a multi-cultural user population. We describe our approach, our experience in setting up and conducting the interviews and brainstorming sessions, and a brief discussion of what we learned.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Harris, J. R. [Colorado State Univ., Fort Collins, CO (United States) Dept. of Electrical and Computer Engineering.; Lewellen, J. W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Poole, B. R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    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.

  1. The Concept of Goals-Driven Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    R. Wigeland; T Bjornard; B. Castle

    2009-02-01

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

  2. Safeguards Workforce Repatriation, Retention and Utilization

    Energy Technology Data Exchange (ETDEWEB)

    Gallucci, Nicholas [Brookhaven National Lab. (BNL), Upton, NY (United States); Poe, Sarah [Brookhaven National Lab. (BNL), Upton, NY (United States)

    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.

  3. Long-Term Weight Change after Initiating Second-Generation Antidepressants

    Directory of Open Access Journals (Sweden)

    David Arterburn

    2016-04-01

    Full Text Available (1 Objective: To examine the relationship between the choice of second-generation antidepressant drug treatment and long-term weight change; (2 Methods: We conducted a retrospective cohort study to investigate the relationship between choice of antidepressant medication and weight change at two years among adult patients with a new antidepressant treatment episode between January, 2006 and October, 2009 in a large health system in Washington State. Medication use, encounters, diagnoses, height, and weight were collected from electronic databases. We modeled change in weight and BMI at two years after initiation of treatment using inverse probability weighted linear regression models that adjusted for potential confounders. Fluoxetine was the reference treatment; (3 Results: In intent-to-treat analyses, non-smokers who initiated bupropion treatment on average lost 7.1 lbs compared to fluoxetine users who were non-smokers (95% CI: −11.3, −2.8; p-value < 0.01; smokers who initiated bupropion treatment gained on average 2.2 lbs compared to fluoxetine users who were smokers (95% CI: −2.3, 6.8; p-value = 0.33. Changes in weight associated with all other antidepressant medications were not significantly different than fluoxetine, except for sertraline users, who gained an average of 5.9 lbs compared to fluoxetine users (95% CI: 0.8, 10.9; p-value = 0.02; (4 Conclusion: Antidepressant drug therapy is significantly associated with long-term weight change at two years. Bupropion may be considered as the first-line drug of choice for overweight and obese patients unless there are other existing contraindications.

  4. Harmonization of initial estimates of shale gas life cycle greenhouse gas emissions for electric power generation.

    Science.gov (United States)

    Heath, Garvin A; O'Donoughue, Patrick; Arent, Douglas J; Bazilian, Morgan

    2014-08-05

    Recent technological advances in the recovery of unconventional natural gas, particularly shale gas, have served to dramatically increase domestic production and reserve estimates for the United States and internationally. This trend has led to lowered prices and increased scrutiny on production practices. Questions have been raised as to how greenhouse gas (GHG) emissions from the life cycle of shale gas production and use compares with that of conventionally produced natural gas or other fuel sources such as coal. Recent literature has come to different conclusions on this point, largely due to differing assumptions, comparison baselines, and system boundaries. Through a meta-analytical procedure we call harmonization, we develop robust, analytically consistent, and updated comparisons of estimates of life cycle GHG emissions for electricity produced from shale gas, conventionally produced natural gas, and coal. On a per-unit electrical output basis, harmonization reveals that median estimates of GHG emissions from shale gas-generated electricity are similar to those for conventional natural gas, with both approximately half that of the central tendency of coal. Sensitivity analysis on the harmonized estimates indicates that assumptions regarding liquids unloading and estimated ultimate recovery (EUR) of wells have the greatest influence on life cycle GHG emissions, whereby shale gas life cycle GHG emissions could approach the range of best-performing coal-fired generation under certain scenarios. Despite clarification of published estimates through harmonization, these initial assessments should be confirmed through methane emissions measurements at components and in the atmosphere and through better characterization of EUR and practices.

  5. Foundations on Generation of Relationships Between Classes Based on Initial Business Knowledge

    Science.gov (United States)

    Nikiforova, Oksana; Pavlova, Natalya

    This chapter focuses on the development of the main component of platform independent model (PIM) of Model Driven Architecture, e.g., class diagram defined in Unified Modeling Language (UML), which has necessary details for transformation into platform specific model (PSM). It is important to formulate core principles of development of well-structured class diagram at a conceptual level, using knowledge of the problem domain, which consists of two interrelated models of system aspects - business processes and concept presentation. Definition of relationships of classes is important for PSM generation; therefore, the research on how it could be defined is performed. The hypothesis that it is possible to derive a class structure from initial business information is adduced. Information about the problem domain is presented in the form of two-hemisphere model that describes two interrelated parts of the most important aspects of a system, namely business process and concept models. These models serve as a source model for class diagram receiving. Capacity for the class diagram generation, based on the two-hemisphere model, is represented by a collection of graph transformations and illustrated with examples, where definition of different kinds of relationships (namely aggregation, dependency, generalization) is displayed.

  6. Safeguards culture on 3S interfaces

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Yon Hong; Lee, Na Young; Han, Jae-Jun [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2015-05-15

    But when proliferation of nuclear weapon does happen due to violation of safeguards, the impact would be no smaller compare to the others. Therefore, it should be treated as important as the others. In fact, safeguards culture wasn't issued first time in this paper. However, the past safeguards culture only meant the conception based upon specific purpose. But it should be generalized to extend the target and scope enough to cover any possible misbehavior. The aforementioned NMAC will be a quite meaningful research subject not just for strengthening safeguards culture, but also for the security and safeguards interface. Recognizing the importance of this, the , IAEA has developed a set of technical criteria based on the IAEA implementing guide entitled Use of Nuclear Material Accounting and Control for Nuclear Security Purposes at Facilities(in publication) and a methodology to assess the use of a facility's NMAC system for nuclear security. IAEA has established an expert team to continuously evaluate and apply NMAC systems going forward. In the process of such efforts, the ROK should work to select and apply appropriate features so as to build a more improved safeguards culture and to determine the best practice.

  7. 78 FR 28835 - Salton Sea Power Generation Company; Supplemental Notice That Initial Market-Based Rate Filing...

    Science.gov (United States)

    2013-05-16

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Salton Sea Power Generation Company; Supplemental Notice That Initial Market... in the above-referenced proceeding of Salton Sea Power Generation Company's application for market...

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

    Energy Technology Data Exchange (ETDEWEB)

    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

  9. Building a Successful Machine Safeguarding Program

    Energy Technology Data Exchange (ETDEWEB)

    McConnell, S

    2003-03-06

    Safeguarding hazards associated with machines is a goal common to all health and safety professionals. Whether the individual is new to the safety field or has held associated responsibilities for a period of time, safeguarding personnel who work with or around machine tools and equipment should be considered an important aspect of the job. Although significant progress has been made in terms of safeguarding machines since the era prior to the organized safety movement, companies continue to be cited by the Occupational Safety and Health Administration (OSHA) and workers continue to be injured, even killed by machine tools and equipment. In the early 1900s, it was common practice to operate transmission machinery (gears, belts, pulleys, shafting, etc.) completely unguarded. At that time, the countersunk set screw used on shafting had not been invented and projecting set screws were involved in many horrific accidents. Manufacturers built machines with little regard for worker safety. Workers were killed or seriously injured before definitive actions were taken to improve safety in the workplace. Many states adopted legislation aimed at requiring machine guarding and improved injury reduction. The first patent for a machine safeguard was issued in 1868 for a mechanical interlock. Other patents followed. As methods for safeguarding machinery and tools were developed, standards were written and programs were set up to monitor factories for compliance. Many of those standards continue to govern how we protect workers today. It is common to see machine tools built in the forties, fifties and sixties being used in machine shops today. In terms of safeguarding, these machines may be considered poorly designed, improperly safeguarded or simply unguarded. In addition to the potential threat of an OSHA citation, these conditions expose the operator to serious hazards that must be addressed. The safety professional can help line management determine workable solutions for

  10. IAEA Safeguards: Cost/benefit analysis of commercial satellite imagery

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Christer [SSC Satellitbild AB, Kiruna (Sweden)

    1999-03-01

    A major milestone in the efforts to strengthen the Safeguards System was reached in May 1997 when the Board of Governors approved a `Model Protocol Additional to Safeguards Agreements`. The Protocol provides the legal basis necessary to enhance the Agency`s ability to detect undeclared nuclear material and activities by using information available from open sources to complement the declarations made by Member States. Commercially available high-resolution satellite data has emerged as one potential complementary open information source to support the traditional and extended Safeguard activities of IAEA. This document constitutes a first report from SSC Satellitbild giving the Agency tentative and initial estimates of the potential cost and time-savings possible with the new proposed technology. The initial cost/benefit simulation will be further finalised in the following `Implementation Blueprint` study. The general foundation and starting point for the cost/benefit calculation is to simulate a new efficient and relatively small `imagery unit` within the IAEA, capable of performing advanced image processing as a tool for various safeguards tasks. The image processing capacity is suggested to be task- and interpretation-oriented. The study was performed over a period of 1,5 weeks in late 1998, and is based upon interviews of IAEA staff, reviews of existing IAEA documentation as well as from SSC Satellitbild`s long-standing experience of satellite imagery and field missions. The cost/benefit analysis is based on a spreadsheet simulation of five potential applications of commercial satellite imagery: Reference information; Confirmation of Agency acquired and Member State supplied data; Change detection and on-going monitoring; Assessing open source information available to the Agency; Detecting undeclared activities and undeclared sites. The study confirms that the proposed concept of a relatively small `imagery unit` using high-resolution data will be a sound and

  11. Controlled synthesis of biodegradable lactide polymers and copolymers using novel in situ generated or single-site stereoselective polymerization initiators.

    Science.gov (United States)

    Zhong, Zhiyuan; Dijkstra, Pieter J; Feijen, Jan

    2004-01-01

    Polylactides and their copolymers are key biodegradable polymers used widely in biomedical, pharmaceutical and ecological applications. The development of synthetic pathways and catalyst/initiator systems to produce pre-designed polylactides, as well as the fundamental understanding of the polymerization reactions, has continuously been an important topic. Here, we will address the recent advances in the ring-opening polymerization of lactides, with an emphasis on the highly versatile in situ generated initiator systems and single-site stereoselective initiators. The in situ generated initiators including in situ formed yttrium, calcium and zinc alkoxides all have been shown to bring about a rapid and living polymerization of lactides under mild conditions, which facilitated the preparation of a variety of advanced lactide-based biomaterials. For example, well-defined di- and tri-block copolymers consisting of hydrophilic poly(ethylene glycol) blocks and hydrophobic polyester blocks, which form novel biodegradable polymersomes or biodegradable thermosensitive hydrogels, have been prepared. In the past few years, significant progress has also been made in the area of stereoselective polymerization of lactides. This new generation of initiators has enabled the production of polylactide materials with novel microstructures and/or properties, such as heterotactic (--RRSSRRSSRRSS--) polylactide, crystalline syndiotactic (--RSRSRSRSRSRS--) polylactide and isotactic stereoblock (--Rn Sn Rn Sn--) polylactide, exhibiting a high melting temperature. The recently developed polymerizations using in situ generated initiators and stereoselective polymerizations have no doubt opened a brand-new avenue for the design and exploration of polylactides and their copolymers.

  12. European initiative for a new generation of satellite navigation services - Galileo; Die europaeische Initiative fuer eine neue Generation von Satellitennavigationsdiensten - GALILEO

    Energy Technology Data Exchange (ETDEWEB)

    Tusk, S. [Bundesministerium fuer Verkehr, Bau- und Wohnungswesen, Berlin (Germany)

    2000-07-01

    The currently existing satellite navigation systems GPS and GLONASS have impressively demonstrated the possibilities of using satellite navigation; there are numerous civilian applications worldwide. However, both systems are controlled nationally and designed for military applications and cannot meet the basic requirements in terms of continuity, integrity and precision required for safety-relevant and sovereign applications. Therefore, the Federal Republic of Germany supports the activities initiated by the EU, which consist of - developing, first of all, technical augmentations to make the existing systems useable without delay also for applications involving exacting requirements (GNSS 1, EGNOS), - carrying out in parallel the definition phase for the development of a global, civilian satellite navigation system (GNSS 2, Galileo). (orig.) [German] Die bisher existierenden Satellitennavigationssysteme GPS und GLONASS haben die Einsatzmoeglichkeiten der Satellitennavigation in eindrucksvoller Weise demonstriert; weltweit haben sich zahlreiche zivile Anwendungen ergeben. Jedoch sind beide Systeme national kontrolliert, auf militaerische Anwendungen zugeschnitten und koennen die fuer sicherheitsrelevante und hoheitliche Anwendungen notwendigen Grundanforderungen nach Kontinuitaet, Integritaet und Praezision nicht garantieren. Daher unterstuetzt die Bundesrepublik Deutschland die von der EU eingeleiteten Aktivitaeten, die daraus bestehen - zunaechst die bestehenden Systeme durch technische Ergaenzungen kurzfristig auch fuer hohe Anforderungen stellende Anwendungen nutzbar zu machen (GNSS 1, EGNOS) - parallel dazu die Definitionsphase zum Aufbau eines globalen zivilen Satellitennavigationssystems (GNSS 2, GALILEO) durchzufuehren. (orig.)

  13. Integrated international safeguards concepts for fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Gutmacher, R.G.; Markin, J.T.; Shipley, J.P.; Whitty, W.J.; Camp, A.L.; Cameron, C.P.; Bleck, M.E.; Ellwein, L.B.

    1981-12-01

    This report is the fourth in a series of efforts by the Los Alamos National Laboratory and Sandia National Laboratories, Albuquerque, to identify problems and propose solutions for international safeguarding of light-water reactor spent-fuel reprocessing plants. Problem areas for international safeguards were identified in a previous Problem Statement (LA-7551-MS/SAND79-0108). Accounting concepts that could be verified internationally were presented in a subsequent study (LA-8042). Concepts for containment/surveillance were presented, conceptual designs were developed, and the effectiveness of these designs was evaluated in a companion study (SAND80-0160). The report discusses the coordination of nuclear materials accounting and containment/surveillance concepts in an effort to define an effective integrated safeguards system. The Allied-General Nuclear Services fuels reprocessing plant at Barnwell, South Carolina, was used as the reference facility.

  14. The evolution of information-driven safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Budlong-sylvester, Kory W [Los Alamos National Laboratory; Pilat, Joseph F [Los Alamos National Laboratory

    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.

  15. Reactor monitoring and safeguards using antineutrino detectors

    CERN Document Server

    Bowden, N S

    2008-01-01

    Nuclear reactors have served as the antineutrino 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. Measurements made with antineutrino detectors could therefore offer an alternative means for verifying the power history and fissile inventory of a reactors, as part of International Atomic Energy Agency (IAEA) and other reactor safeguards regimes. Several efforts to develop this monitoring technique are underway across the globe.

  16. Investing in Interagency Training to Safeguard Children: An Act of Faith or an Act of Reason?

    Science.gov (United States)

    Charles, Marian; Horwath, Jan

    2009-01-01

    Since the 1970s, interagency training has been considered crucial for developing effective collaborative practice, initially in relation to child protection, and latterly, to safeguarding children's welfare. Charting the history of interagency training in England, this paper aims to demonstrate how, despite limited attention being paid to its…

  17. Coupling a Transient Solvent Extraction Module with the Separations and Safeguards Performance Model

    Energy Technology Data Exchange (ETDEWEB)

    de Almeida, Valmor F [ORNL; Birdwell Jr, Joseph F [ORNL; DePaoli, David W [ORNL; Gauld, Ian C [ORNL

    2009-10-01

    A past difficulty in safeguards design for reprocessing plants is that no code existed for analysis and evaluation of the design. A number of codes have been developed in the past, 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 SSPM Separations and Safeguards Performance Model, 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 much more robust transient separations and safeguards model for evaluating safeguards system design. This coupling and the 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    DePaoli, David W. (Oak Ridge National Laboratory, Oak Ridge, TN); Birdwell, Joseph F. (Oak Ridge National Laboratory, Oak Ridge, TN); Gauld, Ian C. (Oak Ridge National Laboratory, Oak Ridge, TN); Cipiti, Benjamin B.; de Almeida, Valmor F. (Oak Ridge National Laboratory, Oak Ridge, TN)

    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.

  19. Analysis of safeguards information treatment system at the facility level

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Doo; Song, Dae Yong; Kwack, Eun Ho

    2000-12-01

    Safeguards Information Treatment System(SITS) at the facility level is required to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, the analysis of information, which the SITS treats, and operation environment of SITS including the review of the relationship between safeguards information are described. SITS will be developed to cover the different accounting procedures and methods applied at the various facilities under IAEA safeguards.

  20. A distinct translation initiation mechanism generates cryptic peptides for immune surveillance.

    Directory of Open Access Journals (Sweden)

    Shelley R Starck

    Full Text Available MHC class I molecules present a comprehensive mixture of peptides on the cell surface for immune surveillance. The peptides represent the intracellular protein milieu produced by translation of endogenous mRNAs. Unexpectedly, the peptides are encoded not only in conventional AUG initiated translational reading frames but also in alternative cryptic reading frames. Here, we analyzed how ribosomes recognize and use cryptic initiation codons in the mRNA. We find that translation initiation complexes assemble at non-AUG codons but differ from canonical AUG initiation in response to specific inhibitors acting within the peptidyl transferase and decoding centers of the ribosome. Thus, cryptic translation at non-AUG start codons can utilize a distinct initiation mechanism which could be differentially regulated to provide peptides for immune surveillance.

  1. Safeguards instruments for Large-Scale Reprocessing Plants

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A. [Los Alamos National Lab., NM (United States); Case, R.S.; Sonnier, C. [Sandia National Labs., Albuquerque, NM (United States)

    1993-06-01

    Between 1987 and 1992 a multi-national forum known as LASCAR (Large Scale Reprocessing Plant Safeguards) met to assist the IAEA in development of effective and efficient safeguards for large-scale reprocessing plants. The US provided considerable input for safeguards approaches and instrumentation. This paper reviews and updates instrumentation of importance in measuring plutonium and uranium in these facilities.

  2. 78 FR 56690 - PE Hydro Generation, LLC; Supplemental Notice That Initial Market-Based Rate Filing Includes...

    Science.gov (United States)

    2013-09-13

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission PE Hydro Generation, LLC; Supplemental Notice That Initial Market-Based Rate Filing Includes Request for Blanket Section 204 Authorization This is a supplemental notice in the above-referenced proceeding, of PE...

  3. The potential use of domestic safeguards interior monitors in International Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Williams, J.D.; Dupree, S.A. [Sandia National Labs., Albuquerque, NM (United States); Sonnier, C.S. [Jupiter Corp., Albuquerque, NM (United States)

    1998-08-01

    An important future element of International Safeguards instrumentation is expected to be the merging of containment/surveillance and nondestructive assay equipment with domestic physical protection equipment into integrated systems, coupled with remote monitoring. Instrumentation would include interior monitoring and assessment and entry/exit monitoring. Of particular importance is the application of interior monitors in spaces of declared inactivity; for example, in nuclear material storage locations that are entered infrequently. The use of modern interior monitors in International Safeguards offers potential for improving effectiveness and efficiency. Within the context of increased cooperation, one can readily envision increased interaction between International Safeguards and Domestic Safeguards, including increased joint use of State System of Accounting and Control data.

  4. Safeguards performance model for evaluation of potential safeguards strategies applied to pyroprocessing facilities

    Energy Technology Data Exchange (ETDEWEB)

    Riley, T.R., E-mail: riletony@isu.edu; Pope, C.L.; Benedict, R.W.

    2016-05-15

    Highlights: • A model was created for simulating safeguards strategies for a pyroprocessing facility. • The model is flexible and simulates process monitoring during steady state operations. • A sensitivity study revealed input spent fuel and storage mass measures most limiting. - Abstract: Electrochemical reprocessing has been proposed as a spent fuel disposition technique. If implemented on a commercial scale, traditional safeguards approaches used to satisfy IAEA requirements may be insufficient. To aid in testing safeguard strategies, a new tool was developed: the Pyroprocessing Safeguards Performance Model, a MATLAB/Simulink simulation of plant operations capable of calculating inventory differences for a specified balance period as well as sensitivity studies of detection measurements. This paper discusses the development of the model and a measurement uncertainty study performed using the model.

  5. The integration of process monitoring for safeguards.

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin B.; Zinaman, Owen R.

    2010-09-01

    The Separations and Safeguards Performance Model is a reprocessing plant model that has been developed for safeguards analyses of future plant designs. The model has been modified to integrate bulk process monitoring data with traditional plutonium inventory balances to evaluate potential advanced safeguards systems. Taking advantage of the wealth of operator data such as flow rates and mass balances of bulk material, the timeliness of detection of material loss was shown to improve considerably. Four diversion cases were tested including both abrupt and protracted diversions at early and late times in the run. The first three cases indicated alarms before half of a significant quantity of material was removed. The buildup of error over time prevented detection in the case of a protracted diversion late in the run. Some issues related to the alarm conditions and bias correction will need to be addressed in future work. This work both demonstrates the use of the model for performing diversion scenario analyses and for testing advanced safeguards system designs.

  6. Advanced Safeguards Approaches for New Fast Reactors

    Energy Technology Data Exchange (ETDEWEB)

    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.

  7. 75 FR 81894 - Safeguarding Child Support Information

    Science.gov (United States)

    2010-12-29

    ... effect safeguards on the access to and use of data in the State's automated system. II. Background This... referred to information provided to parents and putative fathers. The technical correction is necessary to...), which requires that a parent's or putative father's Social Security Number (SSN) be provided to...

  8. "Safeguarding" Sports Coaching: Foucault, Genealogy and Critique

    Science.gov (United States)

    Garratt, Dean; Piper, Heather; Taylor, Bill

    2013-01-01

    This paper offers a genealogical account of safeguarding in sport. Drawing specifically on Foucault's work, it examines the "politics of touch" in relation to the social and historical formation of child protection policy in sports coaching. While the analysis has some resonance with the context of coaching as a whole, for illustrative…

  9. 38 CFR 18.436 - Procedural safeguards.

    Science.gov (United States)

    2010-07-01

    ... or are believed to need special instruction or related services. The system shall include: (1) Notice... THE CIVIL RIGHTS ACT OF 1964 Nondiscrimination on the Basis of Handicap Elementary, Secondary, and Adult Education § 18.436 Procedural safeguards. (a) A recipient that operates a public elementary...

  10. 45 CFR 605.36 - Procedural safeguards.

    Science.gov (United States)

    2010-10-01

    ... records, an impartial hearing with opportunity for participation by the person's parents or guardian and... Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION... Preschool, Elementary, and Secondary Education § 605.36 Procedural safeguards. A recipient that operates a...

  11. Antineutrino reactor safeguards - a case study

    CERN Document Server

    Christensen, Eric; Jaffke, Patrick

    2013-01-01

    Antineutrinos have been proposed as a means of reactor safeguards for more than 30 years and there has been impressive experimental progress in neutrino detection. In this paper we conduct, for the first time, a case study of the application of antineutrino safeguards to a real-world scenario - the North Korean nuclear crisis in 1994. We derive detection limits to a partial or full core discharge in 1989 based on actual IAEA safeguards access and find that two independent methods would have yielded positive evidence for a second core with very high confidence. To generalize our results, we provide detailed estimates for the sensitivity to the plutonium content of various types of reactors, including most types of plutonium production reactors, based on detailed reactor simulations. A key finding of this study is that a wide class of reactors with a thermal power of less than 0.1-1 GWth can be safeguarded achieving IAEA goals for quantitative sensitivity and timeliness with detectors right outside the reactor ...

  12. Readability of Special Education Procedural Safeguards

    Science.gov (United States)

    Mandic, Carmen Gomez; Rudd, Rima; Hehir, Thomas; Acevedo-Garcia, Dolores

    2012-01-01

    This study focused on literacy-related barriers to understanding the rights of students with disabilities and their parents within the special education system. SMOG readability scores were determined for procedural safeguards documents issued by all state departments of education. The average reading grade level was 16; 6% scored in the high…

  13. A Multivariate Empirical Orthogonal Function-Based Scheme for the Balanced Initial Ensemble Generation of an Ensemble Kalman Filter

    Institute of Scientific and Technical Information of China (English)

    ZHENG Fei; ZHU Jiang

    2010-01-01

    The initial ensemble perturbations for an ensemble data assimilation system are expected to reasonably sample model uncertainty at the time of analysis to further reduce analysis uncertainty.Therefore,the careful choice of an initial ensemble perturbation method that dynamically cycles ensemble perturbations is required for the optimal performance of the system.Based on the multivariate empirical onhogonal function(MEOF)method,a new ensemble initialization scheme is developed to generate balanced initial perturbations for the ensemble Kalman filter(EnKF)data assimilation,with a reasonable consideration of the physical relationships between different model variables.The scheme is applied in assimilation experiments with a global spectral atmospheric model and with real observations.The proposed perturbation method is compared to the commonly used method of spatially-correlated random perturbations.The comparisons show that the model uncertainties prior to the first analysis time,which are forecasted from the balanced ensemble initial fields,maintain a much more reasonable spread and a more accurate forecast error covariance than those from the randomly perturbed initial fields.The analysis results are further improved by the balanced ensemble initialization scheme due to more accurate background information.Also,a 20-day continuous assimilation experiment shows that the ensemble spreads for each model variable are still retained in reasonable ranges without considering additional perturbations or inflations during the assimilation cycles,while the ensemble spreads from the randomly perturbed initialization scheme decrease and collapse rapidly.

  14. Automatic Generation of Least-Possible-Impact Traffic Management Initiatives Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Weather accounts for 70% of the annual cost of air traffic delays and cancellations, of which about 60% are estimated to be avoidable. Traffic Management Initiatives...

  15. Technology Transfer and Innovation Initiatives in Strategic Management: Generating an Alternative Perspective

    Science.gov (United States)

    Major, E.

    2003-01-01

    This paper taps the strategic management discipline to inform our understanding of technology transfer and innovation (TTI) initiatives. With special focus on the UK Foresight programme it considers the impacts that the resource-based and core competence approaches to strategy can have on understanding the nature and effectiveness of TTI…

  16. Synthesis and Ring-Opening Metathesis Polymerization of Second-Generation Dendronized Poly(ether Monomers Initiated by Ruthenium Carbenes

    Directory of Open Access Journals (Sweden)

    Guzmán Pablo E.

    2016-03-01

    Full Text Available The Ring-Opening Metathesis Polymerization (ROMP of second-generation dendronized monomers is described. Using the highly active and fast-initiating third-generation ruthenium complex [(H2IMes(pyr2Cl2RuCHPh], moderate to high molecular weight polymers (430-2230 kDa are efficiently synthesized with low dispersities (Ð = 1.01-1.17. This study highlights the power of the metathesis approach toward polymer synthesis in a context where monomer structure can significantly impede polymerization.

  17. Initiation processes for run-off generated debris flows in the Wenchuan earthquake area of China

    NARCIS (Netherlands)

    Hu, W.; Dong, X. J.; Xu, Q.; Wang, G. H.; van Asch, T. W J; Hicher, P. Y.

    2016-01-01

    The frequency of huge debris flows greatly increased in the epicenter area of the Wenchuan earthquake. Field investigation revealed that runoff during rainstorm played a major role in generating debris flows on the loose deposits, left by coseismic debris avalanches. However, the mechanisms of these

  18. TECHNOLOGY DEVELOPMENT ON THE DUPIC SAFEGUARDS SYSTEM

    Energy Technology Data Exchange (ETDEWEB)

    H. KIM; H. CHA; ET AL

    2001-02-01

    A safeguards system has been developed since 1993 in the course of supporting a fuel cycle process to fabricate CANDU fuel with spent PWR fuel (known as Direct Use of PWR spent fuel In CANDU, DUPIC). The major safeguards technology involved here was to design and fabricate a neutron coincidence counting system for process accountability, and also an unattended continuous monitoring system in association with independent verification by the IAEA. This combined technology was to produce information of nuclear material content and to maintain knowledge of the continuity of nuclear material flow. In addition to hardware development, diagnosis software is being developed to assist data acquisition, data review, and data evaluation based on a neural network system on the IAEA C/S system.

  19. Safeguards Accountability Network accountability and materials management

    Energy Technology Data Exchange (ETDEWEB)

    Carnival, G.J.; Meredith, E.M.

