Sample records for transportation safeguards division

  1. Tempe Transportation Division: LNG Turbine Hybrid Electric Buses

    SciTech Connect (OSTI)

    Not Available

    2002-02-01T23:59:59.000Z

    Fact sheet describes the performance of liquefied natural gas (LNG) turbine hybrid electric buses used in Tempe's Transportation Division.

  2. Transportation Safeguards & Security Test Bed (TSSTB) | ORNL

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin Transition in2, 2003ToolsearchTransportationTransportation

  3. Transportation Energy Technology DivisionEnergy Technology Division --TribologyTribology

    E-Print Network [OSTI]

    -frictionless carbon coatings to the components when appropriate · Develop and evaluate polymer composite materials to their prototype using Hitco C/C composite and anodized aluminum material combination. · Fabricated and evaluatedTransportation Materials Energy Technology DivisionEnergy Technology Division -- Tribology

  4. Safeguards Culture

    SciTech Connect (OSTI)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2012-07-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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)

    2011-07-01T23:59:59.000Z

    Nuclear reactors have served as the neutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these very weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Our SNL/LLNL collaboration has demonstrated that such antineutrino based monitoring is feasible using a relatively small cubic meter scale liquid scintillator detector at tens of meters standoff from a commercial Pressurized Water Reactor (PWR). With little or no burden on the plant operator we have been able to remotely and automatically monitor the reactor operational status (on/off), power level, and fuel burnup. The initial detector was deployed in an underground gallery that lies directly under the containment dome of an operating PWR. The gallery is 25 meters from the reactor core center, is rarely accessed by plant personnel, and provides a muon-screening effect of some 20-30 meters of water equivalent earth and concrete overburden. Unfortunately, many reactor facilities do not contain an equivalent underground location. We have therefore attempted to construct a complete detector system which would be capable of operating in an aboveground location and could be transported to a reactor facility with relative ease. A standard 6-meter shipping container was used as our transportable laboratory - containing active and passive shielding components, the antineutrino detector and all electronics, as well as climate control systems. This aboveground system was deployed and tested at the San Onofre Nuclear Generating Station (SONGS) in southern California in 2010 and early 2011. We will first present an overview of the initial demonstrations of our below ground detector. Then we will describe the aboveground system and the technological developments of the two antineutrino detectors that were deployed. Finally, some preliminary results of our aboveground test will be shown. (authors)

  6. The safeguards options study

    SciTech Connect (OSTI)

    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

    1995-04-01T23:59:59.000Z

    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. and Pollutant Safeguarding Buildings

    E-Print Network [OSTI]

    commercial buildings, these flows are driven primarily by the building's ventilation system, but natural2004 Airflow and Pollutant Transport Group Safeguarding Buildings Against Chemical and Biological research since 1998 to protect buildings and building occupants from threats posed by airborne chemical

  8. Zachary Hensley, Jibonananda Sanyal, Joshua New Energy and Transportation Sciences Division

    E-Print Network [OSTI]

    Wang, Xiaorui "Ray"

    modified and evaluated using different energy models, including DOE's EnergyPlus and multiple programsZachary Hensley, Jibonananda Sanyal, Joshua New Energy and Transportation Sciences Division@ornl.gov Provenance In the scientific world, it is important for researchers to know where their data came from

  9. SAFEGUARDS ENVELOPE

    SciTech Connect (OSTI)

    Duc Cao; Richard Metcalf

    2010-07-01T23:59:59.000Z

    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.

  10. Safeguards Culture: Lessons Learned

    SciTech Connect (OSTI)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2010-06-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    1995-08-01T23:59:59.000Z

    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.

  12. Modeling and Simulation for Safeguards

    SciTech Connect (OSTI)

    Swinhoe, Martyn T. [Los Alamos National Laboratory

    2012-07-26T23:59:59.000Z

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

  13. Safeguards Professional Development Opportunities

    SciTech Connect (OSTI)

    Gilligan, Kimberly V [ORNL

    2010-01-01T23:59:59.000Z

    Across the international field of safeguards there has been a rising awareness of the need for development of the next generation of safeguards professionals. The 2010 International Atomic Energy Agency Safeguards Symposium includes a suggested topic of 'developing safeguards professionals.' This can first be addressed by making university students and young professionals aware of safeguards and the unique career opportunities it encompasses. Then, once someone decides to go into safeguards he/she needs to be offered professional development opportunities in order to become a more effective member of the international safeguards community. This paper begins to do that by reviewing opportunities currently available. There are not many opportunities that are well advertised and this paper will serve to raise awareness of what does already exist and therefore benefit the international safeguards community. The current opportunities that will be discussed include training programs, graduate degrees, organizational outreach, professional networks, and intensive topic specific programs. The paper will also identify current needs and holes in the current offerings of professional development opportunities and suggest ways they can be filled. In the conclusion the paper addresses what types of programs are still needed.

  14. Safeguarding Health Information: Building Assurance through HIPAA Security Hosted by the HHS Office for Civil Rights (OCR) and the National Institute of Standards and Technology (NIST)

    E-Print Network [OSTI]

    1 Safeguarding Health Information: Building Assurance through HIPAA Security Hosted by the HHS, Acting Chief, Computer Security Division, Information Technology Laboratory (ITL), NIST 9 Data Using Encryption Matthew Scholl, Computer Security Division, Information Technology Laboratory

  15. Safeguards and Security Program

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

    2007-05-25T23:59:59.000Z

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

  16. Safeguards and Security Program

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

    1988-01-22T23:59:59.000Z

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

  17. Safeguards Envelope Methodology 

    E-Print Network [OSTI]

    Metcalf, Richard

    2012-02-14T23:59:59.000Z

    Nuclear safeguards are intrinsic and extrinsic features of a facility which reduce probability of the successful acquisition of special nuclear material (SNM) by hostile actors. Future bulk handling facilities in the United States will include both...

  18. Measuring Safeguards Culture

    SciTech Connect (OSTI)

    Frazar, Sarah L.; Mladineo, Stephen V.

    2011-07-19T23:59:59.000Z

    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.

  19. E-Print Network 3.0 - air transport division Sample Search Results

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

    Training Program Summary: or mode of delivery Course Purpose: Dry ice is regulated as Dangerous Goods when transported by air... to be trained in accordance...