    1985-01-01

    The Safeguards Accountability Network (SAN) is a computerized on-line accountability system for the safeguards accountability control of nuclear materials inventories at Rocky Flats Plant. SAN is a dedicated accountability system utilizing source documents filled out on the shop floor as its base. The system incorporates double entry accounting and is developed around the Material Balance Area (MBA) concept. MBA custodians enter transaction information from source documents prepared by personnel in the process areas directly into the SAN system. This provides a somewhat near-real time perpetual inventory system which has limited interaction with MBA custodians. MBA custodians are permitted to inquire into the system and status items on inventory. They are also responsible for the accuracy of the accountability information used as input to the system for their MBA. Monthly audits by the Nuclear Materials Control group assure the timeliness and accuracy of SAN accountability information.

  20. Safeguards Accountability Network accountability and materials management

    Energy Technology Data Exchange (ETDEWEB)

    Carnival, G.J.; Meredith, E.M.

    1985-01-01

    The Safeguards Accountability Network (SAN) is an on-line accountability system used by Rocky Flats Plant to provide accountability control of its nuclear material inventory. The system is also used to monitor and evaluate the use of the nuclear material inventory against programmatic objectives for materials management. The SAN system utilizes two Harris 800 Computers as central processing units. Enhancement plans are currently being formulated to provide automated data collection from process operations on the shop floor and from non-destructive analysis safeguards instrumentation. SAN, discussed in this paper, is an excellent system for basic accountability control of nuclear materials inventories and is a quite useful tool in evaluating the efficient use of nuclear materials inventories at Rocky Flats Plant.

  1. LESSONS LEARNED IN TESTING OF SAFEGUARDS EQUIPMENT.

    Energy Technology Data Exchange (ETDEWEB)

    PEPPER,S.; FARNITANO,M.; CARELLI,J.; HAZELTINE,J.; BAILEY,D.

    2001-10-29

    The International Atomic Energy Agency's (IAEA) Department of Safeguards uses complex instrumentation for the application of safeguards at nuclear facilities around the world. Often, this equipment is developed through cooperation with member state support programs because the Agency's requirements are unique and are not met by commercially available equipment. Before approving an instrument or system for routine inspection use, the IAEA subjects it to a series of tests designed to evaluate its reliability. In 2000, the IAEA began to observe operational failures in digital surveillance systems. In response to the observed failures, the IAEA worked with the equipment designer and manufacturer to determine the cause of failure. An action plan was developed to correct the performance issues and further test the systems to make sure that additional operational issues would not surface later. This paper addresses the steps taken to address operation issues related to digital image surveillance systems and the lessons learned during this process.

  2. Preliminary concepts: coordinated safeguards for materials management in a thorium--uranium fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Barnes, J.W.; Dayem, H.A.; Dietz, R.J.; Shipley, J.P.

    1978-10-01

    This report addresses preliminary concepts for coordinated safeguards materials management in a typical generic thorium--uranium-fueled light-water reactor (LWR) fuels reprocessing plant. The reference facility is designed to recover thorium and uranium from first-generation (denatured /sup 235/U) startup fuels, first-recycle and equilibrium (denatured /sup 233/U) thorium--uranium LWR fuels, and to recover the plutonium generated in the /sup 238/U denaturant as well. 12 figures, 3 tables.

  3. Developing a simulation for border safeguarding

    CSIR Research Space (South Africa)

    Van Rooyen, S

    2011-09-01

    Full Text Available Operations Other Than War (OOTW). Border safeguarding provides a platform to develop doctrine through simulation. Defence against aggression is replaced by arrests, and target damage assessment is replaced by the number of intercepts without kills... without the use of intelligent threat behaviour. Section 5 contains our conclusions. 2. Joint Control and Command Figure 1 shows how JC2 operate and communicate between the levels of war as defined in [2]. The levels signify Strategic goals...

  4. Initial dynamics of supercontinuum generation in highly nonlinear photonic crystal fiber.

    Science.gov (United States)

    Moeser, J T; Wolchover, N A; Knight, J C; Omenetto, F G

    2007-04-15

    We present a theoretical and experimental analysis of supercontinuum generation in very short lengths of high-nonlinearity photonic crystal fibers. The Raman response function for Schott SF6 glass is presented for what is believed to be the first time and used for numerical modeling of pulse propagation. Simulation and experiments are in excellent agreement and demonstrate the rapid transition to regimes of spectral complexity due to higher-order nonlinear effects.

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

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, Brian David [Los Alamos National Laboratory; Beddingfield, David H [Los Alamos National Laboratory; Durst, Philip [INL; Bean, Robert [INL

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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

  7. Advancement of safeguards inspection technology for CANDU nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Sung; Park, W. S.; Cha, H. R.; Ham, Y. S.; Lee, Y. G.; Kim, K. P.; Hong, Y. D

    1999-04-01

    The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.B.; Jaramillo, G.R. (comps.)

    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.

  9. Advancement of safeguards inspection technology for CANDU nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Sung; Park, W. S.; Cha, H. R.; Ham, Y. S.; Lee, Y. G.; Kim, K. P.; Hong, Y. D

    1999-04-01

    The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

  10. Eccentricity generation in hierarchical triple systems with coplanar and initially circular orbits

    CERN Document Server

    Georgakarakos, Nikolaos

    2014-01-01

    We develop a technique for estimating the inner eccentricity in hierarchical triple systems with well separated components. We investigate systems with initially circular and coplanar orbits and comparable masses. The technique is based on an expansion of the rate of change of the Runge-Lenz vector for calculating short period terms by using first order perturbation theory. The combination of the short period terms with terms arising from octupole level secular theory, results in the derivation of a rather simple formula for the eccentricity of the inner binary. The theoretical results are tested against numerical integrations of the full equations of motion. Comparison is also made with other results on the subject.

  11. Eccentricity generation in hierarchical triple systems with non-coplanar and initially circular orbits

    CERN Document Server

    Georgakarakos, Nikolaos

    2014-01-01

    In a previous paper, we developed a technique for estimating the inner eccentricity in coplanar hierarchical triple systems on initially circular orbits, with comparable masses and with well separated components, based on an expansion of the rate of change of the Runge-Lenz vector. Now, the same technique is extended to non-coplanar orbits. However, it can only be applied to systems with ${I_{0}140.77^{\\circ}}$, where ${I}$ is the inclination of the two orbits, because of complications arising from the so-called 'Kozai effect'. The theoretical model is tested against results from numerical integrations of the full equations of motion.

  12. Generation of initial Vlasov distributions for simulation of charged particle beams with high space-charge intensity

    Energy Technology Data Exchange (ETDEWEB)

    Lund, S M; Kikuchi, T; Davidson, R C

    2007-04-12

    Self-consistent Vlasov simulations of beams with high space-charge intensity often require specification of initial phase-space distributions that reflect properties of a beam that is well adapted to the transport channel, both in terms of low-order rms (envelope) properties as well as the higher-order phase-space structure. Here, we first review broad classes of distributions commonly in use as initial Vlasov distributions in simulations of beams with intense space-charge fields including: the Kapchinskij-Vladimirskij (KV) equilibrium, continuous-focusing equilibria with specific detailed examples, and various non-equilibrium distributions, such as the semi-Gaussian distribution and distributions formed from specified functions of linear-field Courant-Snyder invariants. Important practical details necessary to specify these distributions in terms of usual accelerator inputs are presented in a unified format. Building on this presentation, a new class of approximate initial distributions are constructed using transformations that preserve linear-focusing single-particle Courant-Snyder invariants to map initial continuous-focusing equilibrium distributions to a form more appropriate for non-continuous focusing channels. Self-consistent particle-in-cell simulations are employed to show that the approximate initial distributions generated in this manner are better adapted to the focusing channels for beams with high space-charge intensity. This improved capability enables simulation applications that more precisely probe intrinsic stability properties and machine performance.

  13. Generation of Initial Kinetic Distributions for Simulation of Long-Pulse Charged Particle Beams with High Space-Charge intensity

    Energy Technology Data Exchange (ETDEWEB)

    Lund, Steven M.; Kikuchi, Takashi; Davidson, Ronald C.

    2007-04-03

    Self-consistent Vlasov-Poisson simulations of beams with high space-charge intensity often require specification of initial phase-space distributions that reflect properties of a beam that is well adapted to the transport channel--both in terms of low-order rms (envelope) properties as well as the higher-order phase-space structure. Here, we first review broad classes of kinetic distributions commonly in use as initial Vlasov distributions in simulations of unbunched or weakly bunched beams with intense space-charge fields including: the Kapchinskij-Vladimirskij (KV) equilibrium, continuous-focusing equilibria with specific detailed examples, and various non-equilibrium distributions, such as the semi-Gaussian distribution and distributions formed from specified functions of linear-field Courant-Snyder invariants. Important practical details necessary to specify these distributions in terms of usual accelerator inputs are presented in a unified format. Building on this presentation, a new class of approximate initial kinetic distributions are constructed using transformations that preserve linear-focusing single-particle Courant-Snyder invariants to map initial continuous-focusing equilibrium distributions to a form more appropriate for non-continuous focusing channels. Self-consistent particle-in-cell simulations are employed to show that the approximate initial distributions generated in this manner are better adapted to the focusing channels for beams with high space-charge intensity. This improved capability enables simulation applications that more precisely probe intrinsic stability properties and machine performance.

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

    Energy Technology Data Exchange (ETDEWEB)

    Fensin, Michael L [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Sandoval, Nathan P [Los Alamos National Laboratory

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    Badwan, Faris M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Miller, Michael Conrad [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pshakin, Gennady [Obninsk Institute of Physics and Power Engineering (Russian Federation)

    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

  16. Safeguarding nonhuman primate iPS cells with suicide genes.

    Science.gov (United States)

    Zhong, Bonan; Watts, Korashon L; Gori, Jennifer L; Wohlfahrt, Martin E; Enssle, Joerg; Adair, Jennifer E; Kiem, Hans-Peter

    2011-09-01

    The development of technology to generate induced pluripotent stem (iPS) cells constitutes one of the most exciting scientific breakthroughs because of the enormous potential for regenerative medicine. However, the safety of iPS cell-related products is a major concern for clinical translation. Insertional mutagenesis, possible oncogenic transformation of iPS cells or their derivatives, or the contamination of differentiated iPS cells with undifferentiated cells, resulting in the formation of teratomas, have remained considerable obstacles. Here, we demonstrate the utility of suicide genes to safeguard iPS cells and their derivatives. We found suicide genes can control the cell fate of iPS cells in vitro and in vivo without interfering with their pluripotency and self-renewal capacity. This study will be useful to evaluate the safety of iPS cell technology in a clinically highly relevant, large animal model and further benefit the clinical use of human iPS cells.

  17. Generating an item pool for translational social cognition research: methodology and initial validation.

    Science.gov (United States)

    Keutmann, Michael K; Moore, Samantha L; Savitt, Adam; Gur, Ruben C

    2015-03-01

    Existing sets of social and emotional stimuli suitable for social cognition research are limited in many ways, including size, unimodal stimulus delivery, and restriction to major universal emotions. Existing measures of social cognition could be improved by taking advantage of item response theory and adaptive testing technology to develop instruments that obtain more efficient measures of multimodal social cognition. However, for this to be possible, large pools of emotional stimuli must be obtained and validated. We present the development of a large, high-quality multimedia stimulus set produced by professional adult and child actors (ages 5 to 74) containing both visual and vocal emotional expressions. We obtained over 74,000 audiovisual recordings of a wide array of emotional and social behaviors, including the main universal emotions (happiness, sadness, anger, fear, disgust, and surprise), as well as more complex social expressions (pride, affection, sarcasm, jealousy, and shame). The actors generated a high quantity of technically superior, ecologically valid stimuli that were digitized, archived, and rated for accuracy and intensity of expressions. A subset of these facial and vocal expressions of emotion and social behavior were submitted for quantitative ratings to generate parameters for validity and discriminability. These stimuli are suitable for affective neuroscience-based psychometric tests, functional neuroimaging, and social cognitive rehabilitation programs. The purposes of this report are to describe the method of obtaining and validating this database and to make it accessible to the scientific community. We invite all those interested in participating in the use and validation of these stimuli to access them at www.med.upenn.edu/bbl/actors/index.shtml .

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

    Energy Technology Data Exchange (ETDEWEB)

    Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James K. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    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.

  19. Quantitative comparison of initial soil erosion processes and runoff generation in Spanish and German vineyards.

    Science.gov (United States)

    Rodrigo Comino, J; Iserloh, T; Lassu, T; Cerdà, A; Keestra, S D; Prosdocimi, M; Brings, C; Marzen, M; Ramos, M C; Senciales, J M; Ruiz Sinoga, J D; Seeger, M; Ries, J B

    2016-09-15

    The aim of this study was to enable a quantitative comparison of initial soil erosion processes in European vineyards using the same methodology and equipment. The study was conducted in four viticultural areas with different characteristics (Valencia and Málaga in Spain, Ruwer-Mosel valley and Saar-Mosel valley in Germany). Old and young vineyards, with conventional and ecological planting and management systems were compared. The same portable rainfall simulator with identical rainfall intensity (40mmh(-1)) and sampling intervals (30min of test duration, collecting the samples at 5-min-intervals) was used over a circular test plot with 0.28m(2). The results of 83 simulations have been analysed and correlation coefficients were calculated for each study area to identify the relationship between environmental plot characteristics, soil texture, soil erosion, runoff and infiltration. The results allow for identification of the main factors related to soil properties, topography and management, which control soil erosion processes in vineyards. The most important factors influencing soil erosion and runoff were the vegetation cover for the ecological German vineyards (with 97.6±8% infiltration coefficients) and stone cover, soil moisture and slope steepness for the conventional land uses.

  20. Nuclear safeguards research and development program. Status report, January--April 1977

    Energy Technology Data Exchange (ETDEWEB)

    Sapir, J.L. (comp.)

    1977-06-01

    The status of the Nuclear Safeguards Research and Development program pursued by LASL Safeguards Groups Q-1, Q-2, Q-3, and Q-4 is presented . Topics covered include nondestructive assay technology development and applications, international safeguards, perimeter safeguards and surveillance, concepts and subsystems development (e.g., DYMAC program), integrated safeguards systems, training courses, and technology transfer.

  1. Technology transfer significance of the International Safeguards Project Office

    Energy Technology Data Exchange (ETDEWEB)

    Marcuse, W.; Wallgura, A.J.

    1988-01-01

    The safeguards implemented by the International Atomic Energy Agency (IAEA) are of major importance to the non-proliferation objectives of the United States of America and other nations of the world. Assurance of safeguards effectiveness is mandatory to continued peaceful use of nuclear power. To enhance the ability of the IAEA to apply safeguards effectively, and to ensure that the IAEA does not lack technical assistance in critical areas, the U.S. Congress has made available a special authorization for a Program for Technical Assistance to IAEA Safeguards (POTAS). In expediting the program full use is made of existing DOE laboratory resources.

  2. Pre-swing deficits in forward propulsion, swing initiation and power generation by individual muscles during hemiparetic walking.

    Science.gov (United States)

    Peterson, Carrie L; Hall, Allison L; Kautz, Steven A; Neptune, Richard R

    2010-08-26

    Clinical studies of hemiparetic walking have shown pre-swing abnormalities in the paretic leg suggesting that paretic muscle contributions to important biomechanical walking subtasks are different than those of non-disabled individuals. Three-dimensional forward dynamics simulations of two representative hemiparetic subjects with different levels of walking function classified by self-selected walking speed (i.e., limited community=0.4-0.8 m/s and community walkers = or > 0.8m/s) and a speed-matched control were generated to quantify individual muscle contributions to forward propulsion, swing initiation and power generation during the pre-swing phase (i.e., double support phase proceeding toe-off). Simulation analyses identified decreased paretic soleus and gastrocnemius contributions to forward propulsion and power generation as the primary impairment in the limited community walker compared to the control subject. The non-paretic leg did not compensate for decreased forward propulsion by paretic muscles during pre-swing in the limited community walker. Paretic muscles had the net effect to absorb energy from the paretic leg during pre-swing in the community walker suggesting that deficits in swing initiation are a primary impairment. Specifically, the paretic gastrocnemius and hip flexors (i.e., iliacus, psoas and sartorius) contributed less to swing initiation and the paretic soleus and gluteus medius absorbed more power from the paretic leg in the community walker compared to the control subject. Rehabilitation strategies aimed at diminishing these deficits have much potential to improve walking function in these hemiparetic subjects and those with similar deficits.

  3. XUV-initiated high harmonic generation: driving inner valence electrons using below-threshold-energy XUV light

    CERN Document Server

    Brown, A C

    2016-01-01

    We propose a novel scheme for resolving the contribution of inner- and outer-valence electrons in XUV-initiated high-harmonic generation in neon. By probing the atom with a low energy (below the 2s ionisation threshold) ultrashort XUV pulse, the 2p electron is steered away from the core, while the 2s electron is enabled to describe recollision trajectories. By selectively suppressing the 2p recollision trajectories we can resolve the contribution of the 2s electron to the high-harmonic spectrum. We apply the classical trajectory model to account for the contribution of the 2s electron, which allows for an intuitive understanding of the process.

  4. A Simple Candle Filter Safeguard Device

    Energy Technology Data Exchange (ETDEWEB)

    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.

  5. Secret Objective Standoff: International Safeguards Educational Exercise

    Energy Technology Data Exchange (ETDEWEB)

    Okowita, Samantha L [ORNL

    2014-01-01

    The International Safeguards Regime, being so multi-faceted, can be overwhelming to those first introduced to its many components. The organizers and lecturers of workshops and courses on nonproliferation often provide a series of independent lectures and must somehow demonstrate the cohesive and effective nature of the system. An exercise titled The Secret Objective Standoff was developed to complement lectures with hands-on learning to assist participants in bringing all the many components (IAEA agreements, export controls, treaty obligations, international diplomacy, etc.) of the International Safeguards Regime together. This exercise divides participants into teams that are assigned the role of either a country or the IAEA and asks that they fully immerse themselves in their roles. The teams are then randomly assigned three unique and secret objectives that are intended to represent realistic and current geopolitical scenarios. Through construction, trading, or hoarding of four resources (experts, technology, money, and uranium), the teams have a finite number of turns to accomplish their objectives. Each turn has three phases random dispersal of resources, a timed discussion where teams can coordinate and strategize with others, and an action phase. During the action phase, teams inform the moderator individually and secretly what they will be doing that turn. The exercise has been tested twice with Oak Ridge National Laboratory personnel, and has been conducted with outside participants twice, in each case the experience was well received by both participants and instructors. This exercise provides instructors the ability to modify the exercise before or during game play to best fit their educational goals. By offering a range of experiences, from an in-depth look at specific components to a generalized overview, this exercise is an effective tool in helping participants achieve a full understanding the International Safeguards Regime.

  6. Nuclear power plants of the 4th generation: American Initiative in the context of an international policy. No frontiers for progress; Kernkraftwerke der vierten Generation: Amerikanische Initiative im Kontext internationaler Politik. Fortschritt ist laenderuebergreifend gepraegt

    Energy Technology Data Exchange (ETDEWEB)

    Botzian, R. [Forschungsinstitut fuer internationale Politik und Sicherheit der Stiftung Wissenschaft und Politik, Ebenhausen (Isar) (Germany)

    2003-05-17

    This article tries to give an overview on more or less political questions of nuclear power generation in the context of technological developments over the years: chronology of the different generations of nuclear technological developments: ways to a higher safety; treatment of spent fuels; overview on the roadmap of the Generation IV International Forum - Nuclear Energy Systems; who defines the international agenda for nuclear energy?; the German position in the international environment. [German] In der aktuellen Konstellation steht einerseits eine global durchschlagende Reduktion der CO{sub 2}-Emissionen in den Sternen, andererseits wurde der Atomausstieg mit der Begruendung inakzeptabler Strahlungsrisiken zu einem weitverbreiteten gesellschaftspolitischen Credo [5]. In dieser Schwebelage haben die Amerikaner erneut die Initiative ergriffen und eine multilaterale wissenschaftlichtechnische Plattform fuer einen ausgedehnten und weltweiten Einsatz von Kernkraftwerken eingerichtet, und zwar mit einem Zeithorizont von drei Dekaden. Hierbei geht es weniger um voellig Neues als vielmehr um eine modifizierte Definition amerikanischer Interessen im Kontext der internationalen Nuklearpolitik. Dazu zaehlen vor allem Wirtschaftlichkeit sowie maximale Sicherheit vor schweren Unfaellen und vor unerlaubter Kernwaffenproduktion. (orig.)

  7. Advanced Safeguards Technology Demonstration at Pacific Northwest National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-05-21

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

  8. Nonproliferation and safeguards aspects of the DUPIC fuel cycle concept

    Energy Technology Data Exchange (ETDEWEB)

    Persiani, P. K. [Argonne National Lab., IL (United States)

    1997-07-01

    The purpose of the study is to comment on the proliferation characteristic profiles of some of the proposed fuel cycle alternatives to help ensure that nonproliferation concerns are introduced into the early stages of a fuel cycle concept development program, and to perhaps aid in the more effective implementation of the international nonproliferation regime initiative and safeguards systems. Alternative recycle concepts proposed by several countries involve the recycle of spent fuel without the separation of plutonium from uranium and fission products. The concepts are alternatives to either the direct long-term storage deposition of or the purex reprocessing of the spent fuels. The alternate fuel cycle concepts reviewed include: the dry-recycle processes such as the direct use of reconfigured PWR spent fuel assemblies into CANDU reactors(DUPIC); low-decontamination, single-cycle co-extraction of fast reactor fuels in a wet-purex type of reprocessing; and on a limited scale the thorium-uranium fuel cycle. The nonproliferation advantages usually associated with the above non-separation processes are: the highly radioactive spent fuel presents a barrier to the physical diversion of the nuclear material; avoid the need to dissolve and chemically separate the plutonium from the uranium and fission products; and that the spent fuel isotopic quality of the plutonium vector is further degraded. Although the radiation levels and the need for reprocessing may be perceived as barriers to the terrorist or the subnational level of safeguards, the international level of nonproliferation concerns is addressed primarily by material accountancy and verification activities. On the international level of nonproliferation concerns, the non-separation fuel cycle concepts involved have to be evaluated on the bases of the impact the processes may have on nuclear materials accountancy. (author).

  9. 77 FR 37804 - Rules for Investigations Relating to Global and Bilateral Safeguard Actions, Market Disruption...

    Science.gov (United States)

    2012-06-25

    ... bilateral safeguard investigations under the North American Free Trade Agreement (NAFTA) Implementation Act... implements bilateral safeguard provisions in several additional free trade agreements (FTAs), including... safeguard provisions in free trade agreements that the United States has negotiated with Australia, Bahrain...

  10. 7 CFR 4290.506 - Safeguarding the RBIC's assets/Internal controls.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 15 2010-01-01 2010-01-01 false Safeguarding the RBIC's assets/Internal controls... Safeguarding the RBIC's assets/Internal controls. You must adopt a plan to safeguard your assets and monitor... your control procedures....

  11. A colalborative environment for information driven safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Scott, Mark R [Los Alamos National Laboratory; Michel, Kelly D [Los Alamos National Laboratory

    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

    Energy Technology Data Exchange (ETDEWEB)

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

    Energy Technology Data Exchange (ETDEWEB)

    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

  14. Changing Landscapes in Safeguarding Babies and Young Children in England

    Science.gov (United States)

    Lumsden, Eunice

    2014-01-01

    The importance of safeguarding children from violence is internationally recognised. However, detecting, intervening and protecting children from abuse both within the family and in institutions is complex. This paper specifically focuses on safeguarding in England and how workforce reform in the early years offers the opportunity to forge new…

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

    Energy Technology Data Exchange (ETDEWEB)

    Shipley, J.P. (comp.)

    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.

  16. The Role of School Psychologists in Child Protection and Safeguarding

    Science.gov (United States)

    Woods, Kevin; Bond, Caroline; Tyldesley, Kath; Farrell, Peter; Humphrey, Neil

    2011-01-01

    Child protection and safeguarding are important aspects of work for all professionals working with children. The current article outlines the international context of school psychologists' work in relation to child protection and safeguarding and describes the United Kingdom context in more detail. Given the relatively recent broadening of the UK…

  17. Safeguards and nonproliferation aspects of a dry fuel recycling technology

    Energy Technology Data Exchange (ETDEWEB)

    Pillay, K.K.S.

    1993-05-01

    Los Alamos National Laboratory undertook an independent assessment of the proliferation potentials and safeguardability of a dry fuel recycling technology, whereby spent pressurized-water reactor (PWR) fuels are used to fuel canadian deuterium uranium (CANDU) reactors. Objectives of this study included (1) the evaluation of presently available technologies that may be useful to safeguard technology options for dry fuel recycling (2) and identification of near-term and long-term research needs to develop process-specific safeguards requirements. The primary conclusion of this assessment is that like all other fuel cycle alternatives proposed in the past, the dry fuel recycle entails prolfferation risks and that there are no absolute technical fixes to eliminate such risks. This study further concludes that the proliferation risks of dry fuel recycling options are relatively minimal and presently known safeguards systems and technologies can be modified and/or adapted to meet the requirements of safeguarding such fuel recycle facilities.

  18. Can a safeguards accountancy system really detect an unauthorized removal

    Energy Technology Data Exchange (ETDEWEB)

    Ehinger, M.H.; Ellis, J.H.

    1981-11-01

    Theoretical investigations and system studies indicate safeguards material balance data from reprocessing plants can be used to detect unauthorized removals. Plant systems have been modeled and simulated data used to demonstrate the techniques. But how sensitive are the techniques when used with actual plant data. What is the effect of safeguards applications on plant operability. Can safeguards be acceptable to plant operators, and are there any benefits to be derived. The Barnwell Nuclear Fuel Plant (BNFP) has been devoted to answering these and other questions over the past several years. A computerized system of near-real-time accounting and in-process inventory has been implemented and demonstrated during actual plant test runs. Measured inventories and hourly material balance closures have been made to assess safeguards in an operating plant application. The tests have culminated in actual removals of material from the operating plant to investigate the response and measure the sensitivity of the safeguards and data evaluation system.

  19. Organizational Culture, 3S, and Safeguards by Design

    Energy Technology Data Exchange (ETDEWEB)

    Mladineo, Stephen V.; Frazar, Sarah L.

    2012-01-31

    While Safety and Security Culture are well socialized among nuclear facility designers, the concept of safeguards culture is less well defined. One area where safeguards culture may play a helpful role is in the area of Safeguards by Design. This paper will include a theoretical discussion of organizational culture, leading with safety culture and security culture that are well known, and positing that there may be room to think about safeguards culture along with the others. It will also examine the utility of the 3S concept and how this concept has been used in training for newcomer states. These will lead into a discussion of how the addition of safeguards to the mix of safety by design and security by design can be valuable, particularly as it is socialized to newcomer states.

  20. Technology development of nuclear material safeguards for DUPIC fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jong Sook; Kim, Ho Dong; Kang, Hee Young; Lee, Young Gil; Byeon, Kee Ho; Park, Young Soo; Cha, Hong Ryul; Park, Ho Joon; Lee, Byung Doo; Chung, Sang Tae; Choi, Hyung Rae; Park, Hyun Soo

    1997-07-01

    During the second phase of research and development program conducted from 1993 to 1996, nuclear material safeguards studies system were performed on the technology development of DUPIC safeguards system such as nuclear material measurement in bulk form and product form, DUPIC fuel reactivity measurement, near-real-time accountancy, and containment and surveillance system for effective and efficient implementation of domestic and international safeguards obligation. By securing in advance a optimized safeguards system with domestically developed hardware and software, it will contribute not only to the effective implementation of DUPIC safeguards, but also to enhance the international confidence build-up in peaceful use of spent fuel material. (author). 27 refs., 13 tabs., 89 figs.

  1. Training to raise staff awareness about safeguarding children.

    Science.gov (United States)

    Fleming, Jane

    2015-04-01

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

  2. Parental Traffic Safeguarding at School Sites: Unequal Risks and Responsibilities

    Directory of Open Access Journals (Sweden)

    Arlene Tigar McLaren

    2011-01-01

    Full Text Available Scholars recognize the importance of parental chauffeuring in urbanenvironments, but pay remarkably little attention to how parents, as part of everyday, domestic practices, safeguard their children in auto-dominated streets. Based on in-depth, qualitative interviews with parents whose children attend public elementary schools, this exploratory study compares traffic safeguarding experiences on the east and west sides of Vancouver, British Columbia. The analysisshows how social class and gender intersect in three traffic sites: school streetscapes, school entrances, and school traffic safety volunteerism. Utilizing automobility and feminist theories, we argue that urban parental traffic safeguarding is a complex and variegated phenomenon involving unequal risks and responsibilities. Our analysis illustrates the ways in which parental traffic safeguarding is a lynchpin to the automobility system, particularly with respect to itsillusion of safety, and how, conversely, this system shapes parenting by constituting traffic safeguarding as part of domestic responsibilities.

  3. Safeguardability of the vitrification option for disposal of plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Pillay, K.K.S. [Los Alamos National Lab., NM (United States)

    1996-05-01

    Safeguardability of the vitrification option for plutonium disposition is rather complex and there is no experience base in either domestic or international safeguards for this approach. In the present treaty regime between the US and the states of the former Soviet Union, bilaterial verifications are considered more likely with potential for a third-party verification of safeguards. There are serious technological limitations to applying conventional bulk handling facility safeguards techniques to achieve independent verification of plutonium in borosilicate glass. If vitrification is the final disposition option chosen, maintaining continuity of knowledge of plutonium in glass matrices, especially those containing boron and those spike with high-level wastes or {sup 137}Cs, is beyond the capability of present-day safeguards technologies and nondestructive assay techniques. The alternative to quantitative measurement of fissile content is to maintain continuity of knowledge through a combination of containment and surveillance, which is not the international norm for bulk handling facilities.

  4. Phase 2 Final Report. IAEA Safeguards: Implementation blueprint of commercial satellite imagery

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Christer [SSC Satellitbild AB, Solna (Sweden)

    2000-01-01

    areas: production of 'dossiers'; generation of reference information; monitoring and verification; and finally organisation of an imagery database. Each work area could be dedicated to one staff member running one of the four main tasks. We recommend the Agency to introduce a full service imagery supply routine, where the image supplier(s) take the responsibility and risks in delivering the best possible set of imagery from a chosen facility. This routine should be the basis for an effective imagery purchasing approach at the Unit. Successful negotiations regarding price and service with the suppliers will substantially influence the overall cost. The implementation of the satellite imagery system is suggested to be performed in a controlled way, by creating clear implementation phases with firm milestones, and by evaluating each step before going further: Initial phase 6-12 months; Pre-operational phase 1-2 years; Operational phase after 3 years. The significant customisation of the Imagery Unit system that is envisaged must be well specified and documented. The following points are the main items arising during the study of the Implementation Blueprint. The findings are an aggregated summary from this Phase 2 study as well as the main points from the Phase 1 Cost/Benefit analysis. The studies confirm that the proposed concept of relatively small and efficient Imagery Units using high-resolution data within the Agency will be a sound and feasible undertaking. Such a unit capable of performing advanced image processing as a tool for various safeguard tasks will give the Agency a new and effective instrument for reference, monitoring, verification, and detection of declared and undeclared activities. One important prerequisite for the success of the implementation and the operation of the Imagery Unit is that the Agency clearly and in measurable terms defines documents and distributes the objectives and role of the Imagery Unit internally to all concerned, and

  5. Phase 2 Final Report. IAEA Safeguards: Implementation blueprint of commercial satellite imagery

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Christer [SSC Satellitbild AB, Solna (Sweden)

    2000-01-01

    areas: production of 'dossiers'; generation of reference information; monitoring and verification; and finally organisation of an imagery database. Each work area could be dedicated to one staff member running one of the four main tasks. We recommend the Agency to introduce a full service imagery supply routine, where the image supplier(s) take the responsibility and risks in delivering the best possible set of imagery from a chosen facility. This routine should be the basis for an effective imagery purchasing approach at the Unit. Successful negotiations regarding price and service with the suppliers will substantially influence the overall cost. The implementation of the satellite imagery system is suggested to be performed in a controlled way, by creating clear implementation phases with firm milestones, and by evaluating each step before going further: Initial phase 6-12 months; Pre-operational phase 1-2 years; Operational phase after 3 years. The significant customisation of the Imagery Unit system that is envisaged must be well specified and documented. The following points are the main items arising during the study of the Implementation Blueprint. The findings are an aggregated summary from this Phase 2 study as well as the main points from the Phase 1 Cost/Benefit analysis. The studies confirm that the proposed concept of relatively small and efficient Imagery Units using high-resolution data within the Agency will be a sound and feasible undertaking. Such a unit capable of performing advanced image processing as a tool for various safeguard tasks will give the Agency a new and effective instrument for reference, monitoring, verification, and detection of declared and undeclared activities. One important prerequisite for the success of the implementation and the operation of the Imagery Unit is that the Agency clearly and in measurable terms defines documents and distributes the objectives and role of the Imagery Unit internally to all concerned, and

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  7. Initial Screening of Thermochemical Water-Splitting Cycles for High Efficiency Generation of Hydrogen Fuels Using Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    Brown, L.C.; Funk, J.F.; Showalter, S.K.

    1999-12-15

    OAK B188 Initial Screening of Thermochemical Water-Splitting Cycles for High Efficiency Generation of Hydrogen Fuels Using Nuclear Power There is currently no large scale, cost-effective, environmentally attractive hydrogen production process, nor is such a process available for commercialization. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Fossil fuels are polluting and carbon dioxide emissions from their combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. Almost 800 literature references were located which pertain to thermochemical production of hydrogen from water and over 100 thermochemical watersplitting cycles were examined. Using defined criteria and quantifiable metrics, 25 cycles have been selected for more detailed study.

  8. Advances toward a transportable antineutrino detector system for reactor monitoring and safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Reyna, D. [Sandia National Laboratories, Livermore, CA 94550 (United States); Bernstein, A. [Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States); Lund, J.; Kiff, S.; Cabrera-Palmer, B. [Sandia National Laboratories, Livermore, CA 94550 (United States); Bowden, N. S.; Dazeley, S.; Keefer, G. [Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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

  11. Two isoforms of TALDO1 generated by alternative translational initiation show differential nucleocytoplasmic distribution to regulate the global metabolic network

    Science.gov (United States)

    Moriyama, Tetsuji; Tanaka, Shu; Nakayama, Yasumune; Fukumoto, Masahiro; Tsujimura, Kenji; Yamada, Kohji; Bamba, Takeshi; Yoneda, Yoshihiro; Fukusaki, Eiichiro; Oka, Masahiro

    2016-01-01

    Transaldolase 1 (TALDO1) is a rate-limiting enzyme involved in the pentose phosphate pathway, which is traditionally thought to occur in the cytoplasm. In this study, we found that the gene TALDO1 has two translational initiation sites, generating two isoforms that differ by the presence of the first 10 N-terminal amino acids. Notably, the long and short isoforms were differentially localised to the cell nucleus and cytoplasm, respectively. Pull-down and in vitro transport assays showed that the long isoform, unlike the short one, binds to importin α and is actively transported into the nucleus in an importin α/β-dependent manner, demonstrating that the 10 N-terminal amino acids are essential for its nuclear localisation. Additionally, we found that these two isoforms can form homo- and/or hetero-dimers with different localisation dynamics. A metabolite analysis revealed that the subcellular localisation of TALDO1 is not crucial for its activity in the pentose phosphate pathway. However, the expression of these two isoforms differentially affected the levels of various metabolites, including components of the tricarboxylic acid cycle, nucleotides, and sugars. These results demonstrate that the nucleocytoplasmic distribution of TALDO1, modulated via alternative translational initiation and dimer formation, plays an important role in a wide range of metabolic networks. PMID:27703206

  12. Analysis of the impact of safeguards criteria

    Energy Technology Data Exchange (ETDEWEB)

    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.

  13. Left atrial appendage closure using the Amulet device: an initial experience with the second generation amplatzer cardiac plug.

    Science.gov (United States)

    Lam, Simon Cheung Chi; Bertog, Stefan; Gafoor, Sameer; Vaskelyte, Laura; Boehm, Patrick; Ho, Raymond Wei Jian; Franke, Jennifer; Hofmann, Ilona; Sievert, Horst

    2015-02-01

    Aim of this study was to demonstrate the feasibility, safety, and short-term outcome of left atrial appendage (LAA) closure with a new generation LAA closure device. The Amulet device (AGA, St Jude Medical, Minneapolis, MN) is a new generation of the amplatzer cardiac plug (ACP), specifically designed for LAA closure. This new version is designed to facilitate the implantation process and minimize procedural or device-related complications. The device was implanted in 17 patients with nonvalvular atrial fibrillation (AF). Clinical data were obtained at baseline, during the procedure, at discharge, at 30 and 90 days. All devices were implanted successfully. Device sizes ranged from 20 mm to 31 mm. A 12 French (Fr) or 14 Fr delivery sheath was used depending on the selected device size. Full and partial recapture was performed in 1 case and 3 cases, respectively. There was 1 procedure-related pericardial effusion successfully managed with pericardiocentesis. There was no device embolization. The mean length of stay was 2.1 ± 0.3 days. At 90 days, there were no deaths, strokes, systemic thromboembolism, or bleeding complications. There was no device-related thrombus or pericardial effusion at 90-day TEE. In 2 of the 17 patients minimal peridevice flow (smaller than 2 mm) was present. The Amulet device, which has new novel features as compared with the first generation ACP, is a feasible option for LAA closure. From our initial experience, implantation of the Amulet is associated with high success rate and good short-term outcome. © 2014 Wiley Periodicals, Inc.

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

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.B. (comp.)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.B. (comp.)

    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.

  16. Improving NPT safeguards. Particularly at the natural uranium starting point

    Energy Technology Data Exchange (ETDEWEB)

    Harry, J. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Klerk, P. de [Ministry of Foreign Affairs, The Hague (Netherlands)

    1996-03-01

    According to the Non Proliferation Treaty (NPT) all nuclear material is subject to safeguards, but according to INFCIRC/153 the full range of safeguards is only applied beyond the `starting point of safeguards`, that is: The point at which nuclear material has reached a composition and purity suitable for fuel fabrication or enrichment. This paper addresses the two questions: (a) is the starting point adequately defined, and (b) what mesures could be applied to nuclear material before the starting point? Those questions have been asked before, some of the answers in this paper are new. (orig.).

  17. Design of safeguards information treatment system at the facility level

    Energy Technology Data Exchange (ETDEWEB)

    Song, Dae Yong; Lee, Byung Doo; Kwack, Eun Ho; Choi, Young Myong

    2001-05-01

    We are developing Safeguards Information Treatment System at the facility level(SITS) to manage synthetically safeguards information and to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, we described the contents of the detailed design of SITS such as database, I/O layout and program. In the present, we are implementing the SITS based on the contents of the design of SITS, and then we plan to provide the system for the facilities after we finish implementing and testing the system.

  18. Process monitoring in international safeguards for reprocessing plants: A demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Ehinger, M.H.

    1989-01-01

    In the period 1985--1987, the Oak Ridge National Laboratory investigated the possible role of process monitoring for international safeguards applications in fuel reprocessing plants. This activity was conducted under Task C.59, ''Review of Process Monitoring Safeguards Technology for Reprocessing Facilities'' of the US program of Technical Assistance to the International Atomic Energy Agency (IAEA) Safeguards program. The final phase was a demonstration of process monitoring applied in a prototypical reprocessing plant test facility at ORNL. This report documents the demonstration and test results. 35 figs.

  19. Repetition priming of motor activity mediated by a central pattern generator: the importance of extrinsic vs. intrinsic program initiators.

    Science.gov (United States)

    Siniscalchi, Michael J; Cropper, Elizabeth C; Jing, Jian; Weiss, Klaudiusz R

    2016-10-01

    Repetition priming is characterized by increased performance as a behavior is repeated. Although this phenomenon is ubiquitous, mediating mechanisms are poorly understood. We address this issue in a model system, the feeding network of Aplysia This network generates both ingestive and egestive motor programs. Previous data suggest a chemical coding model: ingestive and egestive inputs to the feeding central pattern generator (CPG) release different modulators, which act via different second messengers to prime motor activity in different ways. The ingestive input to the CPG (neuron CBI-2) releases the peptides feeding circuit activating peptide and cerebral peptide 2, which produce an ingestive pattern of activity. The egestive input to the CPG (the esophageal nerve) releases the peptide small cardioactive peptide. This model is based on research that focused on a single aspect of motor control (radula opening). Here we ask whether repetition priming is observed if activity is triggered with a neuron within the core CPG itself and demonstrate that it is not. Moreover, previous studies demonstrated that effects of modulatory neurotransmitters that induce repetition priming persist. This suggests that it should be possible to "prime" motor programs triggered from within the CPG by first stimulating extrinsic modulatory inputs. We demonstrate that programs triggered after ingestive input activation are ingestive and programs triggered after egestive input activation are egestive. We ask where this priming occurs and demonstrate modifications within the CPG itself. This arrangement is likely to have important consequences for "task" switching, i.e., the cessation of one type of motor activity and the initiation of another. Copyright © 2016 the American Physiological Society.

  20. Legalizing euthanasia or assisted suicide: the illusion of safeguards and controls.

    Science.gov (United States)

    Pereira, J

    2011-04-01

    Euthanasia or assisted suicide-and sometimes both-have been legalized in a small number of countries and states. In all jurisdictions, laws and safeguards were put in place to prevent abuse and misuse of these practices. Prevention measures have included, among others, explicit consent by the person requesting euthanasia, mandatory reporting of all cases, administration only by physicians (with the exception of Switzerland), and consultation by a second physician.The present paper provides evidence that these laws and safeguards are regularly ignored and transgressed in all the jurisdictions and that transgressions are not prosecuted. For example, about 900 people annually are administered lethal substances without having given explicit consent, and in one jurisdiction, almost 50% of cases of euthanasia are not reported. Increased tolerance of transgressions in societies with such laws represents a social "slippery slope," as do changes to the laws and criteria that followed legalization. Although the initial intent was to limit euthanasia and assisted suicide to a last-resort option for a very small number of terminally ill people, some jurisdictions now extend the practice to newborns, children, and people with dementia. A terminal illness is no longer a prerequisite. In the Netherlands, euthanasia for anyone over the age of 70 who is "tired of living" is now being considered. Legalizing euthanasia and assisted suicide therefore places many people at risk, affects the values of society over time, and does not provide controls and safeguards.

  1. Legalizing euthanasia or assisted suicide: the illusion of safeguards and controls

    Science.gov (United States)

    Pereira, J.

    2011-01-01

    Euthanasia or assisted suicide—and sometimes both—have been legalized in a small number of countries and states. In all jurisdictions, laws and safeguards were put in place to prevent abuse and misuse of these practices. Prevention measures have included, among others, explicit consent by the person requesting euthanasia, mandatory reporting of all cases, administration only by physicians (with the exception of Switzerland), and consultation by a second physician. The present paper provides evidence that these laws and safeguards are regularly ignored and transgressed in all the jurisdictions and that transgressions are not prosecuted. For example, about 900 people annually are administered lethal substances without having given explicit consent, and in one jurisdiction, almost 50% of cases of euthanasia are not reported. Increased tolerance of transgressions in societies with such laws represents a social “slippery slope,” as do changes to the laws and criteria that followed legalization. Although the initial intent was to limit euthanasia and assisted suicide to a last-resort option for a very small number of terminally ill people, some jurisdictions now extend the practice to newborns, children, and people with dementia. A terminal illness is no longer a prerequisite. In the Netherlands, euthanasia for anyone over the age of 70 who is “tired of living” is now being considered. Legalizing euthanasia and assisted suicide therefore places many people at risk, affects the values of society over time, and does not provide controls and safeguards. PMID:21505588

  2. Interim Procedures Safeguarding Mobile Devices during International Travel

    Science.gov (United States)

    This procedure is for safeguarding EPA information and systems for all employees, contractors, and other users while on international travel or to specifically designated locations within the United States and foreign embassies.

  3. It's Never Too Soon to Safeguard Your Bones

    Science.gov (United States)

    ... page: https://medlineplus.gov/news/fullstory_167696.html It's Never Too Soon to Safeguard Your Bones Osteoporosis ... risk, too, according to the National Osteoporosis Foundation. It weakens bones, leaving them at greater risk of ...

  4. Development of Pattern Recognition Options for Combining Safeguards Subsystems

    Energy Technology Data Exchange (ETDEWEB)

    Burr, Thomas L. [Los Alamos National Laboratory; Hamada, Michael S. [Los Alamos National Laboratory

    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).

  5. Reactor safeguards system assessment and design. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    Varnado, G.B.; Ericson, D.M. Jr.; Daniel, S.L.; Bennett, H.A.; Hulme, B.L.

    1978-06-01

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

  6. Safeguards Knowledge Management & Retention at U.S. National Laboratories.

    Energy Technology Data Exchange (ETDEWEB)

    Haddal, Risa; Jones, Rebecca (PNNL); Bersell, Bridget (PNNL); Frazar, Sarah (PNNL); Burbank, Roberta (PNNL); Stevens, Rebecca (LANL); Cain, Ron (ORNL); Kirk, Bernadette (ORNL); Morell, Sean (ORNL)

    2017-09-01

    In 2017, four U.S. National Laboratories collaborated on behalf of DOE/NNSA to explore the safeguards knowledge retention problem, identify possible approaches, and develop a strategy to address it. The one-year effort consisted of four primary tasks. First, the project sought to identify critical safeguards information at risk of loss. Second, a survey and workshop were conducted to assess nine U.S. National Laboratories' efforts to determine current safeguards knowledge retention practices and challenges, and identify best practices. Third, specific tools were developed to identify and predict critical safeguards knowledge gaps and how best to recruit in order to fill those gaps. Finally, based on findings from the first three tasks and research on other organizational approaches to address similar issues, a strategy was developed on potential knowledge retention methods, customized HR policies, and best practices that could be implemented across the National Laboratory Complex.

  7. HARMONISASI REGULASI DAN EFEKTIVITAS KELEMBAGAAN SAFEGUARD DI INDONESIA

    Directory of Open Access Journals (Sweden)

    Abdurrahman Alfaqiih

    2012-06-01

    Full Text Available The implementation of WTO agreement is not easy in accordance with the estabilished regulations, so deviations in the process of trade liberalization that press domestic indrusties will likely to take place. Therefore, it is necessary to have safety actions to actualize mutual benefits in international trade. There are many cases of safety actions conducted by many countries such as Argentine that implements safety actions to its footwear industries without adapting to WTO regulations which causes the country’s losses. The paper examines the consistency of safeguard regulations in Indonesia with safeguard regulations of WTO and its implementation reviewed from the law effectiveness. The result of the study shows that the safeguard regulations in Indonesia is in accordance with the safeguard regulations of WTO in the normative level, but in the implementation the policy is not done effectively.

  8. Application of Telepresence Technologies to Nuclear Material Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    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.

  9. The highly conserved human cytomegalovirus UL136 ORF generates multiple Golgi-localizing protein isoforms through differential translation initiation.

    Science.gov (United States)

    Liao, Huanan; Lee, Jung-Hyun; Kondo, Rikita; Katata, Marei; Imadome, Ken-Ichi; Miyado, Kenji; Inoue, Naoki; Fujiwara, Shigeyoshi; Nakamura, Hiroyuki

    2014-01-22

    The UL133-UL138 locus in the unique long b' (ULb') region of the human cytomegalovirus (HCMV) genome is considered to play certain roles in viral replication, dissemination and latency in a host cell type-dependent manner. Here we characterized the proteins encoded by UL136, one of the open reading frames (ORFs) in the locus. Comparative sequence analysis of UL136 among clinical isolates and laboratory strains indicates that its predicted amino-acid sequence is highly conserved. A polyclonal antibody against UL136 proteins (pUL136s) was raised against its carboxy-terminal region and this antibody specifically recognized at least five UL136-encoded protein isoforms of 29-17 kDa both in HCMV-infected cells and in cells transfected with a construct expressing pUL136. Immunofluorescence analysis with this antibody revealed localization of pUL136 in the Golgi apparatus. Analysis of several pUL136 mutants indicated that the putative transmembrane domain of pUL136 is required for its Golgi localization. Mutational analysis of multiple AUG codons in UL136 demonstrated that translation initiation from these AUG codons contributes in the generation of pUL136 isoforms.

  10. Minor isotope measurements for safeguarding a uranium enrichment plant

    Energy Technology Data Exchange (ETDEWEB)

    Blumkin, S.; Levin, S.A.; Von Halle, E.

    1979-03-26

    A study of the behavior of the minor uranium isotopes in enrichment cascades indicates that the measurement of their concetrations in cascade feed and withdrawal streams can be used to confirm or deny material accountability results in safeguarding an enrichment plant. In further support of safeguard measures, an indirect non-intrusive method to measure cascade uranium inventory has been devised and tested satisfactorily in a gaseous diffusion cascade.

  11. Self-neglect and adult safeguarding: findings from research

    OpenAIRE

    Braye, Suzy; Orr, David; Preston-Shoot, Michael

    2011-01-01

    This report was commissioned by the Department of Health (DH) and examines the concept of self-neglect. The relationship between self-neglect and safeguarding in the UK is a difficult one, partly because the current definition of abuse specifies harmful actions by someone other than the individual at risk. Safeguarding Adults Boards’ policies and procedures commonly contain no reference to self-neglect; occasionally they explicitly exclude it or set criteria for its inclusion\\ud \\ud The perce...

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

    Energy Technology Data Exchange (ETDEWEB)

    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

  13. FY09 Advanced Instrumentation and Active Interrogation Research for Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    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

  14. Health Information Security in Hospitals: the Application of Security Safeguards.

    Science.gov (United States)

    Mehraeen, Esmaeil; Ayatollahi, Haleh; Ahmadi, Maryam

    2016-02-01

    A hospital information system has potentials to improve the accessibility of clinical information and the quality of health care. However, the use of this system has resulted in new challenges, such as concerns over health information security. This paper aims to assess the status of information security in terms of administrative, technical and physical safeguards in the university hospitals. This was a survey study in which the participants were information technology (IT) managers (n=36) who worked in the hospitals affiliated to the top ranked medical universities (university A and university B). Data were collected using a questionnaire. The content validity of the questionnaire was examined by the experts and the reliability of the questionnaire was determined using Cronbach's coefficient alpha (α=0.75). The results showed that the administrative safeguards were arranged at a medium level. In terms of the technical safeguards and the physical safeguards, the IT managers rated them at a strong level. According to the results, among three types of security safeguards, the administrative safeguards were assessed at the medium level. To improve it, developing security policies, implementing access control models and training users are recommended.

  15. Safeguards in prototype fast breeder reactor MONJU

    Energy Technology Data Exchange (ETDEWEB)

    Deshimaru, Takehide; Tomura, Katsuji; Okuda, Yosihisa; Iwamoto, Tomonori [Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)

    1994-12-31

    MONJU is the prototype fast breeder reactor in Japan designed to have the electricity output of 280 MWe. Power Reactor and Nuclear Fuel Development Corporation (PNC) started its construction in the autumn of 1985 in Tsuruga site. The loading of the core fuel assemblies to the core have been started since October 1993 and the pre-operational test is undergoing. MONJU uses 198 MOX fuel assemblies as core fuel and 172 DU assemblies as blanket fuel. Assemblies loaded in core and stored in the ex-vessel storage tank (EVST) exist in liquid sodium. These Pu containing fuel assemblies, MOX and irradiated DU, are regarded as in the difficult-to-access area, and the flows of fuel assemblies into and out of the area are requested to be verified. The verification of the flows is designed to be made with fuel flow monitors measuring radiations, which can abridge the inspector attendance during the fuel handling. This paper describes the detailed aspects of the fuel transfers in MONJU facility and the verification of them through flow monitors together with the functions of other safeguards equipments. (author).

  16. SALE: Safeguards Analytical Laboratory Evaluation computer code

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, D.J.; Bush, W.J.; Dolan, C.A.

    1976-09-01

    The Safeguards Analytical Laboratory Evaluation (SALE) program implements an industry-wide quality control and evaluation system aimed at identifying and reducing analytical chemical measurement errors. Samples of well-characterized materials are distributed to laboratory participants at periodic intervals for determination of uranium or plutonium concentration and isotopic distributions. The results of these determinations are statistically-evaluated, and each participant is informed of the accuracy and precision of his results in a timely manner. The SALE computer code which produces the report is designed to facilitate rapid transmission of this information in order that meaningful quality control will be provided. Various statistical techniques comprise the output of the SALE computer code. Assuming an unbalanced nested design, an analysis of variance is performed in subroutine NEST resulting in a test of significance for time and analyst effects. A trend test is performed in subroutine TREND. Microfilm plots are obtained from subroutine CUMPLT. Within-laboratory standard deviations are calculated in the main program or subroutine VAREST, and between-laboratory standard deviations are calculated in SBLV. Other statistical tests are also performed. Up to 1,500 pieces of data for each nuclear material sampled by 75 (or fewer) laboratories may be analyzed with this code. The input deck necessary to run the program is shown, and input parameters are discussed in detail. Printed output and microfilm plot output are described. Output from a typical SALE run is included as a sample problem.

  17. Generations.

    Science.gov (United States)

    Chambers, David W

    2005-01-01

    Groups naturally promote their strengths and prefer values and rules that give them an identity and an advantage. This shows up as generational tensions across cohorts who share common experiences, including common elders. Dramatic cultural events in America since 1925 can help create an understanding of the differing value structures of the Silents, the Boomers, Gen Xers, and the Millennials. Differences in how these generations see motivation and values, fundamental reality, relations with others, and work are presented, as are some applications of these differences to the dental profession.

  18. Supporting Technical Work Under IAEA Safeguards Agreements of 2013 Completed by Laboratory of Technical Research for Nuclear Safeguards

    Institute of Scientific and Technical Information of China (English)

    GAO; Qiang; LIU; Hong-bin; YANG; Qun; BU; Li-xin; MIAO; Qiang; HE; Li-xia; XU; Zheng; ZHANG; Wen-liang

    2013-01-01

    Safeguards applied by the International Atomic Energy Agency(IAEA)are an important element of the global nuclear non-proliferation regime.In order to verify that commitments made by states under safeguards agreements with the IAEA are fulfilled.China signed the voluntary offer agreement(INFCIRC/369)with IAEA in 1988.The agreement entered into force in 1989.There are three nuclear

  19. Sensitivity of Global Modeling Initiative CTM predictions of Antarctic ozone recovery to GCM and DAS generated meteorological fields

    Energy Technology Data Exchange (ETDEWEB)

    Rotman, D; Bergmann, D

    2003-12-04

    We use the Global Modeling Initiative chemistry and transport model to simulate the evolution of stratospheric ozone between 1995 and 2030, using boundary conditions consistent with the recent World Meteorological Organization ozone assessment. We compare the Antarctic ozone recovery predictions of two simulations, one driven by meteorological data from a general circulation model (GCM), the other using the output of a data assimilation system (DAS), to examine the sensitivity of Antarctic ozone recovery predictions to the characteristic dynamical differences between GCM and DAS-generated meteorological data. Although the age of air in the Antarctic lower stratosphere differs by a factor of 2 between the simulations, we find little sensitivity of the 1995-2030 Antarctic ozone recovery between 350 K and 650 K to the differing meteorological fields, particularly when the recovery is specified in mixing ratio units. Relative changes are smaller in the DAS-driven simulation compared to the GCM-driven simulation due to a surplus of Antarctic ozone in the DAS-driven simulation which is not consistent with observations. The peak ozone change between 1995 and 2030 in both simulations is {approx}20% lower than photochemical expectations, indicating that changes in ozone transport at 450 K between 1995 and 2030 constitute a small negative feedback. Total winter/spring ozone loss during the base year (1995) of both simulations and the rate of ozone loss during August and September is somewhat weaker than observed. This appears to be due to underestimates of Antarctic Cl{sub y} at the 450 K potential temperature level.

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

    Energy Technology Data Exchange (ETDEWEB)

    Ehinger, Michael H [ORNL; Johnson, Shirley [Tucker Creek Consulting

    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.

  1. ELECTROCHEMICALLY-MODULATED SEPARATIONS FOR SAFEGUARDS MEASUREMENTS

    Energy Technology Data Exchange (ETDEWEB)

    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

  2. Safeguard monitoring of direct electrolytic reduction

    Science.gov (United States)

    Jurovitzki, Abraham L.

    Nuclear power is regaining global prominence as a sustainable energy source as the world faces the consequences of depending on limited fossil based, CO2 emitting fuels. A key component to achieving this sustainability is to implement a closed nuclear fuel cycle. Without achieving this goal, a relatively small fraction of the energy value in nuclear fuel is actually utilized. This involves recycling of spent nuclear fuel (SNF)---separating fissile actinides from waste products and using them to fabricate fresh fuel. Pyroprocessing is a viable option being developed for this purpose with a host of benefits compared to other recycling options, such as PUREX. Notably, pyroprocessing is ill suited to separate pure plutonium from spent fuel and thus has non-proliferation benefits. Pyroprocessing involves high temperature electrochemical and chemical processing of SNF in a molten salt electrolyte. During this batch process, several intermediate and final streams are produced that contain radioactive material. While pyroprocessing is ineffective at separating pure plutonium, there are various process misuse scenarios that could result in diversion of impure plutonium into one or more of these streams. This is a proliferation risk that should be addressed with innovative safeguards technology. One approach to meeting this challenge is to develop real time monitoring techniques that can be implemented in the hot cells and coupled with the various unit operations involved with pyroprocessing. Current state of the art monitoring techniques involve external chemical assaying which requires sample removal from these unit operations. These methods do not meet International Atomic Energy Agency's (IAEA) timeliness requirements. In this work, a number of monitoring techniques were assessed for their viability as online monitoring tools. A hypothetical diversion scenario for the direct electrolytic reduction process was experimentally verified (using Nd2O3 as a surrogate for PuO2

  3. Implementation of integrated safeguards at nuclear fuel plant Pitesti Romania

    Energy Technology Data Exchange (ETDEWEB)

    Olaru, Vasilica; Tiberiu, Ivana; Epure, Gheorghe [Nuclear Safety Department, Nuclear Fuel Plant Pitesti, Cimpului, No 1, 115400 Mioveni (Romania)

    2010-07-01

    The nuclear activity in Romania was for many years under Traditional Safeguards (TS) and has developed in good conditions this type of nuclear safeguards. Now it has the opportunity to improve the performance and quality of the safeguards activity and increase the accountancy and control of nuclear material by passing to Integrated Safeguards (IS). The legal framework is Law 100/2000 for ratification of the Protocol between Romania and International Atomic Energy Agency (IAEA), additional to the Agreement between the Socialist Republic of Romania Government and IAEA related to safeguards as part of the Treaty on the non-proliferation of nuclear weapons published in the Official Gazette no. 3/31 January 1970, and the Additional Protocol content published in the Official Gazette no. 295/ 29.06.2000. The first discussion about Integrated Safeguards (IS) between Nuclear Fuel Plant (FCN) representatives and IAEA inspectors was in June 2005. In Feb. 2007 an IAEA mission visited FCN and established the main steps for implementing the IS. There were visited the storages, technological flow, and was reviewed the residence times for different nuclear materials, the applied chemical analysis, metrological methods, weighting method and elaborating the documents and lists. At that time the IAEA and FCN representatives established the main points for starting the IS at FCN: perform the Short Notice Random Inspections (SNRI), communicate the eligible days for SNRI for each year, communicate the estimated deliveries and shipments for first quarter and then for the rest of the year, daily mail box declaration (DD) with respect to the residence time for several nuclear material, advance notification (AN) for each nuclear material transfer (shipments and receipts), others. At 01 June 2007 Romania has passed officially to Integrated Safeguards and FCN (RO-D) has taken all measures to realize this objective. (authors)

  4. A Study on Effects of Initial Conditions to the Fuel Integrity Analysis of Steam Generator Tube Rupture Accident

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Min Seok; Kim, Ung Soo; Park, Min Soo; Huh, Jae Young; Lee, Gyu Cheon [KEPCO, Daejeon (Korea, Republic of)

    2016-05-15

    During SGTR accident, RCS pressure continuously decreases while the core power, core flow rate and core average temperature almost do not change until reactor trip occurs. As a result, the departure from nucleate boiling ratio (DNBR) also continuously decreases, thus eroding the thermal margin to DNB. To identify no damage of the fuel cladding due to the onset of film boiling, it must be analyzed whether the heat flux is maintained below the critical heat flux or not. For this purpose, it is used to define the specified acceptable fuel design limit (SAFDL) of DNBR and evaluate that the DNBR stays above the SAFDL. Evaluating the DNBR in SGTR accident, several initial conditions are varied as that would challenge to the safety limit, or SAFDL. However, the effects of some initial conditions are complicate and difficult to be intuitively identified. The initial conditions mainly affect the minimum DNBR during SGTR accident are the initial core power, the initial RCS flow rate, the initial core inlet temperature and the initial pressurizer pressure. The conservative initial conditions for the core power and the RCS flow rate can be determined easily by qualitative evaluation. The others such as the initial core inlet temperature and the initial pressurizer pressure are complicate and difficult to be determined. From this study, it is identified that the maximum initial pressurizer pressure and the minimum initial core inlet temperature on SGTR accident most postpones the reactor trip resulting in smaller RCS inventory at the reactor trip time point. And the smaller RCS inventory at the time point of the reactor trip tends to make the DNBR undershoot larger which is a dominant factor to determine the minimum DNBR under a LOOP condition.

  5. Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities

    Energy Technology Data Exchange (ETDEWEB)

    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.

  6. Polyhomologation based on in situ generated Boron-thexyl-silaboracyclic initiating sites: a novel strategy towards the synthesis of polyethylene-based complex architectures

    KAUST Repository

    Zhang, Zhen

    2015-04-10

    A novel strategy, based on the in situ generated Boron-thexyl-silaboracyclic initiating sites for the polyhomologation of dimethylsulfoxonium methylide, has been developed for the synthesis of complex polyethylene-based architectures. As examples, the synthesis of a 4-arm polyethylene star, three (polystyrene)(polyethylene)2 3-miktoarm stars and a PE-branched double graft copolymers are given.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Badalamente, R. [Pacific Northwest Lab., Richland, WA (United States); Anzelon, G. [Lawrence Livermore National Lab., CA (United States); Deland, S. [Sandia National Labs., Albuquerque, NM (United States); Whiteson, R. [Los Alamos National Lab., NM (United States)

    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.

  9. Safeguards Approaches for Black Box Processes or Facilities

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  11. An Introduction to Nuclear Non-Proliferation and Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Haakansson, Ane; Jonter, Thomas

    2007-06-15

    The purpose of this project was to compile a course material that covers how the nuclear safeguards system has emerged and how it works today. The produced compendium is directed to both university students and people concerned by safeguards from the industry. The primary aim of the first part of this paper is to describe the historical development of this global non-proliferation system and its central tasks. A second purpose is to discuss the advantages and disadvantages of its current design in order to answer the following question: Can we today say that we have a functioning global non-proliferation system? Does it require further strengthening, and, if so, how can this be achieved? In the second section we review the verification regime within nuclear safeguards, i. e. describe the methods and techniques that are available to reassure the world community that concluded treaties are adhered to

  12. A Comparative Study on Safeguards Implementation under Bilateral Nuclear Cooperation Agreements and the IAEA Comprehensive Safeguards Agreement

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Jihye; Kim, Ki-Hyun; Lee, Young Wook [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2016-10-15

    A Nuclear Cooperation Agreement (NCA) requires several conditions, so-called obligations, on the items under the agreement such as: 1) peaceful use, 2) retransfer consent, 3) consent prior to reprocessing or enrichment and 4) safeguards and security. These obligations of the NCAs are imposed by the supplier country. The Comprehensive Safeguards Agreement (CSA) between the International Atomic Energy Agency (IAEA) and its member states require similar activities. However, there is a significant gap in nuclear material accountancy between safeguards implementation under the NCA and CSA. The difference of those two frameworks is compared herein, focusing on the unique features of the NCA safeguards and its implications are presented. In this study, the NCAs between the ROK and Canada, Australia and US were analyzed since each of them is one of the ROK’s major nuclear trading partners. The safeguards implementation under the NCA is usually specified in an Administrative Arrangement (AA) under the Agreement. The ROK has two AAs in force with Canada and Australia among 29 countries with NCA. Recently, the AA with Canada was revised in December 2015, with those concepts mentioned above. The AA with the US is currently under discussion. Cooperation in nuclear energy between two countries could be further enhanced through reliable implementation of the NCA undertakings. Taking into account the unique features of the NCA, we need to establish effective strategy for fulfilling the obligation under the Agreement.

  13. Working Toward Robust Process Monitoring for Safeguards Applications

    Energy Technology Data Exchange (ETDEWEB)

    Krichinsky, Alan M [ORNL; Bell, Lisa S [ORNL; Gilligan, Kimberly V [ORNL; Laughter, Mark D [ORNL; Miller, Paul [ORNL; Pickett, Chris A [ORNL; Richardson, Dave [ORNL; Rowe, Nathan C [ORNL; Younkin, James R [ORNL

    2010-01-01

    New safeguards technologies allow continuous monitoring of plant processes. Efforts to deploy these technologies, as described in a preponderance of literature, typically have consisted of case studies attempting to prove their efficacy in proof-of-principle installations. While the enhanced safeguards capabilities of continuous monitoring have been established, studies thus far have not addressed such challenges as manipulation of a system by a host nation. To prevent this and other such vulnerabilities, one technology, continuous load cell monitoring, was reviewed. This paper will present vulnerabilities as well as mitigation strategies that were identified.

  14. Assessment of Critical Mass Laboratory safeguards and security upgrades

    Energy Technology Data Exchange (ETDEWEB)

    Merrill, B.J.; DeMyer, J.J.

    1985-05-31

    Pacific Northwest Laboratory (PNL) conducted an evaluation of the safeguards and security systems at the Critical Mass Laboratory (CML) in February 1985, to identify appropriate upgrading actions necessary to ensure that effective and efficient systems consistent with DOE-RL policies, procedures, and site priorities are in place. Since that evaluation, there have been changes in Patrol contingency philosophy, response tactics, and distribution of manpower. Because of these changes, and at the request of DOE-RL, PNL has re-evaluated the safeguards and security systems in place at CML.

  15. Generation IV nuclear energy system initiative. Large GFR core subassemblydesign for the Gas-Cooled Fast Reactor.

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, E. A.; Kulak, R. F.; Therios, I. U.; Wei, T. Y. C.

    2006-07-31

    Gas-cooled fast reactor (GFR) designs are being developed to meet Gen IV goals of sustainability, economics, safety and reliability, and proliferation resistance and physical protection as part of an International Generation IV Nuclear Energy System Research Initiative effort. Different organizations are involved in the development of a variety of GFR design concepts. The current analysis has focused on the evaluation of low-pressure drop, pin-core designs with favorable passive cooling properties. Initial evaluation of the passive cooling safety case for the GFR during depressurized decay heat removal accidents with concurrent loss of electric power have resulted in requirements for a reduction of core power density to the 100 w/cc level and a low core pressure drop of 0.5 bars. Additional design constraints and the implementation of their constraints are evaluated in this study to enhance and passive cooling properties of the reactor. Passive cooling is made easier by a flat radial distribution of the decay heat. One goal of this study was to evaluate the radial power distribution and determine to what extent it can be flattened, since the decay heat is nearly proportional to the fission power at shutdown. In line with this investigation of the radial power profile, an assessment was also made of the control rod configuration. The layout provided a large number of control rod locations with a fixed area provided for control rods. The number of control rods was consistent with other fast reactor designs. The adequacy of the available control rod locations was evaluated. Future studies will be needed to optimize the control rod designs and evaluate the shutdown system. The case for low pressure drop core can be improved by the minimization of pressure drop sources such as the number of required fuel spacers in the subassembly design and by the details of the fuel pin design. The fuel pin design is determined by a number of neutronic, thermal-hydraulic (gas dynamics

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

    Energy Technology Data Exchange (ETDEWEB)

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

    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.

  17. 13 CFR 107.506 - Safeguarding Licensee's assets/Internal controls.

    Science.gov (United States)

    2010-01-01

    .../Internal controls. 107.506 Section 107.506 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION... Safeguarding Licensee's assets/Internal controls. You must adopt a plan to safeguard your assets and monitor... your control procedures....

  18. Dominant Role Of The Explosively Expanding Armature On The Initiation Of Electric Discharge In Magnetic Flux Compression Generators

    Science.gov (United States)

    2009-06-01

    Nd2Fe14B high-energy hard ferromagnets. The FMG-LFCG pulsed power systems that we studied were completely autonomous, being powered exclusively by...were initiated [Fig. 3(A)] and the HE charge (0.7 g of C-4) loaded in central hole of the Nd2Fe14B hard ferromagnetic ring was detonated. A bright...light is clearly visible in the central hole of the Nd2Fe14B ferromagnet [Fig. 3(B)] due to the initiation of the HE charge. This process of

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Henry, C.N. (comp.)

    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.

  1. Initial benchmarking of a new electron-beam raster pattern generator for 130-100 nm maskmaking

    Science.gov (United States)

    Sauer, Charles A.; Abboud, Frank E.; Babin, Sergey V.; Chakarian, Varoujan; Ghanbari, Abe; Innes, Robert; Trost, David; Raymond, Frederick, III

    2000-07-01

    The decision by the Semiconductor Industry Association (SIA) to accelerate the continuing evolution to smaller linewidths is consistent with the commitment by Etec Systems, Inc. to rapidly develop new technologies for pattern generation systems with improved resolution, critical dimension (CD) uniformity, positional accuracy, and throughput. Current pattern generation designs are inadequate to meet the more advanced requirements for masks, particularly at or below the 100 nm node. Major changes to all pattern generation tools will be essential to meet future market requirements. An electron-beam (e-beam) system that is designed to meet the challenges for 130 - 100 nm device generation with extendibility to the 70-nm range will be discussed. This system has an architecture that includes a graybeam writing strategy, a new state system, and improved thermal management. Detailed changes include a pulse width modulated blanking system, per-pixel deflection, retrograde scanning multipass writing, and a column with a 50 kV accelerating voltage that supports a dose of up to 45 (mu) C/cm2 with minimal amounts of resist heating. This paper examines current issues, our approach to meeting International Technology Roadmap for Semiconductors (ITRS) requirements, and some preliminary results from a new pattern generator.

  2. Controlled synthesis of biodegradable lactide polymers and copolymers using novel in situ generated or single-site stereoselective polymerization initiators

    NARCIS (Netherlands)

    Zhong, Zhiyuan; Dijkstra, Pieter J.; Feijen, Jan

    2004-01-01

    Polylactides and their copolymers are key biodegradable polymers used widely in biomedical, pharmaceutical and ecological applications. The development of synthetic pathways and catalyst/initiator systems to produce pre-designed polylactides, as well as the fundamental understanding of the polymeriz

  3. Comparison for thorium fuel cycle facilities of two different capacities for implementation of safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Gangotra, Suresh, E-mail: sgangotra@yahoo.co.in; Grover, R.B.; Ramakumar, K.L.

    2013-09-15

    Highlights: • Facilities for implementation of safeguards for thorium fuel cycle have been compared. • Two concepts have been compared. • In one concept, the facilities are designed in hub and spoke concept. • In second concept the facilities are designed as self-contained concept. • The comparison is done on a number of factors, which affect safeguardability and proliferation resistance. -- Abstract: Thorium based nuclear fuel cycle has many attractive features, its inherent proliferation resistance being one of them. This is due to the presence of high energy gamma emitting daughter products of U{sup 232} associated with U{sup 233}. This high energy gamma radiation also poses challenges in nuclear material accounting. A typical thorium fuel cycle facility has a number of plants including a fuel fabrication plant for initial and equilibrium core, a reprocessed U{sup 233} fuel fabrication plant, a reprocessing plant, a fuel assembly/disassembly plant and associated waste handling and management plants. A thorium fuel cycle facility can be set up to serve reactors at a site. Alternatively, one can follow a hub and spoke approach with a large thorium fuel cycle facility acting as a hub, catering to the requirements of reactors at several sites as spokes. These two concepts have their respective merits and shortcomings in terms of engineering and economics. The present paper is aimed at comparing the merits and challenges for implementation of safeguards on the two concepts viz. a large fuel cycle hub catering to reactors at several sites versus a small fuel cycle facility dedicated to reactors at a single site.

  4. 10 CFR Appendix C to Part 73 - Nuclear Power Plant Safeguards Contingency Plans

    Science.gov (United States)

    2010-01-01

    ... recommendations of the safeguards contingency plan review, management findings on whether the safeguards.... Licensee's Organizational Structure for Contingency Responses—A delineation of the organization's chain of... safeguards contingency will be easily accessible, in good working order, and in sufficient supply to...

  5. 75 FR 8154 - Advisory Committee on Reactor Safeguards

    Science.gov (United States)

    2010-02-23

    ... NRC staff regarding new advanced reactor designs such as NuScale, Iris, Babcock and Wilcox Modular... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards In accordance with the purposes of Sections 29 and...

  6. Nuclear Safeguards and the International Atomic Energy Agency

    Science.gov (United States)

    1995-04-01

    Control and Disarmament McLean, VA AecBurton F. Judson Agency David Dorn Consultant Washington, DC United Nations Special Los Gatos , CA Henry Sokolski...admitted to conducting nuclear activities safeguards are willing to cede additional soy - there. If the request for such a "special inspec- ereignty to

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  8. 5 CFR 293.106 - Safeguarding information about individuals.

    Science.gov (United States)

    2010-01-01

    ... individuals. 293.106 Section 293.106 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL SERVICE REGULATIONS PERSONNEL RECORDS Basic Policies on Maintenance of Personnel Records § 293.106 Safeguarding information about individuals. (a) To ensure the security and confidentiality of personnel records,...

  9. 5 CFR 293.107 - Special safeguards for automated records.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Special safeguards for automated records. 293.107 Section 293.107 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL SERVICE REGULATIONS PERSONNEL RECORDS Basic Policies on Maintenance of Personnel Records § 293.107 Special...

  10. 75 FR 25200 - WTO Agricultural Safeguard Trigger Levels

    Science.gov (United States)

    2010-05-07

    ... to December 31, 2010. kilograms. American-Type Cheese 7,093,001 January 1, 2010 to December 31, 2010. kilograms. Edam/Gouda Cheese 7,019,833 January 1, 2010 to December 31, 2010. kilograms. Italian-Type Cheese... Round negotiations, and only one type of safeguard, price or quantity, may be applied at any given...

  11. Progress Towards Deployable Antineutrino Detectors for Reactor Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Bowden, N; Bernstein, A; Dazeley, S; Keefer, G; Reyna, D; Cabrera-Palmer, B; Kiff, S

    2010-04-05

    Fission reactors emit large numbers of antineutrinos and this flux may be useful for the measurement of two quantities of interest for reactor safeguards: the reactor's power and plutonium inventory throughout its cycle. The high antineutrino flux and relatively low background rates means that simple cubic meter scale detectors at tens of meters standoff can record hundreds or thousands of antineutrino events per day. Such antineutrino detectors would add online, quasi-real-time bulk material accountancy to the set of reactor monitoring tools available to the IAEA and other safeguards agencies with minimal impact on reactor operations. Between 2003 and 2008, our LLNL/SNL collaboration successfully deployed several prototype safeguards detectors at a commercial reactor in order to test both the method and the practicality of its implementation in the field. Partially on the strength of the results obtained from these deployments, an Experts Meeting was convened by the IAEA Novel Technologies Group in 2008 to assess current antineutrino detection technology and examine how it might be incorporated into the safeguards regime. Here we present a summary of our previous deployments and discuss current work that seeks to provide expanded capabilities suggested by the Experts Panel, in particular aboveground detector operation.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-11-01

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

  13. 34 CFR 300.150 - SEA implementation of procedural safeguards.

    Science.gov (United States)

    2010-07-01

    ... EDUCATION OF CHILDREN WITH DISABILITIES State Eligibility Sea Responsibility for General Supervision and... 34 Education 2 2010-07-01 2010-07-01 false SEA implementation of procedural safeguards. 300.150 Section 300.150 Education Regulations of the Offices of the Department of Education (Continued) OFFICE...

  14. Safeguards Issues at Nuclear Reactors and Enrichment Plants

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, Brian D [Los Alamos National Laboratory

    2012-08-15

    The Agency's safeguards technical objective is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection.

  15. 41 CFR 101-28.306-5 - Safeguards.

    Science.gov (United States)

    2010-07-01

    ... all orders filled by the CSC with the exception of orders picked up at the CSC by the customer. GSA... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Safeguards. 101-28.306-5 Section 101-28.306-5 Public Contracts and Property Management Federal Property Management Regulations...

  16. Safeguarding the welfare of children: what is the nurse's role?

    Science.gov (United States)

    El-Radhi, A Sahib

    Everyone who works with children, including teachers, GPs, other medical professionals and the police, has a responsibility to keep children safe and protect them from harm. Simply put, safeguarding children is everyone's responsibility. Children should be protected from maltreatment and any impairment that may affect their health and development. In addition, we all have to ensure that children grow up with safe and effective care. At particular risk, and therefore in particular need of safeguarding, are children who are disabled; who have educational or other specific additional needs; and who bear signs of child abuse, substance abuse, or domestic violence. Under the Children Act 1989, local authorities are required to provide services for children in need for the purposes of safeguarding and promoting their welfare. Nurses are well-placed to identify children and young people who may be at risk, and to act to safeguard them. Nurses and other health professionals should be familiar with local referral arrangements, usually to children's social care.

  17. 26 CFR 301.6803-1 - Accounting and safeguarding.

    Science.gov (United States)

    2010-04-01

    ... 26 Internal Revenue 18 2010-04-01 2010-04-01 false Accounting and safeguarding. 301.6803-1 Section 301.6803-1 Internal Revenue INTERNAL REVENUE SERVICE, DEPARTMENT OF THE TREASURY (CONTINUED) PROCEDURE AND ADMINISTRATION PROCEDURE AND ADMINISTRATION General Provisions Relating to Stamps § 301.6803-1...

  18. Role for Federal Government in Safeguarding Student Data Privacy

    Science.gov (United States)

    Barnes, Khaliah; Kowalski, Paige

    2016-01-01

    Unsurprisingly, schools, companies, and others that have amassed student information have been unable to adequately safeguard it. They simply cannot keep up with all the data they have collected and have routinely experienced data breaches. These breaches have compromised grades, student financial information, Social Security numbers, and even…

  19. Safeguarding and Promoting Human Rights and Building a Harmonious World

    Institute of Scientific and Technical Information of China (English)

    CHEN SHIQIU

    2007-01-01

    @@ It is the common wish of the people from all over the world as well as the inexorable demand for the progress of human society to build a harmonious world of lasting peace and common prosperity. Many preconditions are indispensable for building a harmonious world, one of which is to abide by the international laws on human rights and safeguard and promote human rights.

  20. Initial operation of a new generation of highly efficient absorption heat pumps in Maastricht/Netherlands. Inbetriebnahme einer neuen Generation hocheffizienter Absorptionswaermepumpen in Maastricht/NL

    Energy Technology Data Exchange (ETDEWEB)

    Schneider-Weyergraf, R. (Ingenieurbuero Colibri (Netherlands)); Veelken, H. (Ingenieurbuero Colibri (Netherlands))

    1993-12-01

    No better place or time could have been chosen: In april '93, two weeks before the opening of the 4. Int. HEAT PUMP CONFERENCE in Maastricht/NL, the first type of a new generation of high efficient absorption heat pumps was installed in the government building in Maastricht. The ABRES 250 is a gas driven machine, which is operating with ammonia as the refrigerant. Her special merits are her high efficiency and her compactness. The high COP (coefficient of performance) is realised by a perfected process, by which the machine is driven continuously between a single- and two-stage process depending on the working conditions. Its low size results from the consequent use of compact heat exchangers of the plate-fin-heat-exchanger type. (orig.)

  1. High levels of the adhesion molecule CD44 on leukemic cells generate acute myeloid leukemia relapse after withdrawal of the initial transforming event

    OpenAIRE

    Quéré, R.; Andradottir, S; Brun, A C M; Zubarev, R.A.; Karlsson, G; Olsson, K.; Magnusson, M.; Cammenga, J; Karlsson, S.

    2010-01-01

    Multiple genetic hits are detected in patients with acute myeloid leukemia (AML). To investigate this further, we developed a tetracycline-inducible mouse model of AML, in which the initial transforming event, overexpression of HOXA10, can be eliminated. Continuous overexpression of HOXA10 is required to generate AML in primary recipient mice, but is not essential for maintenance of the leukemia. Transplantation of AML to secondary recipients showed that in established leukemias, ∼80% of the ...

  2. Computation of a leakage in a stream generator heating tube with realistic initial and boundary conditions; Berechnung eines Dampferzeugerheizrohrlecks mit realistischen Anfangs- und Randbedingungen

    Energy Technology Data Exchange (ETDEWEB)

    Sarkadi, Peter; Schaffrath, Andreas [TUeV NORD SysTec GmbH und Co. KG, Hamburg (Germany)

    2009-07-01

    In the frame of a PWR reactor safety analysis the TUEV Nord Sys Tec GmbH has analyzed the plant behavior in case of a steam generator tube leakage using the thermal hydraulic code ATHLET and realistic initial and boundary conditions. The aim of the analysis was to show that the response of the emergency cooling criteria including the activation of safety injection pumps can be avoided. The Activation of the safety injection pumps could jeopardize the activity retention.

  3. The slope of the initial temperature drop predicts acute pulmonary vein isolation using the second-generation cryoballoon.

    Science.gov (United States)

    Deubner, Nikolas; Greiss, Harald; Akkaya, Ersan; Zaltsberg, Sergey; Hain, Andreas; Berkowitsch, Alexander; Güttler, Norbert; Kuniss, Malte; Neumann, Thomas

    2017-09-01

    There is no objective, early indicator of occlusion quality, and efficacy of cryoballoon pulmonary vein isolation. As previous experience suggests that the initial cooling rate correlates with these parameters, we investigated the slope of the initial temperature drop as an objective measure. A systematic evaluation of 523 cryoapplications in 105 patients using a serial ROC-AUC analysis was performed. We found the slope of a linear regression of the temperature-time function to be a good predictor (PPV 0.9, specificity 0.72, sensitivity 0.71, and ROC-AUC 0.75) of acute isolation. It also correlated with nadir temperatures (P< 0.001, adjusted R2= 0.43), predicted very low nadir temperatures, and varied according to visual occlusion grades (ANOVA P< 0.001). About 25 s after freeze initiation, the temperature-time slope predicts important key characteristics of a cryoablation, such as nadir temperature. The slope is the only reported predictor to actually precede acute isolation and thus to support decisions about pull-down manoeuvres or aborting a cryoablation early on. It is also predictive of very low nadir temperatures and phrenic nerve palsy and thus may add to patient safety.

  4. Initial soil moisture effects on flash flood generation - A comparison between basins of contrasting hydro-climatic conditions

    Science.gov (United States)

    Grillakis, M. G.; Koutroulis, A. G.; Komma, J.; Tsanis, I. K.; Wagner, W.; Blöschl, G.

    2016-10-01

    The purpose of this paper is to contribute to the understanding of the importance of the initial soil moisture state for flash flood magnitudes. Four extreme events that occurred in different case study regions were analysed, one winter and one autumn flash flood in the Giofiros and Almirida catchments in Crete, and two summer floods in the Rastenberg catchment in Austria. The hydrological processes were simulated by the spatially distributed flash flood model Kampus. For the Crete cases Kampus model was calibrated against remotely sensed soil moisture while for the Austrian case the model was calibrated against observed runoff. Kampus model was then used to estimate the sensitivity of the stream flow peak to initial soil moisture. The largest of the events analysed (in terms of specific peak discharge) was found to have a sensitivity of less than 0.2% flood peak change per % soil moisture change while the smallest event had a sensitivity of more than 3% flood peak change per % soil moisture change. This suggests that initial soil moisture effects on the flash flood response probably depend on event magnitude rather than on the climate or region. Moreover, the Austrian catchment was found to exhibit a more nonlinear relationship between antecedent soil moisture and the peak discharge than the Cretan catchments which was explained by differences in the soil type.

  5. Security, Extremism and Education: Safeguarding or Surveillance?

    Science.gov (United States)

    Davies, Lynn

    2016-01-01

    This article analyses how education is positioned in the current concerns about security and extremism. This means firstly examining the different meanings of security (national, human and societal) and who provides security for whom. Initially, a central dilemma is acknowledged: that schooling appears to be simultaneously irrelevant to the huge…

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  7. High levels of the adhesion molecule CD44 on leukemic cells generate acute myeloid leukemia relapse after withdrawal of the initial transforming event.

    Science.gov (United States)

    Quéré, R; Andradottir, S; Brun, A C M; Zubarev, R A; Karlsson, G; Olsson, K; Magnusson, M; Cammenga, J; Karlsson, S

    2011-03-01

    Multiple genetic hits are detected in patients with acute myeloid leukemia (AML). To investigate this further, we developed a tetracycline-inducible mouse model of AML, in which the initial transforming event, overexpression of HOXA10, can be eliminated. Continuous overexpression of HOXA10 is required to generate AML in primary recipient mice, but is not essential for maintenance of the leukemia. Transplantation of AML to secondary recipients showed that in established leukemias, ∼80% of the leukemia-initiating cells (LICs) in bone marrow stopped proliferating upon withdrawal of HOXA10 overexpression. However, the population of LICs in primary recipients is heterogeneous, as ∼20% of the LICs induce leukemia in secondary recipients despite elimination of HOXA10-induced overexpression. Intrinsic genetic activation of several proto-oncogenes was observed in leukemic cells resistant to inactivation of the initial transformation event. Interestingly, high levels of the adhesion molecule CD44 on leukemic cells are essential to generate leukemia after removal of the primary event. This suggests that extrinsic niche-dependent factors are also involved in the host-dependent outgrowth of leukemias after withdrawal of HOXA10 overexpression event that initiates the leukemia.

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

    Science.gov (United States)

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

    2013-11-01

    have therefore reached high level of attention for safeguards authorities. Furthermore, IRMM initiated and coordinated the development of a Modified Total Evaporation (MTE) technique for accurate abundance ratio measurements of the "minor" isotope-amount ratios of uranium and plutonium in nuclear material and, in combination with a multi-dynamic measurement technique and filament carburization, in environmental samples. Currently IRMM is engaged in a study on the development of plutonium reference materials for "age dating", i.e. determination of the time elapsed since the last separation of plutonium from its daughter nuclides. The decay of a radioactive parent isotope and the build-up of a corresponding amount of daughter nuclide serve as chronometer to calculate the age of a nuclear material. There are no such certified reference materials available yet.

  9. The application of state-level integration of safeguards in Sweden. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Dahlin, G.; Haeggblom, E.; Larsson, Mats; Rehn, I

    2000-12-01

    The role of Sweden in disarmament and non-proliferation efforts extends from the late 1940's to the present. It covers active support to place nuclear weapons under international control and participation in practically all control regimes aimed at non-proliferation and elimination of any mass destruction capability. Sweden has also made available highly competent and high-ranking officers to serve many of the institutions and organisations supporting the political work and operative functions in this field. Until 1968, Sweden had a double-track policy where both the nuclear weapons option and non-proliferation as a possibility were pursued and investigated. After 1968, non-proliferation became the established policy, and the nuclear programme, materials and activities have since served exclusively peaceful purposes. It appears possible that the IAEA could, after a short period of initial implementation, be in a position to draw conclusions on the absence of undeclared nuclear materials and activities in Sweden. Sweden has undertaken to ensure the transparency of its nuclear programme by providing all relevant information and by facilitating physical access, as necessary, and by addressing any questions and issues of concern in a direct and open-minded manner. The implementation of traditional safeguards should continue effectively, to enable the Agency to draw its conclusions on the absence of diversion of declared nuclear material in Sweden in the future. Using its reporting mechanisms, the Agency should share these conclusions with Member States so as to ensure that the objectives of the strengthened safeguards are met. Under these conditions, IAEA could and would decide to proceed with the implementation of integrated safeguard measures at the declared facilities and locations in Sweden. It is proposed that IAEA would participate in annual PIV's, but would, however, detach from routine verification work to the extent possible and make full use of the

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-08-12

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-09-01

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

  12. Uncertainty Quantification for Nuclear Safeguards and Non-Destructive Assay - Fact Sheet

    Energy Technology Data Exchange (ETDEWEB)

    Croft, Stephen [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Nicholson, Andrew D [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    UQ is the scientific art of generating confidence statements. Without defensible UQ physical measurements and calculations have no meaning. The UQ team performed a series of case studies with the following results: minimum detectable activity of a Tomographic Gamma-Ray Scanning system was determined using the Currie formalism. Bootstrapping method was used to generate fluorescence yield parameters and uncertainties. For Hybrid K-Edge Densitometry (HKED) measurements, these parameters can be used to predict the concentration of plutonium and quantify uncertainty in HKED models for nuclear safeguards measurements. Detection efficiency was determined for a coincidence counter using covariance data. The use of covariance information drastically reduced the total uncertainty in the average detection efficiency.

  13. Integrated Safeguards and Security Management Self-Assessment 2004

    Energy Technology Data Exchange (ETDEWEB)

    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

  14. Measurements and automated mechanism generation modeling of OH production in photolytically initiated oxidation of the neopentyl radical.

    Science.gov (United States)

    Petway, Sarah V; Ismail, Huzeifa; Green, William H; Estupiñan, Edgar G; Jusinski, Leonard E; Taatjes, Craig A

    2007-05-17

    Production of OH in the reaction of the neopentyl radical with O2 has been measured by a laser photolysis/cw absorption method for various pressures and oxygen concentrations at 673, 700, and 725 K. The MIT Reaction Mechanism Generator (RMG) was used to automatically generate a model for this system, and the predicted OH concentration profiles are compared to present and literature experimental results. Several reactions significantly affect the OH profile. The experimental data provide useful constraints on the rate coefficient for the formally direct chemical activation reaction of neopentyl radical with O2 to form OH (CH3)3CCH2 + O2 --> OH + 3,3-dimethyloxetane (Rxn 1) At 673 K and 60 Torr, log k(1) (cm(3) molecule(-1) s(-1)) = -13.7 +/- 0.5. Absolute absorbance measurements on OH and I indicate that the branching ratio for R + O2 to OH is about 0.03 under these conditions. The data suggest that the ab initio neopentyl + O2 potential energy surface of Sun and Bozzelli is accurate to within 2 kcal mol(-1).

  15. Safeguarding End-User Military Software

    Science.gov (United States)

    2014-12-04

    provided specification. We instantiated and evaluated this approach in subsets of three languages, the Java String library, Yahoo! Pipes mashup language...particular, we have studied the ability of 30 users, across two empirical stud- ies, to classify invariants generated from three Java programs. Our results...relevant domain of Android mobile applications. The study revealed that 22% of the confirmed and fixed bugs have to do with poor excep- tional handling

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  17. A Hubble Astrometry Initiative: Laying the Foundation for the Next-Generation Proper-Motion Survey of the Local Group

    CERN Document Server

    Kallivayalil, Nitya; Simon, Joshua D; Boylan-Kolchin, Michael; Deason, Alis J; Fritz, Tobias K; Geha, Marla; Sohn, Sangmo Tony; Weisz, Daniel R

    2015-01-01

    High-precision astrometry throughout the Local Group is a unique capability of the Hubble Space Telescope (HST), with potential for transformative science, including constraining the nature of dark matter, probing the epoch of reionization, and understanding key physics of galaxy evolution. While Gaia will provide unparalleled astrometric precision for bright stars in the inner halo of the Milky Way, HST is the only current mission capable of measuring accurate proper motions for systems at greater distances (> 80 kpc), which represents the vast majority of galaxies in the Local Group. The next generation of proper-motion measurements will require long time baselines, spanning many years to decades and possibly multiple telescopes, combining HST with the James Webb Space Telescope (JWST) or the Wide-Field Infrared Survey Telescope (WFIRST). However, the current HST allocation process is not conducive to such multi-cycle/multi-mission science, which will bear fruit primarily over many years. We propose an HST ...

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

    Science.gov (United States)

    Griffith, Richard; Tengnah, Cassam

    2012-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    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. Safeguarding vulnerable families: work with refugees and asylum seekers.

    Science.gov (United States)

    Burchill, John

    2011-02-01

    This paper will highlight one of the key findings of a qualitative study based on the analysis of in-depth interviews with 14 health visitors describing their experiences working with refugees and asylum seekers. Despite changes in government legislation to improve children's services in order to prevent harm to children, this recent study demonstrated that health visitors were working with the complexities of needs among refugees and asylum seekers related to safeguarding both children and vulnerable women. The health visitors often worked with families and individuals with no support from other professional services, they worked with failed asylum seekers who were unable to access other forms of support and they worked with women and children who were caught in a cycle of domestic abuse due to their immigration status. They were also working with families who would disappear from the systems in place to safeguard children.

  1. Using Highly Interactive Virtual Environments for Safeguards Activities

    Energy Technology Data Exchange (ETDEWEB)

    Weil, Bradley S [ORNL; Alcala, Benjamin S [ORNL; Alcala, Scott [ORNL; Eipeldauer, Mary D [ORNL; Weil, Logan B [ORNL

    2010-01-01

    Highly interactive virtual environment (HIVE) is a term that refers to interactive educational simulations, serious games and virtual worlds. Studies indicate that learning with the aid of interactive environments produces better retention and depth of knowledge by promoting improved trainee engagement and understanding. Virtual reality or three dimensional (3D) visualization is often used to promote the understanding of something when personal observation, photographs, drawings, and/or sketches are not possible or available. Subjects and situations, either real or hypothetical, can be developed using a 3D model. Models can be tailored to the audience allowing safeguards and security features to be demonstrated for educational purposes in addition to engineering evaluation and performance analysis. Oak Ridge National Laboratory (ORNL) has begun evaluating the feasibility of HIVEs for improving safeguards activities such as training, mission planning, and evaluating worker task performance. This paper will discuss the development workflow of HIVEs and present some recent examples.

  2. A second isoform of the ferredoxin:NADP oxidoreductase generated by an in-frame initiation of translation.

    Science.gov (United States)

    Thomas, Jean-Claude; Ughy, Bettina; Lagoutte, Bernard; Ajlani, Ghada

    2006-11-28

    Ferredoxin:NADP oxidoreductases (FNRs) constitute a family of flavoenzymes that catalyze the exchange of reducing equivalents between one-electron carriers and the two-electron-carrying NADP(H). The main role of FNRs in cyanobacteria and leaf plastids is to provide the NADPH for photoautotrophic metabolism. In root plastids, a distinct FNR isoform is found that has been postulated to function in the opposite direction, providing electrons for nitrogen assimilation at the expense of NADPH generated by heterotrophic metabolism. A multiple gene family encodes FNR isoenzymes in plants, whereas there is only one FNR gene (petH) in cyanobacteria. Nevertheless, we detected two FNR isoforms in the cyanobacterium Synechocystis sp. strain PCC6803. One of them (FNR(S) approximately 34 kDa) is similar in size to the plastid FNR and specifically accumulates under heterotrophic conditions, whereas the other one (FNR(L) approximately 46 kDa) contains an extra N-terminal domain that allows its association with the phycobilisome. Site-directed mutants allowed us to conclude that the smaller isoform, FNR(S), is produced from an internal ribosome entry site within the petH ORF. Thus we have uncovered a mechanism by which two isoforms are produced from a single gene, which is, to our knowledge, novel in photosynthetic bacteria. Our results strongly suggest that FNR(L) is an NADP(+) reductase, whereas FNR(S) is an NADPH oxidase.

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

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, Chantell Lynne-Marie [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-01-27

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Moses, David Lewis [ORNL

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    Henzlova, Daniela [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kouzes, R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); McElroy, R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Peerani, P. [European Commission, Ispra (Italy). Joint Research Centre; Aspinall, M. [Hybrid Instruments Ltd., Birmingham (United Kingdom); Baird, K. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Bakel, A. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Borella, M. [SCK.CEN, Mol (Belgium); Bourne, M. [Univ. of Michigan, Ann Arbor, MI (United States); Bourva, L. [Canberra Ltd., Oxford (United Kingdom); Cave, F. [Hybrid Instruments Ltd., Birmingham (United Kingdom); Chandra, R. [Arktis Radiation Detectors Ltd., Zurich (Sweden); Chernikova, D. [Chalmers Univ. of Technology (Sweden); Croft, S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dermody, G. [Symetrica Inc., Maynard, MA (United States); Dougan, A. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Ely, J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fanchini, E. [Istituto Nazionale di Fisica Nucleare (INFN), Milano (Italy); Finocchiaro, P. [Istituto Nazionale di Fisica Nucleare (INFN), Milano (Italy); Gavron, Victor [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kureta, M. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Ianakiev, Kiril Dimitrov [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ishiyama, K. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Lee, T. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Martin, Ch. [Symetrica Inc., Maynard, MA (United States); McKinny, K. [GE Reuter-Stokes, Twinsburg, OH (United States); Menlove, Howard Olsen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Orton, Ch. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Pappalardo, A. [Istituto Nazionale di Fisica Nucleare (INFN), Milano (Italy); Pedersen, B. [European Commission, Ispra (Italy). Joint Research Centre; Peranteau, D. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Plenteda, R. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Pozzi, S. [Univ. of Michigan, Ann Arbor, MI (United States); Schear, M. [Symetrica Inc., Maynard, MA (United States); Seya, M. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Siciliano, E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Stave, S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sun, L. [Proportional Technologies Inc., Houston, TX (United States); Swinhoe, Martyn Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tagziria, H. [European Commission, Ispra (Italy). Joint Research Centre; Vaccaro, S. [DG Energy (Luxembourg); Takamine, J. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Weber, A. -L. [Inst. for Radiological Protection and Nuclear Safety (IRSN), Fontenay-aux-Roses (France); Yamaguchi, T. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Zhu, H. [National Nuclear Security Administration (NNSA), Washington, DC (United States)

    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

  6. DEVELOPMENT OF A CANDLE FILTER FAILURE SAFEGUARD DEVICE

    Energy Technology Data Exchange (ETDEWEB)

    G.J. Bruck; E.E. Smeltzer; Z.N. Sanjana

    2002-06-06

    Development, testing and optimization of advanced metal and ceramic, barrier and fiber safeguard devices (SGDs) is described. Metal barrier devices are found prone to manufacturing defects and premature blinding. Fiber devices are found to be satisfactory if fine fibers are used. Durable alloys are identified for both oxidation and gasification conditions. Ceramic honeycomb SGDs were found to perform as excellent barrier devices. Optimization has shown such devices to be durable. Field testing of ceramic honeycomb SGDs from two different manufacturers is being pursued.

  7. The role of time-dependent deformation in intergranular crack initiation of alloy 600 steam generator tubing material

    Energy Technology Data Exchange (ETDEWEB)

    Was, G.S.; Lian, K.

    1998-03-01

    Intergranular stress corrosion cracking (IGSCC) of two commercial alloy 600 conditions (600LT, 600HT) and controlled- purity Ni-18Cr-9Fe alloys (CDMA, CDTT) were investigated using constant extension rate tensile (CERT) tests in primary water (0.01M LiOH+0.01M H{sub 3}BO{sub 3}) with 1 bar hydrogen overpressure at 360{degrees}C and 320{degrees}C. Heat treatments produced two types of microstructures in both commercial and controlled-purity alloys: one dominated by grain boundary carbides (600HT and CDTT) and one dominated by intragranular carbides (600LT and CDMA). CERT tests were conducted over a range of strain rates and at two temperatures with interruptions at specific strains to determine the crack depth distributions. Results show that in all samples, IGSCC was the dominant failure mode. For both the commercial alloy and the controlled-purity alloys, the microstructure with grain boundary carbides showed delayed crack initiation and shallower crack depths than did the intragranular carbide microstructure under all experimental conditions. This data indicates that a grain boundary carbide microstructure is more resistant to IGSCC than an intragranular carbide microstructure. Observations support both the film rupture/slip dissolution mechanism and enhanced localized plasticity. The advantage of these results over previous studies is that the different carbide distributions were obtained in the same commercial alloy using different heat treatments, and in the other case, in nearly identical controlled-purity alloys. Therefore, observations of the effects of carbide distribution on IGSCC can more confidently be attributed to the carbide distribution alone rather than other potentially significant differences in microstructure or composition.

  8. Assessment of Process Monitoring Techniques for Pyro processing Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Y. E.; Kim, C. M.; Yim, M. S. [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    PM technologies can be used to inspect normal/off-normal operation with various data obtained from facility operations in real time to meet safeguards objectives. To support the use of PM technologies for the purpose of pyroprocessing safeguards, this study aims at identifying technologies that could be useful for PM purposes and evaluating their applicability to a pyroprocessing facility. This paper describes the development of the assessment criteria to evaluate the practicality of candidate technologies for PM based on a variety of requirements and considerations. By using the developed assessment criteria, application of technologies in the oxide reduction process was assessed as a test case example. Research is necessary to validate the criteria according to the needs of each unit process, perhaps based on expert elicitation and/or international collaboration with other expert organization(s). These advanced assessment criteria will serve a useful guideline for selecting appropriate candidate PM technologies for pyroprocessing safeguards. Based on the results of using these evaluation criteria, the optimum technologies can be successfully selected for use at a large scale pyroprocessing facility.

  9. STEAMakers- a global initiative to connect STEM career professionals with the public to inspire the next generation and nurture a creative approach to science, technology, maths & engineering

    Science.gov (United States)

    Shaw, Niamh; Sorkhabi, Elburz; Gasquez, Oriol; Yajima, Saho

    2016-04-01

    STEAMakers is a global initiative founded by Niamh Shaw, Elburz Sorkhabi, Oriol Gasquez & Saho Yajima, four alumni of The International Space University's Space Studies Programme 2015 who each shared a vision to inspire the next generation to embrace science, technology, engineering & maths (STEM) in new ways, by embedding the Arts within STEM, putting the 'A' in STEAM. STEAMakers invited STEM professionals around the world to join their community, providing training and a suite of STEAM events, specially designed to encourage students to perceive science, technology, engineering & maths as a set of tools with which to create, design, troubleshoot, innovate, and imagine. The ultimate goal of STEAMakers is to grow this community and create a global culture of non-linear learning among the next generation, to nurture within them a new multidisciplinary mindset and incubate new forms of innovation and thought leadership required for the future through the power of inspiration and creativity.

  10. The organisation of interagency training to safeguard children in England: a case study using realistic evaluation

    Directory of Open Access Journals (Sweden)

    Demi Patsios

    2010-11-01

    Full Text Available Background: Joint training for interagency working is carried out by Local Safeguarding Children Boards in England to promote effective local working to safeguard and promote the welfare of children.Purpose: This paper reports on the findings of the outputs and outcomes of interagency training to safeguard children in eight Local Safeguarding Children Boards.Methods: A review of Local Safeguarding Children Board documentation, observations of Local Safeguarding Children Board training sub-group meetings and a series of interviews with training key stakeholders in each Local Safeguarding Children Board were used to assess how partner agencies in the Local Safeguarding Children Boards carried out their statutory responsibilities to organise interagency training. 'Realistic Evaluation' was used to evaluate the mechanisms by which a central government mandate produced particular inter-agency training outputs (number of courses, training days and joint working outcomes (effective partnerships, within particular Local Safeguarding Children Board contexts.Results: The 'mandated partnership' imposed on Local Safeguarding Children Boards by central government left little choice but for partner agencies to work together to deliver joint training, which in turn affected the dynamics of working partnerships across the various sites. The effectiveness of the training sub group determined the success of the organisation and delivery of training for joint working. Despite having a central mandate, Local Safeguarding Children Boards had heterogeneous funding and training arrangements. These resulted in significant variations in the outputs in terms of the number of courses per 'children in need' in the locality and in the cost per course.Conclusions: Interagency training which takes account of the context of the Local Safeguarding Children Board is more likely to produce better trained staff, effective partnership working, and lead to better integrated

  11. The organisation of interagency training to safeguard children in England: a case study using realistic evaluation

    Directory of Open Access Journals (Sweden)

    Demi Patsios

    2010-11-01

    Full Text Available Background: Joint training for interagency working is carried out by Local Safeguarding Children Boards in England to promote effective local working to safeguard and promote the welfare of children. Purpose: This paper reports on the findings of the outputs and outcomes of interagency training to safeguard children in eight Local Safeguarding Children Boards. Methods: A review of Local Safeguarding Children Board documentation, observations of Local Safeguarding Children Board training sub-group meetings and a series of interviews with training key stakeholders in each Local Safeguarding Children Board were used to assess how partner agencies in the Local Safeguarding Children Boards carried out their statutory responsibilities to organise interagency training. 'Realistic Evaluation' was used to evaluate the mechanisms by which a central government mandate produced particular inter-agency training outputs (number of courses, training days and joint working outcomes (effective partnerships, within particular Local Safeguarding Children Board contexts. Results: The 'mandated partnership' imposed on Local Safeguarding Children Boards by central government left little choice but for partner agencies to work together to deliver joint training, which in turn affected the dynamics of working partnerships across the various sites. The effectiveness of the training sub group determined the success of the organisation and delivery of training for joint working. Despite having a central mandate, Local Safeguarding Children Boards had heterogeneous funding and training arrangements. These resulted in significant variations in the outputs in terms of the number of courses per 'children in need' in the locality and in the cost per course. Conclusions: Interagency training which takes account of the context of the Local Safeguarding Children Board is more likely to produce better trained staff, effective partnership working, and lead to better integrated

  12. The Net Generation Cheating Challenge

    Science.gov (United States)

    Milliron, Valerie; Sandoe, Kent

    2008-01-01

    Integral to higher education, academic integrity stands as a cornerstone of academic life. However, compelling evidence of widespread academic dishonesty among Net-Generation students threatens to undermine both the environment of trust that nourishes integrity and the safeguards that help ensure it. Working from their experience with widespread…

  13. Treatment patterns in Medicaid patients with schizophrenia initiated on a first- or second-generation long-acting injectable versus oral antipsychotic

    Directory of Open Access Journals (Sweden)

    Pilon D

    2017-03-01

    Full Text Available Dominic Pilon,1 Kruti Joshi,2 Neeta Tandon,2 Marie-Hélène Lafeuille,1 Rhiannon L Kamstra,1 Bruno Emond,1 Patrick Lefebvre2 1Groupe d’analyse, Ltée, Montréal, QC, Canada; 2Janssen Scientific Affairs, LLC, Titusville, NJ, USA Background: Poor antipsychotic (AP adherence is a key issue in patients with schizophrenia. First-generation antipsychotic (FGA and second-generation antipsychotic (SGA long-acting injectable therapies (LAI may improve adherence compared to oral antipsychotics (OAP. The objective of the study was to compare treatment adherence and persistence in Medicaid patients with schizophrenia initiated on first-generation long-acting injectable therapies (FGA-LAI or second-generation long-acting injectable therapies (SGA-LAI versus OAP.Methods: Adults with schizophrenia initiated on FGA-LAI, SGA-LAI, or OAP on or after January 2010 were identified using a six-state Medicaid database (January 2009– March 2015. Outcomes were assessed during the 12 months following treatment initiation. Index medication adherence was assessed using the proportion of days covered ≥80%, while persistence was assessed as no gap of ≥30, ≥60, or ≥90 days between days of supply. Outcomes were compared between FGA/SGA-LAI and OAP cohorts using chi-squared tests and adjusted odds ratios (OR.Results: During follow-up, AP polypharmacy was more common in FGA-LAI patients (N=1,089; 36%; P=0.029 and less common in SGA-LAI patients (N=2,209; 27%; P<0.001 versus OAP patients (N=20,478; 33%. After adjustment, SGA-LAI patients had 24% higher odds of adherence at 12 months (OR: 1.24; P<0.001, in contrast to FGA-LAI patients who had 48% lower odds of adherence (OR: 0.52; P<0.001 relative to OAP patients. SGA-LAI patients were more likely to be persistent (no gap ≥60 days at 12 months than OAP patients (37% vs 30%; P<0.001, but not FGA-LAI patients (31% vs 30%; P=0.776. In comparison to OAP patients, SGA-LAI patients had 46% higher adjusted odds of

  14. AITI and GELATI - Initiatives to promote education and training for the next generation of educators and scientists during the IPY 2007/08 and beyond

    Science.gov (United States)

    Vogel, S. W.; Bouchard, M.; Das, S.; Gillermann, J.; Greve, R.; Matsuoka, K.; Pasotti, J.; Tweedie, C.

    2005-05-01

    The fourth International Polar Year (IPY) in 2007/08 provides a unique opportunity to enhance international collaboration in research and education. Here we present an IPY-teaching initiative (AITI), which proposes to develop an interdisciplinary international short course series promoting and fostering education and training of the next generation(s) of scientists and educators interested in natural and social sciences related to Polar Regions; a short course series (GELATI) focusing on the impact of the cryosphere on the Earth system. The main goals of the short course series are to: a) provide education and training for the next generation of graduate students, science teachers, researchers in science related to Polar Regions; b) provide training for junior faculty c) integrate research and education; d) create awareness for Polar Regions related questions in class-rooms and beyond; e) create international partnerships in education and training; f) promote multidisciplinary thinking; g) increase gender diversity in science and teaching; h) encourage minority participation. To achieve these goals it is intended to develop a curriculum of specialized and interdisciplinary courses considering various aspects of science and scientific activities, which study, or are concerned with processes/developments in Polar Regions. Due to the vast dimensions and distribution of Polar Regions across international boundaries as well as the complexity of environmental studies in Polar Regions these courses will internationally pool students and instructors. Pooling of experts and students internationally will not only ensure highest standards but also foster international partnership. To allow the integration of research and teaching and to provide the best possible study environment the up to two to three weeklong, courses will be held at international field stations or will be incorporated into large research projects. To ensure training of the next generation of

  15. Advances in nuclear instrumentation for safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Prettyman, T.H.; Reilly, T.D.; Miller, M.C.; Hollas, C.L.; Pickrell, M.M.; Prommel, J.M.; Dreicer, J.S.

    1996-12-31

    This paper describes detectors, instrumentation, and analytical methods under development to address the above issues. The authors will describe work underway on room-temperature semiconductors including attempts to model the response of these detectors to improve spectrum analysis procedures and detector design. Computerized tomography is used in many medical and industrial applications; they are developing both gamma-ray and neutron tomography for improved measurements of waste and direct-use materials. Modern electronics and scintillation detectors should permit the development of fast neutron coincidence detectors with dramatically improved signal-to-noise ratios. For active measurements, they are studying several improved neutron sources, including a high-fluence, plasma-based, d-t generator. New analysis tools from information theory may permit one to better combine data from different measurement systems. This paper attempts to briefly describe a range of new sensors, electronics, and data analysis methods under study at Los Alamos and other laboratories to promote discussion of promising technology that they may bring to bear on these important global issues.

  16. First remarks on the initiative of conception and evaluation of the safety of the reactors of the fourth generation; Premieres reflexions sur la demarche de conception et d'evaluation de la surete des reacteurs de quatrieme generation

    Energy Technology Data Exchange (ETDEWEB)

    Clement, Ch.; Maliverney, B.; Mulet-Marquis, D.; Sauvage, J.F. [Electricite de France (EDF), 75 - Paris (France); Guesdon, B. [Technical Secretary (France); Carluec, B.; Ehster, S. [AREVA NP, 92 - Paris la Defense (France); Greneche, D. [AREVA NC, 78 - Velizy Villacoublay (France); Anzieu, P. [CEA Saclay, 91 - Gif sur Yvette (France); Fiorini, G.L. [CEA Cadarache, 13 - Saint Paul lez Durance (France); Rozenholc, M.; Vitton, F.; Rouyer, J.L

    2007-09-15

    The objectives of the nuclear systems of the fourth generation impose ambitious requirements which concern the sustainable development, the competitiveness, the safety, the reliability, the resistance to proliferation and the physical protection. The examination of the policies of safety applicable to these systems is led at the same moment to the national and international levels. In France, thoughts on the safety is organized within the French consultative group of safety (G.C.F.S.) which collects the industrial actors and of research and development involved in the development of the new systems. Within the framework of the initiatives of international harmonization, the G.C.F.S. suggests defining recommendations common to all the concepts of the fourth generation reactors then on the basis of this neutral frame towards the technologies, establishing specific recommendations for each of the systems. (N.C.)

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

    Science.gov (United States)

    Suzuki, Mitsutoshi; Mochiji, Toshiro

    2014-09-01

    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.

  18. Preliminary concepts: materials management in an internationally safeguarded nuclear-waste geologic repository

    Energy Technology Data Exchange (ETDEWEB)

    Ostenak, C.A.; Whitty, W.J.; Dietz, R.J.

    1979-11-01

    Preliminary concepts of materials accountability are presented for an internationally safeguarded nuclear-waste geologic repository. A hypothetical reference repository that receives nuclear waste for emplacement in a geologic medium serves to illustrate specific safeguards concepts. Nuclear wastes received at the reference repository derive from prior fuel-cycle operations. Alternative safeguards techniques ranging from item accounting to nondestructive assay and waste characteristics that affect the necessary level of safeguards are examined. Downgrading of safeguards prior to shipment to the repository is recommended whenever possible. The point in the waste cycle where international safeguards may be terminate depends on the fissile content, feasibility of separation, and practicable recoverability of the waste: termination may not be possible if spent fuels are declared as waste.

  19. Safeguards and security research and development: Program status report, February-July 1981

    Energy Technology Data Exchange (ETDEWEB)

    Henry, C.N.; Walton, R.B. (comps.)

    1982-04-01

    This report, one of a series of biannual progress reports, describes the status of research and development in the Safeguards and Security Program at Los Alamos from February-July 1981. Most work covered here is sponsored by the Office of Safeguards and Security of the Department of Energy; however, project activities that are technically closely related to nuclear safeguards and security also are included where appropriate for conveying information useful to the nuclear community. The report comprises four major subject areas: Security Development and Support; Nuclear Materials Measurement and Engineering; Nuclear Facility Safeguards Support; and International Safeguards, Technology Transfer, and Training. Some technical topics included in the subject areas are computer and informational security, chemical and nondestructive analysis of nuclear materials, process modeling and analysis, nuclear materials accounting systems, evaluation of prototype measurement instrumentation and procedures in nuclear facilities, design and consultation for facilities, technical exchange, training courses, and international safeguards.

  20. The Use of Performance Metrics for the Assessment of Safeguards Effectiveness at the State Level

    Energy Technology Data Exchange (ETDEWEB)

    Bachner K. M.; George Anzelon, Lawrence Livermore National Laboratory, Livermore, CA Yana Feldman, Lawrence Livermore National Laboratory, Livermore, CA Mark Goodman,Department of State, Washington, DC Dunbar Lockwood, National Nuclear Security Administration, Washington, DC Jonathan B. Sanborn, JBS Consulting, LLC, Arlington, VA.

    2016-07-24

    In the ongoing evolution of International Atomic Energy Agency (IAEA) safeguards at the state level, many safeguards implementation principles have been emphasized: effectiveness, efficiency, non-discrimination, transparency, focus on sensitive materials, centrality of material accountancy for detecting diversion, independence, objectivity, and grounding in technical considerations, among others. These principles are subject to differing interpretations and prioritizations and sometimes conflict. This paper is an attempt to develop metrics and address some of the potential tradeoffs inherent in choices about how various safeguards policy principles are implemented. The paper carefully defines effective safeguards, including in the context of safeguards approaches that take account of the range of state-specific factors described by the IAEA Secretariat and taken note of by the Board in September 2014, and (2) makes use of performance metrics to help document, and to make transparent, how safeguards implementation would meet such effectiveness requirements.

  1. RING-OPENING POLYMERIZAION OF 2,2-DIMETHYLTRIMETHYLENE CARBONATE INITIATED BY IN SITU GENERATED, TETRAHYDROSALEN STABLIZED YTTRIUM BOROHYDRIDE COMPLEX AND RANDOM COPOLYMERIZATION WITH ε-CAPROLACTONE

    Institute of Scientific and Technical Information of China (English)

    Jing Huang; Jian-fang Yu; Han-jian Yu; Wei-lin Sun; Zhi-quan Shen

    2011-01-01

    The poly(2,2-dimethyltrimethylene carbonate) (PDTC) with one hydroxyl and one formate tenninal fimctions was synthesized by in situ generated, tetrahydrosalen stabilized yttrium borohydride complex. The influences of monomer/initiator molar ratio, temperature and reaction time on polymerization of DTC were investigated. Under the condition: [DTC]/[I] = 500, 55℃, toluene: 0.5 mL, DTC: 0.6 g, PDTC with Mn = 15600 and PDI = 2.15 was obtained.Through 1H-NMR and 13C-NMR analyses, the structure of PDTC was characterized and a coordination-insertion mechanism was proposed. In addition, the random copolymerization of DTC and caprolactone (CL) initiated by rare-earth borohydride compound was studied. The microstructure of PDTC-co-PCL includes four diads: DTC-CL, CL-CL, DTC-DTC and CLDTC, which were determined by the specific signals in 1H-NMR spectra. Based on the typical signals of the formate (δ=8.08) and hydroxyl (δ = 3.34) end groups of PDTC-co-PCL, a mechanism involving DTC monomer inserts before CL during the initiation process was presumed. Furthermore, the thermal properties of amorphous copolymer were characterized by differential scanning calorimetry (DSC). The results support the random structure of PDTC-co-PCL.

  2. INL Active Interrogation Testing In Support of the GNEP Safeguards Campaign

    Energy Technology Data Exchange (ETDEWEB)

    David L. Chichester

    2008-04-01

    Active interrogation, a measurement technique which uses a radiation source to probe materials and generate unique signatures useful for characterizing those materials, is a powerful tool for assaying special nuclear material. Work at Idaho National Laboratory (INL) in the area of active interrogation, using neutron and photon sources, has been under way for many years to develop methods for detecting and quantifying nuclear material for national and homeland security research areas. This research knowledge base is now being extended to address nuclear safeguards and process monitoring issues related to the Global Nuclear Energy Partnership (GNEP). As a first step in this area preliminary scoping studies have been performed to investigate the usefulness of using active neutron interrogation, with a low-power electronic neutron generator, to assay Department of Transportation 6M shipping drums containing uranium oxide fuel rodlets from INL’s zero power physics reactor. Using the paired-counting technique during the die-away time period of interrogation, a lower detection limit of approximately 4.2 grams of enriched uranium (40% 235U) was calculated for a 40 minute measurement using a field portable 2.5 MeV neutron source and an array of 16 moderated helium-3 neutron tubes. Future work in this area, including the use of a more powerful neutron source and a better tailored detector array, would likely improve this limit to a much lower level. Further development work at INL will explore the applicability of active interrogation in association with the nuclear safeguards and process monitoring needs of the advanced GNEP facilities under consideration. This work, which will include both analyses and field demonstrations, will be performed in collaboration with colleagues at INL and elsewhere that have expertise in nuclear fuel reprocessing as well as active interrogation and its use for nuclear material analyses.

  3. Coordinated safeguards for materials management in a mixed-oxide fuel facility

    Energy Technology Data Exchange (ETDEWEB)

    Shipley, J.P.; Cobb, D.D.; Dietz, R.J.; Evans, M.L.; Schelonka, E.P.; Smith, D.B.; Walton, R.B.

    1977-02-01

    A coordinated safeguards system is described for safeguarding strategic quantities of special nuclear materials in mixed-oxide recycle fuel fabrication facilities. The safeguards system is compatible with industrial process requirements and combines maximum effectiveness consistent with modest cost and minimal process interference. It is based on unit process accounting using a combination of conventional and state-of-the-art NDA measurement techniques. The effectiveness of the system against single and multiple thefts is evaluated using computer modeling and simulation techniques.

  4. Comparative benefits and harms of second generation antidepressants and cognitive behavioral therapies in initial treatment of major depressive disorder: systematic review and meta-analysis.

    Science.gov (United States)

    Amick, Halle R; Gartlehner, Gerald; Gaynes, Bradley N; Forneris, Catherine; Asher, Gary N; Morgan, Laura C; Coker-Schwimmer, Emmanuel; Boland, Erin; Lux, Linda J; Gaylord, Susan; Bann, Carla; Pierl, Christiane Barbara; Lohr, Kathleen N

    2015-12-08

    What are the benefits and harms of second generation antidepressants and cognitive behavioral therapies (CBTs) in the initial treatment of a current episode of major depressive disorder in adults? This was a systematic review including qualitative assessment and meta-analyses using random and fixed effects models. Medline, Embase, the Cochrane Library, the Allied and Complementary Medicine Database, PsycINFO, and the Cumulative Index to Nursing and Allied Health Literature were searched from January 1990 through January 2015. The 11 randomized controlled trials included compared a second generation antidepressant CBT. Ten trials compared antidepressant monotherapy with CBT alone; three compared antidepressant monotherapy with antidepressant plus CBT. Meta-analyses found no statistically significant difference in effectiveness between second generation antidepressants and CBT for response (risk ratio 0.91, 0.77 to 1.07), remission (0.98, 0.73 to 1.32), or change in 17 item Hamilton Rating Scale for Depression score (weighted mean difference, -0.38, -2.87 to 2.10). Similarly, no significant differences were found in rates of overall study discontinuation (risk ratio 0.90, 0.49 to 1.65) or discontinuation attributable to lack of efficacy (0.40, 0.05 to 2.91). Although more patients treated with a second generation antidepressant than receiving CBT withdrew from studies because of adverse events, the difference was not statistically significant (risk ratio 3.29, 0.42 to 25.72). No conclusions could be drawn about other outcomes because of lack of evidence. Results should be interpreted cautiously given the low strength of evidence for most outcomes. The scope of this review was limited to trials that enrolled adult patients with major depressive disorder and compared a second generation antidepressant with CBT, and many of the included trials had methodological shortcomings that may limit confidence in some of the findings. Second generation antidepressants and CBT

  5. Negotiating supranational rules. The genesis of the International Atomic Energy Agency safeguards system

    Energy Technology Data Exchange (ETDEWEB)

    Forland, A.

    1997-12-31

    The object of this study is the evolution from 1954-56 up until the mid-1970s of the nuclear safeguards system administered by the International Atomic Energy Agency (IAEA) in Vienna. The main aim of the study is not to describe the IAEA safeguards system as such. The focus will be on analysing the arguments advanced in the various negotiations, and the main objective will be to single out the factors determining the result. In the course of the time span under study two international treaties were negotiated which were decisive for the development of international nuclear safeguards. These were the IAEA Stature (1956) and the Non-Proliferation Treaty (1968). The Statue as well as the NPT contain articles on international nuclear safeguards. These articles limit themselves to spelling out the safeguards principles. It was thus left to the IAEA Board of Governors to develop the safeguards procedures in detail. Two IAEA safeguards documents were negotiated between 1959 and 1965 in order to implement the safeguards article of the Statue. The safeguards requirements of the NPT were spelled out in a new model agreement in 1972. 58 refs.

  6. Advanced Process Monitoring Techniques for Safeguarding Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, Brian David [Los Alamos National Laboratory; Erpenbeck, Heather H [Los Alamos National Laboratory; Miller, Karen A [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Ianakiev, Kiril [Los Alamos National Laboratory; Marlow, Johnna B [Los Alamos National Laboratory

    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.

  8. Landmark Law Provides Equal Safeguards to Public,Private Property

    Institute of Scientific and Technical Information of China (English)

    LI XIN

    2007-01-01

    @@ After more than a quarter-century of market-oriented economic policies and unprecedented economic growths,China on March 15, 2007enacted its first law that provides equal legal safeguards to both public and private properties. The 247-article People's Republic of China Property Law, which is due to come into effect as of October 1, 2007, stipulates that "the property of the State, the collecfive, the individual and other obligees shall be protected by law, and no units or individuals may infringe upon it".

  9. Materials management in an internationally safeguarded fuels reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    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)

  10. Safeguarding cultural properties security for museums, libraries, parks, and zoos

    CERN Document Server

    Layne, Stevan P

    2014-01-01

    Safeguarding Cultural Properties is a step-by-step guide for creating and maintaining a comprehensive security program in any cultural facility or public institution. Author Stevan P. Layne, the leading expert in the field of cultural property protection, draws from his many years of experience providing protection training and planning to more than 350 cultural and public institutions around the world. Designed especially for those with limited security budgets, the book provides a proven and effective program for hiring the right security personnel, selecting the appropriate electronic s

  11. On acceleration of Krylov-subspace-based Newton and Arnoldi iterations for incompressible CFD: replacing time steppers and generation of initial guess

    CERN Document Server

    Gelfgat, Alexander

    2016-01-01

    We propose two techniques aimed at improving the convergence rate of steady state and eigenvalue solvers preconditioned by the inverse Stokes operator and realized via time-stepping. First, we suggest a generalization of the Stokes operator so that the resulting preconditioner operator depends on several parameters and whose action preserves zero divergence and boundary conditions. The parameters can be tuned for each problem to speed up the convergence of a Krylov-subspace-based linear algebra solver. This operator can be inverted by the Uzawa-like algorithm, and does not need a time-stepping. Second, we propose to generate an initial guess of steady flow, leading eigenvalue and eigenvector using orthogonal projection on divergence-free basis satisfying all boundary conditions. The approach, including the two proposed techniques, is illustrated on the solution of the linear stability problem for laterally heated square and cubic cavities.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  13. High-resolution modeling of overland flow and sediment transport following wildfire: Insights into initiation mechanisms and sediment sources for runoff-generated debris flows

    Science.gov (United States)

    McGuire, L.; Kean, J. W.; Staley, D. M.; Rengers, F. K.

    2015-12-01

    Sediment transport in steep landscapes may be facilitated by both water-dominated flows and debris-flow processes. Given the differences in erosion potential and mobility possessed by runoff and debris flows, knowledge of the conditions that determine the runoff-to-debris-flow transition has important implications for hazard assessment as well as our understanding of the long-term evolution of steep bedrock channels. Debris flows in alpine areas and burned steeplands are frequently triggered by runoff following high-intensity rainfall, but the mechanics by which runoff generates a debris flow are not well understood. To examine the connections between runoff and debris flow initiation, we developed a numerical model that couples overland flow with sediment transport and debris-flow processes. We applied the model to study erosion and debris-flow initiation that occurred during a rainfall event that produced numerous debris flows within a burned drainage basin in the San Gabriel Mountains, CA, USA. Input data for the numerical model was constrained by rain gauges, stage measurements at the basin outlet, soil-moisture sensors, and high-resolution topographic data obtained using a terrestrial laser scanner (TLS). Numerical model predictions, which compare well with TLS-derived measurements of topographic change, indicate that hillslope erosion at our study site was primarily the result of raindrop-induced sediment transport. Further, results indicate that the majority of sediment eroded from the hillslopes was deposited within the channel system during the storm with only minor amounts being transported out of the basin in suspension. Based on model results, we hypothesize that numerous debris flows were generated from the mass failure of sediment dams that built up within the channel system throughout the storm. This study adds to our understanding of sediment transport in steep landscapes and provides insight into the topographic and hydrologic factors that

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  15. Specific features of the radial distributions of plasma parameters in the initial segment of a supersonic jet generated by a pulsed capillary discharge

    Science.gov (United States)

    Pashchina, A. S.; Efimov, A. V.; Chinnov, V. F.; Ageev, A. G.

    2017-07-01

    Results are presented from spectroscopic studies of the initial segment of a supersonic plasma jet generated by a pulsed capillary discharge with an ablative carbon-containing polymer wall. Specific features of the spatial distributions of the electron density and intensities of spectral components caused, in particular, by the high electron temperature in the central zone, much exceeding the normal temperature, as well as by the high nonisobaricity of the initial segment of the supersonic jet, are revealed. Measurements of the radiative properties of the hot jet core (the intensity and profile of the Hα and Hβ Balmer lines and the relative intensities of C II lines) with high temporal (1-50 μs) and spatial (30-50 μm) resolutions made it possible to determine general features of the pressure and temperature distributions near the central shock. The presence of molecular components exhibiting their emission properties at the periphery of the plasma jet allowed the authors to estimate the parameters of the plasma in the jet region where "detached" shock waves form.

  16. Generation of a predicted protein database from EST data and application to iTRAQ analyses in grape (Vitis vinifera cv. Cabernet Sauvignon berries at ripening initiation

    Directory of Open Access Journals (Sweden)

    Smith Derek

    2009-01-01

    Full Text Available Abstract Background iTRAQ is a proteomics technique that uses isobaric tags for relative and absolute quantitation of tryptic peptides. In proteomics experiments, the detection and high confidence annotation of proteins and the significance of corresponding expression differences can depend on the quality and the species specificity of the tryptic peptide map database used for analysis of the data. For species for which finished genome sequence data are not available, identification of proteins relies on similarity to proteins from other species using comprehensive peptide map databases such as the MSDB. Results We were interested in characterizing ripening initiation ('veraison' in grape berries at the protein level in order to better define the molecular control of this important process for grape growers and wine makers. We developed a bioinformatic pipeline for processing EST data in order to produce a predicted tryptic peptide database specifically targeted to the wine grape cultivar, Vitis vinifera cv. Cabernet Sauvignon, and lacking truncated N- and C-terminal fragments. By searching iTRAQ MS/MS data generated from berry exocarp and mesocarp samples at ripening initiation, we determined that implementation of the custom database afforded a large improvement in high confidence peptide annotation in comparison to the MSDB. We used iTRAQ MS/MS in conjunction with custom peptide db searches to quantitatively characterize several important pathway components for berry ripening previously described at the transcriptional level and confirmed expression patterns for these at the protein level. Conclusion We determined that a predicted peptide database for MS/MS applications can be derived from EST data using advanced clustering and trimming approaches and successfully implemented for quantitative proteome profiling. Quantitative shotgun proteome profiling holds great promise for characterizing biological processes such as fruit ripening

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

    Energy Technology Data Exchange (ETDEWEB)

    Trellue, Holly Renee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fugate, Michael Lynn [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tobin, Stephen Joesph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  19. Safeguards and Security Technology Development Directory. FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    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.

  20. A Suggestion for Safeguards System under Nuclear Supply Assurance Environment

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Seong Youn [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2009-05-15

    Various ideas about nuclear fuel supply assurance have been proposed with the expectation of a new era of 'Nuclear Renaissance.' The possibility is ever than high now as the environmental impact due to the fossil fuel burning is worsening. But there are several obstacles to realize the resurrection of nuclear power as promising energy source in the future. The disposal of high radioactive wastes like nuclear spent fuel could be the first one that everyone can imagine, because those wastes are regarded as one of the direct threat to human health. But the most dangerous threat can be materialized through the diversion of nuclear material, if some malicious actors like some rogue states or terrorist groups take chance of the nuclear industry booming. Most supply assurance ideas based on multilateral approach provide the way to provide nuclear fuel while limiting dissipation of sensitive technologies. But regarding the safeguards implementation under the supply assurance environment, it seems that any appropriate approach has not been prepared. It is prerequisite to establish safeguards implementation system for multilateral facilities prior to their actual operation.

  1. Advanced Safeguards Technology Demonstration at Pacific Northwest National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    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.

  2. 42 CFR 431.305 - Types of information to be safeguarded.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false Types of information to be safeguarded. 431.305... Information on Applicants and Recipients § 431.305 Types of information to be safeguarded. (a) The agency must have criteria that govern the types of information about applicants and recipients that are...

  3. 41 CFR 51-9.101-5 - Safeguarding systems of records.

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 1 2010-07-01 2010-07-01 true Safeguarding systems of records. 51-9.101-5 Section 51-9.101-5 Public Contracts and Property Management Other Provisions Relating... ACT RULES 9.1-General Policy § 51-9.101-5 Safeguarding systems of records. The Executive...

  4. 10 CFR 73.23 - Protection of Safeguards Information-Modified Handling: Specific requirements.

    Science.gov (United States)

    2010-01-01

    ... PROTECTION OF PLANTS AND MATERIALS General Provisions § 73.23 Protection of Safeguards Information—Modified... specific design features of plant security communications systems; (vi) Lock combinations, mechanical key... access Safeguards Information by gaining access to retained memory or network connectivity). (f)...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  7. Distortions of Sino-US and Sino-EU Safeguard Agreements: Effects on World Textile Markets

    Institute of Scientific and Technical Information of China (English)

    Suwen Pan; Mark Welch; Samarendu Mohanty; Xiurong He

    2007-01-01

    The effects of Sino-US and Sino-EU safeguard agreements on US, Chinese and world cotton and textile sectors are investigated using a partial equilibrium model. The effects are compared to a free trade scenario under the provisions of the Agreement on Textiles and Clothing. The two safeguard agreements capping Chinese textile exports would decrease China's textile and apparel exports, production, and domestic consumption by an average 1.57, 0.63 and 0.32 percent, respectively. The safeguard agreements cause an increase in the US cotton textile price index and a slight decrease in US net textile imports and textile consumption. The agreements cause a decrease in the world cotton price and the quantity of cotton traded, but these trends reverse at safeguard expiration. The results generally support the view that the safeguard agreements forestall the effects of free trade in textiles and apparel rather than creating long lasting shifts in the textile trade.

  8. Negotiating supranational rules - The genesis of the International Atomic Energy Agency Safeguards System

    Energy Technology Data Exchange (ETDEWEB)

    Forland, Astrid

    1998-12-31

    The object of this thesis is the evolution from 1954-56 up until the mid 1970s of the nuclear safeguards system administered by the International Atomic Energy Agency (IAEA) in Vienna. The evolution is traced not through the practical implementation of the safeguards system, but through the various multilateral negotiations through which it was created. The focus is on analysing the arguments advanced in the various negotiations, and the main objective is to single out the factors determining the result. The discussion is organised into the following chapters: (1) The statute of the IAEA, (2) The IAEA 1961 safeguard document (INFCIRC/26), (3) The IAEA 1965 safeguards document (INFCIRC/66), (4) The non-proliferation treaty, (5) NPT safeguards. 92 refs.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Beddingfield, David H [Los Alamos National Laboratory; Nordquist, Heather A [Los Alamos National Laboratory; Umebayaashi, Eiji [JAEA

    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.

  11. 10 CFR 76.119 - Security facility approval and safeguarding of National Security Information and Restricted Data.

    Science.gov (United States)

    2010-01-01

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

  12. Multi-Level Policy Dialogues, Processes, and Actions: Challenges and Opportunities for National REDD+ Safeguards Measurement, Reporting, and Verification (MRV

    Directory of Open Access Journals (Sweden)

    Pamela Jagger

    2014-09-01

    Full Text Available REDD+ social safeguards have gained increasing attention in numerous forums. This paper reviews the evolution of multi-level policy dialogues, processes, and actions related to REDD+ social safeguards (e.g., Cancun Safeguards 1–5 among policy makers, civil society organizations, and within the media in Brazil, Indonesia and Tanzania, three countries with well advanced REDD+ programs. We find that progress on core aspects of social safeguards is uneven across the three countries. Brazil is by far the most advanced having drafted a REDD+ social safeguards policy. Both Brazil and Indonesia have benefited from progress made by strong sub-national entities in the operationalization of REDD+ safeguards including free prior and informed consent (FPIC, participation, and benefit sharing. Tanzania has weakly articulated how social safeguards will be operationalized and has a more top-down approach. We conclude that in all three countries, measuring, reporting and verifying progress on social safeguards is likely to be a complex issue. Stakeholders with vested interests in REDD+ social safeguards operate in polycentric rather than nested systems, suggesting that aggregation of information from local to national-scale will be a challenge. However, polycentric systems are also likely to support more transparent and comprehensive safeguards systems. Clear direction from the international community and financing for REDD+ safeguard MRV is essential if REDD+ social safeguards are to be meaningfully integrated into forest-based climate mitigation strategies.

  13. Computation of a leakage in a stream generator heating tube with realistic initial and boundary conditions; Berechnung eines Dampferzeugerheizrohrlecks mit realistischen Anfangs- und Randbedingungen

    Energy Technology Data Exchange (ETDEWEB)

    Sarkadi, Peter; Schaffrath, Andreas [TUEV NORD SysTec GmbH und Co. KG, Hamburg (Germany)

    2009-02-15

    Within the framework of the safety review of a pressurized water reactor, TUeV NORD SysTec GmbH and Co.KG analyzed plant behavior for the case of a leakage in a steam generator heating tube by means of the ATHLET thermohydraulic code system using realistic initial and boundary conditions. The analysis was performed to show that operation of the safety injection pumps avoids 2 out of 3 emergency cooling criteria being triggered. After coolant transfer from the primary to the secondary side, activity retention is ensured only if the coolant is contained by the components of the secondary system. This requires the pressure in the failed steam generator to remain below the level of 88.3 bar at which the safety valves respond. Startup of the safety injection pumps would jeopardize activity retention because of the zero head of these pumps. Analysis indicated the filling level of the pressurizer to be above 3.6 m during the accident. The minimum margin from the ''pressurizer level <2.28 m'' reactor protection limit is around 1.3 m. Consequently, only the first of the 3 emergency cooling criteria (in this case, 'coolant pressure <132 bar') will respond. This avoids unwanted boosting of the coolant pressure due to connection of the safety injection pumps. By the end of the period of observation, approx. 36 Mg of coolant are transferred to the secondary side. Activity retention is ensured by the components of the secondary system. (orig.)

  14. Initiation of detonation by impact on granular explosives; Contribution a l'etude de la generation de la detonation provoquee par impact sur un explosif

    Energy Technology Data Exchange (ETDEWEB)

    Bernier, H. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-05-15

    A good number of experiments have shown up the particular behaviour of granular explosives when they are detonated by barrier transmitted shocks. Similar results can be obtained when the shock is induced by impact. In this case the pressure signal shape applied at the explosive is better known and both its intensity and duration can be varied. By using a mathematical model in which the law of chemical kinetics is a linear function of pressure, and different temperatures are used for solids and gases, it is possible to describe most of the behaviour of detonation initiation in solid granular explosives. (author) [French] De nombreuses etudes experimentales ont montre le comportement particulier des explosifs granulaires lors de la detonation provoquee par choc transmis a travers une barriere. Les memes resultats peuvent etre obtenus lorsque la detonation est engendree par impact. Dans ce cas, la forme du signal de pression induit dans l'explosif est mieux connue, et il est possible d'en faire varier l'intensite et la duree d'application. Un modele mathematique utilisant une loi de cinetique chimique fonction lineaire de la pression et ou les temperatures des etats solide et gazeux pendant la reaction sont differenciees, permet de retrouver la plupart des caracteres specifiques de la generation dans un explosif solide granulaire. (auteur)

  15. Prescribing Practice in Inpatients Versus Outpatients With Schizophrenia Initiating Treatment With Second-Generation Antipsychotics: A Naturalistic Follow-Up Study.

    Science.gov (United States)

    Edlinger, Monika; Rettenbacher, Maria A; Kemmler, Georg; Biedermann, Falko; Widschwendter, Christian G; Fleischhacker, W Wolfgang; Hofer, Alex

    2016-12-01

    The primary objective of this study was to investigate whether the choice and dosage of antipsychotic medication differ between patients with schizophrenia starting treatment in an inpatient or outpatient unit. In addition, we investigated whether the reason for the introduction of new antipsychotic medication had an impact on the treatment setting and whether the use of benzodiazepines differed between inpatients and outpatients. From October 1997 to September 2010, patients with a schizophrenia spectrum disorder according to the International Classification of Diseases, Tenth Revision aged between 18 and 65 years were allocated to a naturalistic drug-monitoring program when starting treatment with a second-generation antipsychotic drug. Psychopathological symptoms were rated at baseline and after 1, 2, 4, and 8 weeks of treatment using the Positive and Negative Syndrome Scale. Inpatients and outpatients were compared with regard to the use of antipsychotics and benzodiazepines. To compare different drugs, chlorpromazine and diazepam equivalents were calculated. Lack of efficacy and side effects were the main reasons for initiating new antipsychotic medication. Combined evaluation of all antipsychotic compounds by meta-analysis resulted in a significant effect of the treatment setting, with inpatients receiving higher doses than outpatients. In addition, inpatients were prescribed benzodiazepines more often and in higher doses than outpatients. Both antipsychotics and benzodiazepines were prescribed at higher doses in an inpatient setting. Moreover, benzodiazepines were prescribed more frequently to inpatients. Accordingly, the treatment setting needs to be taken into consideration in treatment recommendations for schizophrenia spectrum disorders.

  16. Development of Metallic Magnetic Calorimeters for Nuclear Safeguards Applications

    Energy Technology Data Exchange (ETDEWEB)

    Bates, Cameron Russell [Univ. of California, Berkeley, CA (United States)

    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

  17. Analysis of the vibration response of a safeguard piping system

    Energy Technology Data Exchange (ETDEWEB)

    Trollat, C.; Tephany, F.; Payan, F. (Electricite de France, Villeurbanne (France))

    1993-01-01

    Following the discovery of a longitudinal through-wall crack at the base of a pressure instrumentation tap on the system, Electricite de France started a huge campaign to check the safeguard pipes in its 1300-MW nuclear power plants. The analysis of several hundreds of taps of this type on-site revealed several tens of cases of cracking. These safeguard systems practically only operate during periodic test phases that generally correspond to partial now regimes for the pump and to hydraulic configurations that do not correspond to the main system function. These hydraulic configurations were clearly identified as [open quotes]worst cases[close quotes] for the system through vibration measurements during the startup tests, allowing the system to be tested under rated conditions. Experience feedback raises several difficulties in interpreting the damage; in particular, considerable differences were found in the vibration levels of the same tap on the same piping system from one plant unit to another. Also, the vibration measurements taken on the main pipe are not always correlated with the tap vibration level. To explain these phenomena, it was decided to model the discharge line of the 1300-MW low head safety injection system. To obtain the system response to pump excitation, a fluid-structure-coupled finite element model was built for which the boundary conditions are well controlled. Modal analysis revealed acoustic-mechanical coupling of the system in the environment of the discontinuous zone that cracked. Further analysis of this mechanical discontinuity showed that its first natural frequency is close to that of the coupled mode. Knowing the system transfer function, the force and displacement response are obtained.

  18. [Safeguarding herds from the animal hygiene point of view].

    Science.gov (United States)

    Hartung, J

    2005-08-01

    One of the most important concepts for the protection of herd health is the implementation of structural and organisational measures to prevent infective agents and other adverse compounds from entering the farm. Safeguarding health, well-being and production efficiency is part of the overall management concept of hygiene in animal production systems. This paper presents an overview of the most important rules and recommendations to protect livestock production facilities from the intrusion of infectious pathogens, beginning with the right choice of the site for the farm and the animal housing ("safe distances" to neighbouring farm animal houses), solid fencing and control and disinfecting places at the entrance gate. The traffic of vehicles and people transporting animals, feedstuff, equipment and slurry or manure to and from the facility should be reduced to a minimum. Fallen animals should be stored in separate and safe containers until removed by specialised companies. Regular control of rodents, insects and wild birds is crucial to avoid the transfer of infectious agents from farm to farm and between herds within a farm. Equally important factors are the health status of personnel to avoid transmission of zoonotic diseases, the application of the all-in-all-out system and a strict cleaning and disinfecting regime. The internal and external organisational measures for preventing the spread of infections in animal production will gain increasing importance in the future because the farm animal producer bears the responsibility for the production of safe and healthy food at the primary segment of the food chain. Increasing restrictions on the use of veterinary drugs for food delivering animals will increase the importance of prophylaxis, prevention and protection of production units as the keys for safeguarding health, well-being and efficiency of farm animals. Only the application of strict hygiene principles in animal production will make it possible to meet

  19. Web-Based Training Applications in Safeguards and Security

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, R.L.

    1999-05-21

    The U.S. Department of Energy (DOE) requires all employees who hold a security clearance and have access to classified information and/or special nuclear material to be trained in the area of Safeguards and Security. Since the advent of the World Wide Web, personnel who are responsible for training have capitalized on this communication medium to develop and deliver Web-based training. Unlike traditional computer based training where the student was required to find a workstation where the training program resided, one of Web-based training strongest advantage is that the training can be delivered right to the workers desk top computer. This paper will address reasons for the driving forces behind the utilization of Web-based training at the Laboratory with a brief explanation of the different types of training conducted. Also discussed briefly is the different types of distance learning used in conjunction with Web-based training. The implementation strategy will be addressed and how the Laboratory utilized a Web-Based Standards Committee to develop standards for Web-based training applications. Web-based problems resulting from little or no communication between training personnel across the Laboratory will be touched on and how this was solved. Also discussed is the development of a ''Virtual Training Center'' where personnel can shop on-line for their training needs. Web-based training programs within the Safeguards and Security arena will be briefly discussed. Specifically, Web-based training in the area of Materials Control and Accountability will be explored. A Web-based example of what a student would experience during a training session is also discussed. A short closing statement of what the future of Web-based Training holds in the future is offered.

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

    Energy Technology Data Exchange (ETDEWEB)

    Pabian, Frank Vincent [Los Alamos National Laboratory

    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.

  1. System aspects on safeguards for the back-end of the Swedish nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Fritzell, Anni (Dept. of Physics and Astronomy, Uppsala Univ., Uppsala (Sweden))

    2008-03-15

    This thesis has investigated system aspects of safeguarding the back-end of the Swedish nuclear fuel cycle. These aspects include the important notion of continuity of knowledge, the philosophy of verifying measurements and the need to consider the safeguards system as a whole when expanding it to include the encapsulation facility and the geological repository. The research has been analytical in method both in the identification of concrete challenges for the safeguards community in Paper 1, and in the diversion path analysis performed in Paper 2. This method of work is beneficial for example when abstract notions are treated. However, as a suggestion for further work along these lines, a formal systems analysis would be advantageous, and may even reveal properties of the safeguards system that the human mind so far has been to narrow to consider. A systems analysis could be used to model a proposed safeguards approach with the purpose of finding vulnerabilities in its detection probabilities. From the results, capabilities needed to overcome these vulnerabilities could be deduced, thereby formulating formal boundary conditions. These could include: The necessary partial defect level for the NDA measurement; The level of redundancy required in the C/S system to minimize the risk of inconclusive results due to equipment failure; and, Requirements on the capabilities of seismic methods, etc. The field of vulnerability assessment as a tool for systems analysis should be of interest for the safeguards community, as a formal approach could give a new dimension to the credibility of safeguards systems

  2. The US Support Program to IAEA Safeguards Priority of Training and Human Resources

    Energy Technology Data Exchange (ETDEWEB)

    Queirolo,A.

    2008-06-13

    The U.S. Support Program to IAEA Safeguards (USSP) priority of training and human resources is aimed at providing the Department of Safeguards with an appropriate mixture of regular staff and extrabudgetary experts who are qualified to meet the IAEA's technical needs and to provide personnel with appropriate instruction to improve the technical basis and specific skills needed to perform their job functions. The equipment and methods used in inspection activities are unique, complex, and evolving. New and experienced safeguards inspectors need timely and effective training to perform required tasks and to learn new skills prescribed by new safeguards policies or agreements. The role of the inspector has changed from that of strictly an accountant to include that of a detective. New safeguards procedures are being instituted, and therefore, experienced inspectors must be educated on these new procedures. The USSP also recognizes the need for training safeguards support staff, particularly those who maintain and service safeguards equipment (SGTS), and those who perform information collection and analysis (SGIM). The USSP is committed to supporting the IAEA with training to ensure the effectiveness of all staff members and will continue to offer its assistance in the development and delivery of basic, refresher, and advanced training courses. This paper will discuss the USSP ongoing support in the area of training and IAEA staffing.

  3. Open source information acquisition, analysis and integration in the IAEA Department of Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Barletta, M.; Zarimpas, N.; Zarucki, R., E-mail: M.Barletta@iaea.or [IAEA, Wagramerstrasse 5, P.O. Box 100, 1400 Vienna (Austria)

    2010-10-15

    Acquisition and analysis of open source information plays an increasingly important role in the IAEA strengthened safeguards system. The Agency's focal point for open source information collection and analysis is the Division of Safeguards Information Management (SGIM) within the IAEA Department of Safeguards. In parallel with the approval of the Model Additional Protocol in 1997, a new centre of information acquisition and analysis expertise was created within SGIM. By acquiring software, developing databases, retraining existing staff and hiring new staff with diverse analytical skills, SGIM is pro actively contributing to the future implementation of information-driven safeguards in collaboration with other Divisions within the Department of Safeguards. Open source information support is now fully integrated with core safeguards processes and activities, and has become an effective tool in the work of the Department of Safeguards. This provides and overview of progress realized through the acquisition and use of open source information in several thematic areas: evaluation of additional protocol declarations; support to the State Evaluation process; in-depth investigation of safeguards issues, including assisting inspections and complementary access; research on illicit nuclear procurement networks and trafficking; and monitoring nuclear developments. Demands for open source information have steadily grown and are likely to continue to grow in the future. Coupled with the enormous growth and accessibility in the volume and sources of information, new challenges are presented, both technical and analytical. This paper discusses actions taken and future plans for multi-source and multi-disciplinary analytic integration to strengthen confidence in safeguards conclusions - especially regarding the absence of undeclared nuclear materials and activities. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  5. Study On Safeguard Measures for Implementing Overall Planning of Land Use

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Based on minutely analysing the main problems existing in safeguard measures for implementing a new round of overall planning of land use,this paper constructs implementation security system of overall planning of land use,and puts forward the principles and basis of formulating safeguard measures for implementing overall planning of land use.Finally,this paper establishes the content system of safeguard measures:effectively strengthen social supervision;strengthen administrative management of land use planning;strengthen economic management of land use planning;reinforce the legal status of planning;establish incentive and constraint mechanism for reinforcing implementation;improve support system of planning.

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

    Energy Technology Data Exchange (ETDEWEB)

    Trond Bjornard; Philip C. Durst

    2012-05-01

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

  7. Safeguarding biodiversity and ecosystem services in the Little Karoo, South Africa

    CSIR Research Space (South Africa)

    Egoh, Benis N

    2010-02-01

    Full Text Available Global declines in biodiversity and the widespread degradation of ecosystem services have led to urgent calls to safeguard both. Responses to this urgency include calls to integrate the needs of ecosystem services and biodiversity into the design...

  8. 76 FR 34276 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Digital...

    Science.gov (United States)

    2011-06-13

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Digital Instrumentation and Control Systems; Notice of Meeting The ACRS Subcommittee on Digital Instrumentation...

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Gastelum, Zoe N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gitau, Ernest T. N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Doehle, Joel R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Toomey, Christopher M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-09-01

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

  11. 32 CFR Appendix A to Part 310 - Safeguarding Personally Identifiable Information (PII)

    Science.gov (United States)

    2010-07-01

    .... Risk Management and Safeguarding Standards 1. Establish administrative, technical, and physical... sensitivity of the data being processed, stored and accessed. b. The installation environment. c. The risk of... alteration. 2. Develop access procedures for unclassified computer rooms, tape libraries,...

  12. 10 CFR 73.22 - Protection of Safeguards Information: Specific requirements.

    Science.gov (United States)

    2010-01-01

    ..., or sabotage of source, byproduct, or special nuclear material. (2) Physical protection in transit... Safeguards Information is attended by such an individual even though the information is in fact...

  13. 78 FR 2295 - Consideration of Approval of Application Containing Sensitive Unclassified Non-Safeguards...

    Science.gov (United States)

    2013-01-10

    ... From the Federal Register Online via the Government Publishing Office ] NUCLEAR REGULATORY COMMISSION Consideration of Approval of Application Containing Sensitive Unclassified Non-Safeguards Information Regarding Proposed Energy Future Holdings Corporation Internal Restructuring AGENCY:...

  14. Analysis on approach of safeguards implementation at research reactor handling item count and bulk material

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Jo; Lee, Sung Ho; Lee, Byung Doo; Jung, Juang [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    KiJang research reactor (KJRR) will be constructed to produce the radioisotope such as Mo-99 etc., provide the neutron transmutation doping (NTD) service of silicon, and develop the core technologies of research reactor. In this paper, the features of the process and nuclear material flow are reviewed and the material balance area (MBA) and key measurement point (KMP) are established based on the nuclear material flow. Also, this paper reviews the approach on safeguards and nuclear material accountancy at the facility level for Safeguards-by-Design at research reactor handling item count and bulk material. In this paper, MBA and KMPs are established through the analysis on facility features and major process at KJRR handling item count and bulk material. Also, this paper reviews the IAEA safeguards implementation and nuclear material accountancy at KJRR. It is necessary to discuss the safeguards approach on the fresh FM target assemblies and remaining uranium in the intermediate level liquid wastes.

  15. Sustainable Forest Bioenergy Initiative

    Energy Technology Data Exchange (ETDEWEB)

    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

  16. Initial results of a new generation dual source CT system using only an in-plane comb filter for ultra-high resolution temporal bone imaging

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Mathias; Haubenreisser, Holger; Schoenberg, Stefan O.; Henzler, Thomas [Heidelberg University, Institute of Clinical Radiology and Nuclear Medicine, University Medical Center Mannheim, Medical Faculty Mannheim, Mannheim (Germany); Raupach, Rainer; Schmidt, Bernhard; Leidecker, Christianne; Allmendinger, Thomas; Flohr, Thomas [Siemens Healthcare, Imaging and Therapy Division, Forchheim (Germany); Lietzmann, Florian; Schad, Lothar R. [Heidelberg University, Computer Assisted Clinical Medicine, University Medical Center Mannheim, Medical Faculty Mannheim, Mannheim (Germany)

    2015-01-15

    To prospectively evaluate radiation dose and image quality of a third generation dual-source CT (DSCT) without z-axis filter behind the patient for temporal bone CT. Forty-five patients were either examined on a first, second, or third generation DSCT in an ultra-high-resolution (UHR) temporal bone-imaging mode. On the third generation DSCT system, the tighter focal spot of 0.2 mm{sup 2} removesthe necessity for an additional z-axis-filter, leading to an improved z-axis radiation dose efficiency. Images of 0.4 mm were reconstructed using standard filtered-back-projection or iterative reconstruction (IR) technique for previous generations of DSCT and a novel IR algorithm for the third generation DSCT. Radiation dose and image quality were compared between the three DSCT systems. The statistically significantly highest subjective and objective image quality was evaluated for the third generation DSCT when compared to the first or second generation DSCT systems (all p < 0.05). Total effective dose was 63 %/39 % lower for the third generation examination as compared to the first and second generation DSCT. Temporal bone imaging without z-axis-UHR-filter and a novel third generation IR algorithm allows for significantly higher image quality while lowering effective dose when compared to the first two generations of DSCTs. (orig.)

  17. Social Safeguards for REDD+ in Mexico’s Watershed Management Program

    OpenAIRE

    Garduño Diaz, Philippe Youssef

    2012-01-01

    Case studies on environmental governance are essential to improve comprehension on howto implement international agreements. This study focuses on seven social safeguards relevant toREDD+. The existence of these social safeguards is examined in Mexico’s watershed managementprogram in La Sierra Madre and La Costa of Chiapas. The watershed management program is anotherPayment for Ecosystem Services (PES) scheme similar to REDD+. Questionnaires and interviews wereused to conduct primary research...

  18. The Advantages and Disadvantages of Different Models of Organising Adult Safeguarding

    OpenAIRE

    Norrie, Caroline; Stevens, Martin; Graham, Katherine Elizabeth; Moriarty, Jo; Manthorpe, Jill

    2017-01-01

    Professionals express divergent views about whether adults at risk are best served by safeguarding work being incorporated into social workers’ casework or being undertaken by specialist workers within local area or centralised teams. This paper draws on findings from the final two phases of a three-phase study which aimed to identify a typology of different models of organising adult safeguarding and compare the advantages and disadvantages of these. We used mixed-methods to investigate four...

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

    Energy Technology Data Exchange (ETDEWEB)

    Kovacic, Donald N [ORNL

    2015-01-01

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

  20. Start-up and safeguarding of an industrial adiabatic tubular reactor

    OpenAIRE

    Verwijs, J.W.; Berg, van den, M.M.; Westerterp, K.R.

    1994-01-01

    The safeguarding methodology currently used in the chemical industry is based on controlling the instantaneous values of the process state variables within a certain operating window, the process being brought to shut-down when the operating constraints are exceeded. It is concluded from an analysis of runaways which occurred in industrial reactors that this safeguarding methodology does not necessarily prevent reactor systems suffering from a runaway because (a) excessive amounts of unreacte...

  1. Safeguarding critical e-documents implementing a program for securing confidential information assets

    CERN Document Server

    Smallwood, Robert F

    2012-01-01

    Practical, step-by-step guidance for corporations, universities and government agencies to protect and secure confidential documents and business records Managers and public officials are looking for technology and information governance solutions to "information leakage" in an understandable, concise format. Safeguarding Critical E-Documents provides a road map for corporations, governments, financial services firms, hospitals, law firms, universities and other organizations to safeguard their internal electronic documents and private communications.Provides practical, step-by-step guidance o

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

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, Brian David [Los Alamos National Laboratory; Erpenbeck, Heather H [Los Alamos National Laboratory; Miller, Karen A [Los Alamos National Laboratory; Ianakiev, Kiril D [Los Alamos National Laboratory; Reimold, Benjamin A [Los Alamos National Laboratory; Ward, Steven L [Los Alamos National Laboratory; Howell, John [GLASGOW UNIV.

    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.

  3. Integrated neutron/gamma-ray portal monitors for nuclear safeguards

    Science.gov (United States)

    Fehlau, Paul E.

    1994-08-01

    Radiation monitoring is one nuclear-safeguards measure used to protect against the theft of special nuclear materials (SNM) by pedestrians departing from SNM access areas. The integrated neutron/gamma-ray portal monitor is an ideal radiation monitor for the task when the SNM is plutonium. It achieves high sensitivity for detecting both bare and shielded plutonium by combining two types of radiation detector. One type is a neutron-chamber detector, comprising a large, hollow, neutron moderator that contains a single thermal-neutron proportional counter. The entrance wall of each chamber is thin to admit slow neutrons from plutonium contained in a moderating shield, while the other walls are thick to moderate fast neutrons from bare or lead-shielded plutonium so that they can be detected. The other type of detector is a plastic scintillator that is primarily for detecting gamma rays from small amounts of unshielded plutonium. The two types of detector are easily integrated by making scintillators part of the thick back wall of each neutron chamber or by inserting them into each chamber void. We compared the influence of the two methods of integration on detecting neutrons and gamma rays, and we examined the effectiveness of other design factors and the methods for signal detection as well.

  4. Protecting citizen-children safeguards our common future.

    Science.gov (United States)

    Zayas, Luis H

    2010-08-01

    For every two adult undocumented immigrants that are deported from the U.S., one citizen-child is affected. With roughly 1.3 million adults deported in the past decade, the number of citizen-children is staggering. Deportation forces parents to make crucial decisions about their U.S.-born children: to take them or leave them behind. Our deportation policies and practices fall hardest on citizen-children in mixed-status families. In this commentary, I review the conditions facing citizen-children, and consider the consequences to the children and to the U.S. To remedy the effects of deportation policies and practices, federal immigration enforcement must follow sound child welfare models. Solid health and educational research helps immigration courts in decision-making by documenting the effects of parental deportation on citizen-children. Promoting legislation such as the Child-Citizen Protection and The Dream Act insures the principled and humane treatment of citizen-children. International treaties and programs that protect citizen-children will also safeguard our nation's future.

  5. Initial results of a new generation dual source CT system using only an in-plane comb filter for ultra-high resolution temporal bone imaging.

    Science.gov (United States)

    Meyer, Mathias; Haubenreisser, Holger; Raupach, Rainer; Schmidt, Bernhard; Lietzmann, Florian; Leidecker, Christianne; Allmendinger, Thomas; Flohr, Thomas; Schad, Lothar R; Schoenberg, Stefan O; Henzler, Thomas

    2015-01-01

    To prospectively evaluate radiation dose and image quality of a third generation dual-source CT (DSCT) without z-axis filter behind the patient for temporal bone CT. Forty-five patients were either examined on a first, second, or third generation DSCT in an ultra-high-resolution (UHR) temporal bone-imaging mode. On the third generation DSCT system, the tighter focal spot of 0.2 mm(2) removes the necessity for an additional z-axis-filter, leading to an improved z-axis radiation dose efficiency. Images of 0.4 mm were reconstructed using standard filtered-back-projection or iterative reconstruction (IR) technique for previous generations of DSCT and a novel IR algorithm for the third generation DSCT. Radiation dose and image quality were compared between the three DSCT systems. The statistically significantly highest subjective and objective image quality was evaluated for the third generation DSCT when compared to the first or second generation DSCT systems (all p generation examination as compared to the first and second generation DSCT. Temporal bone imaging without z-axis-UHR-filter and a novel third generation IR algorithm allows for significantly higher image quality while lowering effective dose when compared to the first two generations of DSCTs. • Omitting the z-axis-filter allows a reduction in radiation dose of 50% • A smaller focal spot of 0.2 mm (2) significantly improves spatial resolution • Ultra-high-resolution temporal-bone-CT helps to gain diagnostic information of the middle/inner ear.

  6. Delayed Gamma-ray Spectroscopy for Safeguards Applications

    Energy Technology Data Exchange (ETDEWEB)

    Mozin, Vladimir [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-01-03

    The delayed gamma-ray assay technique utilizes an external neutron source (D-D, D-T, or electron accelerator-driven), and high-resolution gamma-ray spectrometers to perform characterization of SNM materials behind shielding and in complex configurations such as a nuclear fuel assembly. High-energy delayed gamma-rays (2.5 MeV and above) observed following the active interrogation, provide a signature for identification of specific fissionable isotopes in a mixed sample, and determine their relative content. Potential safeguards applications of this method are: 1) characterization of fresh and spent nuclear fuel assemblies in wet or dry storage; 2) analysis of uranium enrichment in shielded or non-characterized containers or in the presence of a strong radioactive background and plutonium contamination; 3) characterization of bulk and waste and product streams at SNM processing plants. Extended applications can include warhead confirmation and warhead dismantlement confirmation in the arms control area, as well as SNM diagnostics for the emergency response needs. In FY16 and prior years, the project has demonstrated the delayed gamma-ray measurement technique as a robust SNM assay concept. A series of empirical and modeling studies were conducted to characterize its response sensitivity, develop analysis methodologies, and analyze applications. Extensive experimental tests involving weapons-grade Pu, HEU and depleted uranium samples were completed at the Idaho Accelerator Center and LLNL Dome facilities for various interrogation time regimes and effects of the neutron source parameters. A dedicated delayed gamma-ray response modeling technique was developed and its elements were benchmarked in representative experimental studies, including highresolution gamma-ray measurements of spent fuel at the CLAB facility in Sweden. The objective of the R&D effort in FY17 is to experimentally demonstrate the feasibility of the delayed gamma-ray interrogation of shielded SNM

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

    Energy Technology Data Exchange (ETDEWEB)

    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. Monitoring REDD+: From Social Safeguards to Social Learning

    Science.gov (United States)

    Ravikumar, A.; Andersson, K.

    2010-12-01

    Krister Andersson 1 and Ashwin Ravikumar 1 The UNFCCC requires countries that participate in the REDD+ (Reducing Emissions from Deforestation and Forest Degradation in Developing Countries) program to monitor both forest carbon inventories as well as the governance of REDD+ activities and their social consequences. Exactly how this should be done, however, remains an open question. This paper addresses this question by drawing on existing research on social-ecological systems and new institutional economics. We make the case for a monitoring system that goes beyond a narrow focus of qualitative indicators of REDD+ governance that seek to provide social safeguards for international investors to create a more comprehensive monitoring system that is useful for social learning about how policies affect a variety of forest outcomes. We describe the defining characteristics of five existing approaches to monitoring REDD+ governance. Applying evaluative criteria of affordability, comprehensiveness, transparency, uncertainty specification, and explanatory potential, we analyze the extent to which each of the programs contribute to broader social learning processes in participating countries. Our analysis finds that it makes sense to move from the current narrow focus of monitoring for control to monitoring for social learning. Particularly valuable to participating REDD+ actors would be the creation of learning systems that can help policy makers to identify opportunities for policy improvements, with the ultimate goal of making REDD+ more effective, efficient, and equitable. Such learning is not possible, however, without timely and systematic collection of data on the relationships between forests and forest users. 1University of Colorado at Boulder, Environmental Studies Program, Boulder, CO 80309-0397

  9. Long-Term Information Management (LTIM) of Safeguards Data at Repositories: Phase II

    Energy Technology Data Exchange (ETDEWEB)

    Haddal, Risa N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-10-01

    One of the challenges of implementing safeguards for geological repositories will be the long-term preservation of safeguards-related data for 100 years or more. While most countries considering the construction and operation of such facilities agree that safeguards information should be preserved, there are gaps with respect to standardized requirements, guidelines, timescales, and approaches. This study analyzes those gaps and explores research to clarify stakeholder needs, identify current policies, approaches, best practices and international standards, and explores existing safeguards information management infrastructure. The study also attempts to clarify what a safeguards data classification system might look like, how long data should be retained, and how information should be exchanged between stakeholders at different phases of a repository’s life cycle. The analysis produced a variety of recommendations on what information to preserve, how to preserve it, where to store it, retention options and how to exchange information in the long term. Key findings include the use of the globally recognized international records management standard, ISO15489, for guidance on the development of information management systems, and the development of a Key Information File (KIF). The KIF could be used to identify only the most relevant, high-level safeguards information and the history of decision making about the repository. The study also suggests implementing on-site and off-site records storage in digital and physical form; developing a safeguards data classification system; long-term records retention with periodic reviews every 5 to 10 years during each phase of the repository life cycle; and establishing transition procedures well in advance so that data shepherds and records officers can transfer information with incoming facility managers effectively and efficiently. These and other recommendations are further analyzed in this study.

  10. Development of in-field monitoring techniques. Report on Task FIN A845 on the Finnish Support Programme to IAEA Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Toivonen, H.; Honkamaa, T.; Kansanaho, A.; Poellaenen, R. [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland). Aerosol Lab.; Aarnio, P.; Ala-Heikkilae, J.; Nikkinen, M. [Helsinki Univ. of Technology, Otaniemi (Finland). Nuclear Engineering Lab.

    1994-12-01

    Several in-field measuring techniques were identified for use in safeguards inspections. The radiation measurements play a major role in seeking environmetal signatures. A high-resolution gamma-ray spectrometer, either in-situ or in sample analysis, gives unequivocal evidence of nuclear activities on the site of interest. Although portable spectrometers are commercially available, hardware development and software tailoring seem to be necessary before efficient mobile measurements can be initiated. To understand trends and pattern of contamination, the results of the measurements have be displayed on digital maps. GPS-integration is an essential requirement for the equipment in environmental monitoring. (orig.) (14 refs., 5 figs., 17 tabs.).

  11. United States Program for Technical assistance to IAEA Standards. Concept Paper: Knowledge Acquisition, Skills training for enhanced IAEA safeguards inspections

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-11-01

    This concept paper explores the potential contribution of ``Knowledge Acquisition Skills`` in enhancing the effectiveness of international safeguards inspections by the International Atomic energy Agency (IAEA, or Agency) and identifies types of training that could be provided to develop or improve such skills. For purposes of this concept paper, Knowledge Acquisition Skills are defined broadly to include all appropriate techniques that IAEA safeguards inspectors can use to acquire and analyze information relevant to the performance of successful safeguards inspections. These techniques include a range of cognitive, analytic, judgmental, interpersonal, and communications skills that have the potential to help IAEA safeguards inspectors function more effectively.

  12. United States Program for Technical assistance to IAEA Standards. Concept Paper: Knowledge Acquisition, Skills training for enhanced IAEA safeguards inspections

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-11-01

    This concept paper explores the potential contribution of ``Knowledge Acquisition Skills`` in enhancing the effectiveness of international safeguards inspections by the International Atomic energy Agency (IAEA, or Agency) and identifies types of training that could be provided to develop or improve such skills. For purposes of this concept paper, Knowledge Acquisition Skills are defined broadly to include all appropriate techniques that IAEA safeguards inspectors can use to acquire and analyze information relevant to the performance of successful safeguards inspections. These techniques include a range of cognitive, analytic, judgmental, interpersonal, and communications skills that have the potential to help IAEA safeguards inspectors function more effectively.

  13. University-level Non-proliferation and Safeguards Education and Human Capital Development Activities at Brookhaven National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Bachner K. M.; Pepper, S.; Gomera, J.; Einwechter, M.; Toler, L. T.

    2016-07-24

    BNL has offered Nuclear Nonproliferation, Safeguards and Security in the 21st Century,? referred to as NNSS, every year since 2009 for graduate students in technical and policy fields related to nuclear safeguards and nonproliferation. The course focuses on relevant policy issues, in addition to technical components, and is part of a larger NGSI short course initiative that includes separate courses that are delivered at three other national laboratories and NNSA headquarters. [SCHOLZ and ROSENTHAL] The course includes lectures from esteemed nonproliferation experts, tours of various BNL facilities and laboratories, and in-field and table-top exercises on both technical and policy subjects. Topics include the history of the Treaty on the Non-proliferation of Nuclear Weapons (NPT) and other relevant treaties, the history of and advances in international nuclear safeguards, current relevant political situations in countries such as Iran, Iraq, and the Democratic Peoples? Republic of Korea (DPRK), nuclear science and technology, instrumentation and techniques used for verification activities, and associated research and development. The students conduct a mock Design Information Verification (DIV) at BNL?s decommissioned Medical Research Reactor. The capstone of the course includes a series of student presentations in which students act as policy advisors and provide recommendations in response to scenarios involving a current nonproliferation related event that are prepared by the course organizers. ?The course is open to domestic and foreign students, and caters to students in, entering, or recently having completed graduate school. Interested students must complete an application and provide a resume and a statement describing their interest in the course. Eighteen to 22 students attend annually; 165 students have completed the course to date. A stipend helps to defray students? travel and subsistence expenses. In 2015, the course was shortened from three weeks to

  14. Generative Semantics

    Science.gov (United States)

    Bagha, Karim Nazari

    2011-01-01

    Generative semantics is (or perhaps was) a research program within linguistics, initiated by the work of George Lakoff, John R. Ross, Paul Postal and later McCawley. The approach developed out of transformational generative grammar in the mid 1960s, but stood largely in opposition to work by Noam Chomsky and his students. The nature and genesis of…

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

    Energy Technology Data Exchange (ETDEWEB)

    Beddingfield, David H [Los Alamos National Laboratory; Lafleur, Adrienne M [Los Alamos National Laboratory

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Gastelum, Zoe N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Henry, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Burtner, IV, E. R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Doehle, J. R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hampton, S. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); La Mothe, R. R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nordquist, P. L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zarzhitsky, D. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    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.

  17. Initial Object Segmentation for Video Object Plane Generation Using Cellular Neural Networks%在视频对象平面生成中使用细胞神经网络进行初始对象的分割

    Institute of Scientific and Technical Information of China (English)

    王慧; 杨高波; 张兆扬

    2003-01-01

    MPEG-4 is a basic tool for interactivity and manipulation of video sequences. Video object segmentation is a key issue indefining the content of any video sequence, which is often divided into two steps: initial object segmentation and object tracking. Inthis paper, an initial object segmentation method for video object plane(VOP) generation using color information is proposed. Based on3 by 3 linear templates, a cellular neural network (CNN) is used to implemented object segmentation, The Experimental results arepresented to verify the efficiency and robustness of this approach.

  18. Evaluating Safeguards in a Conservation Incentive Program: Participation, Consent, and Benefit Sharing in Indigenous Communities of the Ecuadorian Amazon

    Directory of Open Access Journals (Sweden)

    Torsten Krause

    2013-12-01

    Full Text Available Critics suggest that Reducing Emissions from Deforestation and forest Degradation (REDD+ may not generate improvements in well-being for participating stakeholders, and may in fact undermine indigenous rights. To ensure positive social benefits from REDD+ projects, the United Nations REDD Programme has proposed core safeguards, including local stakeholder participation; free, prior, and informed consent; and equitable distribution of benefits. However, there is little experience to date in implementing and evaluating these safeguards. We apply these core safeguards as a framework to study how people in indigenous communities in the Ecuadorian Amazon perceive and benefit from Programa Socio Bosque, a conservation incentive program in Ecuador's national REDD+ Programme portfolio. We interviewed 101 individuals in five communities that had participated in the Programa Socio Bosque for at least 18 months. Close to 80% of respondents reported that the decision to join Socio Bosque was made democratically, that they were familiar with the conservation goals of Socio Bosque, and that they were aware which area their community had selected for conservation. However, only 17% were familiar with the overall terms of the conservation agreement, implying that they were either not fully informed of or did not fully understand what they were consenting to in joining the program. Although the terms of the program require a community investment plan to be democratically developed by community members, less than half of respondents were aware of the existence of the investment plan, and fewer than 20% had participated in its development. The majority of respondents (61% reported that they did not know the amount of incentives that their community currently receives, and only 44% stated that incentives were managed democratically in communal assemblies. Moreover, although a slight majority (53% said they had noticed benefits to the community from participating in

  19. DEVELOPMENT OF AN ADHESIVE CANDLE FILTER SAFEGUARD DEVICE

    Energy Technology Data Exchange (ETDEWEB)

    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

  20. DEVELOPMENT OF AN ADHESIVE CANDLE FILTER SAFEGUARD DEVICE

    Energy Technology Data Exchange (ETDEWEB)

    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

  1. Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control

    Energy Technology Data Exchange (ETDEWEB)

    Forsberg, C.W.; Storch, S.N. [Oak Ridge National Lab., TN (United States); Lewis, L.C. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

    1998-07-07

    The US investigated the use of {sup 233}U for weapons, reactors, and other purposes from the 1950s into the 1970s. Based on the results of these investigations, it was decided not to use {sup 233}U on a large scale. Most of the {sup 233}U-containing materials were placed in long-term storage. At the end of the cold war, the US initiated, as part of its arms control policies, a disposition program for excess fissile materials. Other programs were accelerated for disposal of radioactive wastes placed in storage during the cold war. Last, potential safety issues were identified related to the storage of some {sup 233}U-containing materials. Because of these changes, significant activities associated with {sup 233}U-containing materials are expected. This report is one of a series of reports to provide the technical bases for future decisions on how to manage this material. A basis for defining when {sup 233}U-containing materials can be managed as waste and when they must be managed as concentrated fissile materials has been developed. The requirements for storage, transport, and disposal of radioactive wastes are significantly different than those for fissile materials. Because of these differences, it is important to classify material in its appropriate category. The establishment of a definition of what is waste and what is fissile material will provide the guidance for appropriate management of these materials. Wastes are defined in this report as materials containing sufficiently small masses or low concentrations of fissile materials such that they can be managed as typical radioactive waste. Concentrated fissile materials are defined herein as materials containing sufficient fissile content such as to warrant special handling to address nuclear criticality, safeguards, and arms control concerns.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  4. Safeguarding what and for whom? The role of institutional fit in shaping REDD+ in Mexico

    Directory of Open Access Journals (Sweden)

    Constance L. McDermott

    2016-03-01

    Full Text Available This paper examines the UN Framework Convention on Climate Change mechanism Reducing Emissions from Deforestation and Degradation (REDD+, and its associated multitude of global to local safeguards, as they apply to a single ejido on the Yucatan Peninsula, Mexico. It draws on written sources and interviews to analyze the ways in which broad international norms articulated through the REDD+ safeguards, including support for human rights and sustainable livelihoods for local communities, are translated at national, regional, and local levels. Our findings indicate a wide range of perspectives on what constitutes sustainability, from strict conservation to more forest use-oriented strategies, such as community forestry and traditional Mayan shifting cultivation. These visions, in turn, shape what types of REDD+ interventions are considered a good "environmental fit," i.e., that fit the environmental problems they aim to address. Fits and misfits also occur between institutions, and play a core role in determining whose visions of sustainability prevail. We found a good fit in the case study ejido between REDD+ and the Payment for Ecosystem service (PES scheme, which sets the parameters for what counts as "sustainable livelihoods" within a strict conservation paradigm. We likewise found a good fit between REDD+ safeguards and institutions supporting local community rights to reject REDD+ projects. However, despite the strength of procedural safeguards, the parameters of the PES scheme constrained the choice of REDD+ activities available, including the possibilities of local people to work on the farm and in the forest, and hence the scope of its distributive benefits. This highlights the important, but also problematic, roles of institutional and environmental "fit" in determining whose rights are safeguarded and what is recognized as a sustainable livelihood strategy. It also calls for more proactive efforts to expand the range of REDD+ activities

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Pan, Paul Y [Los Alamos National Laboratory

    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.

  7. Towards integrated safeguards in Spain: implementation issues at the Juzbado plant

    Energy Technology Data Exchange (ETDEWEB)

    Zurron-Cifuentes, Oscar; Luis-Merino, Marcos [Department of Safety, ENUSA Industrias Avanzadas S.A., Juzbado Nuclear Fuel Fabrication Plant, Ctra. Salamanca-Ledesma, km. 26, 37015 Juzbado, Salamanca (Spain)

    2010-07-01

    Nuclear safeguards are implemented on the global international scale by the International Atomic Energy Agency (IAEA), which aims to verify that a State uses nuclear energy for only peaceful purposes, whereas in the European Union (EU) the European Commission applies nuclear safeguards to make certain that nuclear materials are not diverted to purposes other than those for which are intended. Thus, nuclear operators in the EU are subjected to the scrutiny of two different Inspectorates with different goals. To cope with this issue, safeguards in the EU are undertaken on a joint team partnership approach (EURATOM/IAEA), designed to minimise the burden on nuclear operators whilst ensuring that both Inspectorates are able to meet the goals derived from their respective safeguards regime. Notwithstanding, nuclear safeguards implementation has largely evolved since 1950's to the present day, which implies a continuous effort to adapt the EURATOM/IAEA's partnership agreements to state-of-the art approaches without excessive burden to nuclear operators. In this context, Integrated Safeguards (IS) can be seen as the latest evolution of the IAEA's safeguards regime. IS introduces new key factors to provide credible assurance of both the non-diversion of nuclear material from declared nuclear activities and the absence of undeclared nuclear material and activities in the State as a whole. The adaptation of the EU States to this new regime has just been finished. Nevertheless, the way to IS has not always been straight and easy, mainly because several parties were involved in the discussions and the common minimum denominator was sometimes hard to achieve. In particular, discussions in Spain started by 2004 and finished at the end of 2009. An example is the Facility Specific Partnership Approach agreement for the Juzbado Plant, which entered into force recently in September 2009 and governs IS implementation at the Juzbado Plant. This paper briefly describes

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

    Energy Technology Data Exchange (ETDEWEB)

    Disser, Jay; Arthur, Edward; Lambert, Janine

    2016-09-01

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

  9. Initial generation of sand across climate zones of the Mojave, Sierra Nevada, and Klamath Batholiths in California, U.S.A.

    Science.gov (United States)

    Hessler, Angela M.; Lowe, Donald R.

    2017-03-01

    The generation of modern, plutoniclastic sediment across California varies with climate, resulting in significant mineralogical and geochemical differences between parent rock, weathering profile material, and low-order stream sand. With average precipitation of 15 cm/yr in the arid zones and 120 cm/yr in the temperate zones, feldspar is relatively decreased in stream sand (compared to parent rock) by paleoclimate studies, where a moderate precipitation shift is capable of producing a significant loss of feldspar. The differential response of common minerals to chemical weathering should be considered for studies and modeling related to bedrock erodibility, sediment supply, and landscape evolution.

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

    Energy Technology Data Exchange (ETDEWEB)

    Davis, G.; Mansur, D.L.; Ruhter, W.D.; Steele, E.; Strait, R.S.

    1994-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  12. Experimentally investigating efficiency of using the catalytic blocks in a small N2O gas-generators with resonant initiation system

    Directory of Open Access Journals (Sweden)

    K. Yu. Aref'ev

    2014-01-01

    Full Text Available The object of research work are small gasifiers (SGF to nitrous oxide(N2O gas-dynamic resonance system (GRS initiate the workflow. Subject of research - methods to improve the efficiency of the SGF . Relevance of the work is determined by what is currently on the SGF as nitrous oxidemonopropellant are widely used in aerospace engineering, in particular in various power plant and increasing the efficiency of decomposition of N2O is an important scientific and technical challenge .Duty cycle begins after the SGF through the nozzle GRS gas N2O. At a certain ratio geometrical and operational parameters of the SGF in the area of the nozzle is formed GRS unstable region gasdynamic flow consisting of "holes" and the Mach disk . In the case where the Mach disk is localized in the leading edge cavity , mounted coaxially with the nozzle GRS longitudinal oscillations occur supported kinetic energy of the feed gas . In this case, stagnant zone of the resonator is carried out intensive heating nitrous oxidegas . The heat release is due to the high frequency of the cyclic process of transmission and reflection from the end wall of the cavity shock waves (SW . The high temperature level in the resonant cavity causes the thermal decomposition of N2O with the evolution of heat and the spread of this upstream process and then run the SGF .The aim is to improve the methods of experimental study of the effectiveness of the SGF with the GRS , including the use of catalytic converters and original heating nitrous oxide. The objectives of the study is to determine the characteristics , comparative analysis and synthesis of the results obtained for the three variants of the GRS (without catalytic converters , with the end surface of the cavity of the catalytic material , the end surface of the cavity of the catalytic material and the catalyst unit IDI when the initial temperature of N2O in the range of initial temperature 300 ... 600 K.The paper presents a diagram of

  13. 76 FR 18586 - Advisory Committee on Reactor Safeguards; Revised Meeting Notice

    Science.gov (United States)

    2011-04-04

    ... discussion on the Commission Paper on Emergency Planning for Small Modular Reactors, scheduled to be held on... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Revised Meeting Notice The Agenda for the 582nd...

  14. From "Public Health" to "Safeguarding Children": British Health Visiting in Policy, Practice and Research

    Science.gov (United States)

    Peckover, Sue

    2013-01-01

    This study examines the location of British health visiting in contemporary policy discourses concerned with public health and safeguarding children. It argues that professional identity and orientation can be understood through health visiting's long history of public health work with children and families, which has included an engagement with…

  15. Federal Privacy Laws That Apply to Children and Education. Safeguarding Data

    Science.gov (United States)

    Data Quality Campaign, 2014

    2014-01-01

    This table identifies and briefly describes the following federal policies that safeguard and protect the confidentiality of personal information: (1) Family Educational Rights and Privacy Act (FERPA); (2) Protection of Pupil Rights Amendment (PPRA); (3) Health Insurance Portability and Accountability Act (HIPAA); (4) Children's Online Privacy…

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  17. Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2007-10-01

    The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

  18. 30 CFR 77.1112 - Welding, cutting, or soldering with arc or flame; safeguards.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Welding, cutting, or soldering with arc or... WORK AREAS OF UNDERGROUND COAL MINES Fire Protection § 77.1112 Welding, cutting, or soldering with arc or flame; safeguards. (a) When welding, cutting, or soldering with arc or flame near...

  19. 77 FR 74697 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2012-12-17

    ... participation in ACRS meetings were published in the Federal Register on October 18, 2012, (77 FR 64146- 64147... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on January 18, 2013, Room...

  20. 78 FR 50457 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2013-08-19

    ... October 18, 2012, (77 FR 64146-64147). Detailed meeting agendas and meeting transcripts are available on... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on September 4, 2013, Room...

  1. 77 FR 28637 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2012-05-15

    ... participation in ACRS meetings were published in the Federal Register on October 17, 2011, (76 FR 64126- 64127... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on May 22- 23, 2012, Room...

  2. 77 FR 31676 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2012-05-29

    ... October 17, 2011, (76 FR 64126- 64127). Detailed meeting agendas and meeting transcripts are available on... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on June 20, 2012, Room...

  3. 78 FR 2694 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2013-01-14

    ... the Federal Register on Monday, December 17, 2012, (77 FR 74697-74698). Information regarding this... COMMISSION Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Fukushima; Cancellation of the January 18, 2013, ACRS Subcommittee Meeting The ACRS Subcommittee meeting on...

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

    Science.gov (United States)

    2012-05-16

    ... ACRS meetings were published in the Federal Register on October 17, 2011, (76 FR 64126-64127). Detailed... COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on May 22, 2012, Room...

  5. 78 FR 27442 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2013-05-10

    ... were published in the Federal Register on October 18, 2012, (77 FR 64146- 64147). Detailed meeting... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on May 23, Room T-2B1,...

  6. 76 FR 44377 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2011-07-25

    ... participation in ACRS meetings were published in the Federal Register on October 21, 2010, (75 FR 65038-65039... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on August 16, 2011, Room...

  7. 77 FR 52371 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2012-08-29

    ... Register on October 17, 2011, (76 FR 64126- 64127). Detailed meeting agendas and meeting transcripts are... COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on September 5, 2012, Room...

  8. 77 FR 59676 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2012-09-28

    ... in ACRS meetings were published in the Federal Register on October 17, 2011, (76 FR 64126-64127... COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on October 3, 2012, Room...

  9. 78 FR 65008 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Fukushima...

    Science.gov (United States)

    2013-10-30

    ... October 18, 2012, (77 FR 64146-64147). Detailed meeting agendas and meeting transcripts are available on... COMMISSION Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on November 5, 2013, Room...

  10. 76 FR 34778 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2011-06-14

    ..., (75 FR 65038-65039). Detailed meeting agendas and meeting transcripts are available on the NRC Web... COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on June 23, 2011, Room...

  11. 78 FR 17945 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2013-03-25

    ... Register on October 18, 2012, (77 FR 64146-64147). Detailed meeting agendas and meeting transcripts are... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on April 10, 2013, Room...

  12. 77 FR 68161 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2012-11-15

    ... Register on October 18, 2012 (77 FR 64146- 64147). Detailed meeting agendas and meeting transcripts are... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on December 4, 2012, Room...

  13. 78 FR 51752 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2013-08-21

    ... participation in ACRS meetings were published in the Federal Register on October 18, 2012, (77 FR 64146- 64147... COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on September 18, 2013, Room...

  14. 76 FR 27103 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2011-05-10

    ... were published in the Federal Register on October 21, 2010 (75 FR 65038-65039). Detailed meeting... COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on May 26, 2011, Room...

  15. 77 FR 64147 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2012-10-18

    ... published in the Federal Register on October 17, 2011 (76 FR 64126- 64127). Detailed meeting agendas and... COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting The ACRS Subcommittee on Fukushima will hold a meeting on October 31, 2012, Room...

  16. 13 CFR 108.506 - Safeguarding the NMVC Company's assets/Internal controls.

    Science.gov (United States)

    2010-01-01

    ... assets/Internal controls. 108.506 Section 108.506 Business Credit and Assistance SMALL BUSINESS... Requirements § 108.506 Safeguarding the NMVC Company's assets/Internal controls. You must adopt a plan to... document describing your control procedures....

  17. 77 FR 45700 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Fukushima...

    Science.gov (United States)

    2012-08-01

    ... [Federal Register Volume 77, Number 148 (Wednesday, August 1, 2012)] [Notices] [Page 45700] [FR... October 17, 2011, (76 FR 64126- 64127). Detailed meeting agendas and meeting transcripts are available on... Branch, Advisory Committee on Reactor Safeguards. [FR Doc. 2012-18763 Filed 7-31-12; 8:45 am]...

  18. 77 FR 45699 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima...

    Science.gov (United States)

    2012-08-01

    ... [Federal Register Volume 77, Number 148 (Wednesday, August 1, 2012)] [Notices] [Page 45699] [FR... Register on October 17, 2011, (76 FR 64126-64127). Detailed meeting agendas and meeting transcripts are... Advisor, Advisory Committee on Reactor Safeguards. [FR Doc. 2012-18757 Filed 7-31-12; 8:45 am]...

  19. Human Rights Safeguards in Criminal Procedure——An interview with Prof. Fan Chongyi

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    @@ The issue relating to human rights safeguards in criminal procedure has of late attracted extensive attention. A Human Rights reporter recently interviewed Prof. Fan Chongyi of China University of Political Science and Law on the issue. Following are excerpts of the interview.

  20. Child Ecology: Dimensions to Safeguard the Development and Education of Children.

    Science.gov (United States)

    Schleicher, Klaus

    A human-ecological dimension is needed to safeguard the development of children. This "child ecology" will protect children against alienating forces of modern civilization caused by rapid social, cultural, and technical changes. The human-ecological dimension is a contribution toward regaining an overall framework for human self-interpretation…

  1. 75 FR 10840 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Subcommittee on Advanced Boiling...

    Science.gov (United States)

    2010-03-09

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Subcommittee on Advanced Boiling Water Reactor (ABWR); Notice of Meeting The ACRS Subcommittee on ABWR will hold a meeting on March 18...

  2. 75 FR 7632 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Subcommittee on Advanced Boiling...

    Science.gov (United States)

    2010-02-22

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Subcommittee on Advanced Boiling Water Reactor (ABWR) The ACRS Subcommittee on ABWR will hold a meeting on March 2, 2010, at 11545...

  3. 78 FR 40773 - Order Imposing Requirements for the Protection of Certain Safeguards Information (Effective...

    Science.gov (United States)

    2013-07-08

    ..., include verification of employment, education, and personal references. The licensee shall also, to the..., contractual, or licensee duties of employment. The Licensee and all other persons who obtain Safeguards...., seeking references not supplied by the individual). (b) If an individual's employment has been less...

  4. Reactor antineutrino monitoring with a plastic scintillator array as a new safeguards method

    CERN Document Server

    Oguri, S; Kato, Y; Nakata, R; Inoue, Y; Ito, C; Minowa, M

    2014-01-01

    We developed a segmented reactor-antineutrino detector made of plastic scintillators for application as a tool in nuclear safeguards inspection and performed mostly unmanned field operations at a commercial power plant reactor. At a position outside the reactor building, we measured the difference in reactor antineutrino flux above the ground when the reactor was active and inactive.

  5. 18 CFR 3b.204 - Safeguarding information in manual and computer-based record systems.

    Science.gov (United States)

    2010-04-01

    ... information in manual and computer-based record systems. 3b.204 Section 3b.204 Conservation of Power and Water... Collection of Records § 3b.204 Safeguarding information in manual and computer-based record systems. (a) The administrative and physical controls to protect the information in the manual and computer-based record...

  6. 77 FR 7618 - Advisory Committee on Reactor Safeguards; Meeting of the ACRS Subcommittee on Planning and...

    Science.gov (United States)

    2012-02-13

    ... COMMISSION Advisory Committee on Reactor Safeguards; Meeting of the ACRS Subcommittee on Planning and Procedures; Notice of Meeting The ACRS Subcommittee on Planning and Procedures will hold a meeting on March 7... the Chairman as necessary to facilitate the conduct of the meeting, persons planning to attend...

  7. 75 FR 13611 - Advisory Committee on Reactor Safeguards (ACRS) Planning and Procedures Subcommittee Meeting...

    Science.gov (United States)

    2010-03-22

    ... COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Planning and Procedures Subcommittee Meeting; Notice of Meeting The ACRS Planning and Procedures Subcommittee will hold a meeting on April 7, 2010, at Room T2-B1, at 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

  8. 75 FR 7634 - Advisory Committee on Reactor Safeguards (ACRS); Planning and Procedures Subcommittee Meeting...

    Science.gov (United States)

    2010-02-22

    ... COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Planning and Procedures Subcommittee Meeting; Notice of Meeting The ACRS Planning and Procedures Subcommittee will hold a meeting on March 3, 2010, Room T2-B1, at 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to...

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

    Science.gov (United States)

    2011-03-02

    ... and Probabilistic Risk Assessment (PRA); Notice of Meeting The ACRS Subcommittee on Reliability and Probabilistic Risk Assessment (PRA), Room T-2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting..., Reactor Safety Branch B, Advisory Committee on Reactor Safeguards. BILLING CODE 7590-01-P...

  10. 76 FR 22934 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Reliability...

    Science.gov (United States)

    2011-04-25

    ... and Probabilistic Risk Assessment; Notice of Meeting The ACRS Subcommittee on Reliability and Probabilistic Risk Assessment (PRA) will hold a meeting on May 11, 2011, Room T-2B3, 11545 Rockville Pike..., Acting Chief, Reactor Safety Branch B, Advisory Committee on Reactor Safeguards. BILLING CODE 7590-01-P...

  11. Start-up and safeguarding of an industrial adiabatic tubular reactor

    NARCIS (Netherlands)

    Verwijs, J.W.; Berg, van den H.; Westerterp, K.R.

    1994-01-01

    The safeguarding methodology currently used in the chemical industry is based on controlling the instantaneous values of the process state variables within a certain operating window, the process being brought to shut-down when the operating constraints are exceeded. It is concluded from an analysis

  12. Startup strategy design and safeguarding of industrial adiabatic tubular reactor systems

    NARCIS (Netherlands)

    Verwijs, J.W.; Berg, van den H.; Westerterp, K.R.

    1996-01-01

    The safeguarding methodology of chemical plants is usually based on controlling the instantaneous values of process state variables within a certain operating window, the process being brought to shutdown when operating constraints are exceeded. This method does not necessarily prevent chemical reac

  13. The Case for Social Safeguards in a Post-2012 Agreement on REDD

    Directory of Open Access Journals (Sweden)

    David J. Kelly

    2010-06-01

    Full Text Available This paper explores the policy need and legal case for including social safeguards in a post-2012 agreement on reducing emissions from deforestation and forest degradation (REDD. One serious charge laid against so called 'market-based' approaches to REDD is the potential for forest dwelling communities to be dispossessed from their land and to lose other rights afforded to them in international human rights law. Rather than criticise current REDD proposals as being inherently negative for forest dwelling communities, this paper asks firstly, whether REDD can potentially work in their favour and secondly, how such an opportunity could be realised in a future REDD agreement. After reviewing current REDD proposals and related threats, this paper argues for the inclusion of social safeguards within the post-2012 agreement on REDD. The primary cause of forest dwelling communities vulnerability is not REDD itself but the potential for REDD to operate in the absence of social safeguards. This paper presents four mutually reinforcing safeguards to protect forest dwelling communities in the context of a future agreement on REDD. This paper finds that a REDD market which requires minimum international standards of social protection is likely to benefit forest dwelling communities.

  14. Safeguards in a world of ambient intelligence: A social, economic, legal, and ethical perspective

    NARCIS (Netherlands)

    van den Broek, Egon

    2011-01-01

    The book "Safeguards in a world of ambient intelligence" is unique in its kind. It discusses social, economic, legal, technological and ethical issues related to identity, privacy and security in Ambient Intelligence (AmI). It introduces AmI and, subsequently, makes it vivid by describing four scena

  15. Start-up and safeguarding of an industrial adiabatic tubular reactor

    NARCIS (Netherlands)

    Verwijs, J.W.; van den Berg, Henderikus; Westerterp, K.R.

    1994-01-01

    The safeguarding methodology currently used in the chemical industry is based on controlling the instantaneous values of the process state variables within a certain operating window, the process being brought to shut-down when the operating constraints are exceeded. It is concluded from an analysis

  16. Privacy by Design: An alternative to existing practice in safeguarding privacy

    NARCIS (Netherlands)

    Lieshout, M.J. van; Kool, L.; Schoonhoven, B. van; Jonge, M. de

    2011-01-01

    Purpose: The purpose of this paper is to develop/elaborate the concept Privacy by Design (PbD) and to explore the validity of the PbD framework. Design/methodology/approach: Attention for alternative concepts, such as PbD, which might offer surplus value in safeguarding privacy, is growing. Using

  17. 78 FR 56541 - Concept Release on Risk Controls and System Safeguards for Automated Trading Environments

    Science.gov (United States)

    2013-09-12

    ... September 12, 2013 Part IV Commodity Futures Trading Commission 17 CFR Chapter I Concept Release on Risk Controls and System Safeguards for Automated Trading Environments; Proposed Rule #0;#0;Federal Register / Vol. 78 , No. 177 / Thursday, September 12, 2013 / Proposed Rules#0;#0; ] COMMODITY FUTURES...

  18. Everybody's Business? A Research Review of the Informal Safeguarding of Other People's Children in the UK

    Science.gov (United States)

    Holland, Sally; Tannock, Stuart; Collicott, Hayley

    2011-01-01

    The paper reviews public discourses and research on the safeguarding of other people's children by adults at the neighbourhood level. There is much empirical evidence pointing to the existence of thriving informal communities of support and informal childcare for parents across the social classes. There appears to be less empirical evidence…

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

    Energy Technology Data Exchange (ETDEWEB)

    Laughter, Mark D [ORNL; Whitaker, J Michael [ORNL; Howell, John [University of Glasgow

    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

  20. Geminin: a major DNA replication safeguard in higher eukaryotes

    DEFF Research Database (Denmark)

    Melixetian, Marina; Helin, Kristian

    2004-01-01

    Eukaryotes have evolved multiple mechanisms to restrict DNA replication to once per cell cycle. These mechanisms prevent relicensing of origins of replication after initiation of DNA replication in S phase until the end of mitosis. Most of our knowledge of mechanisms controlling prereplication...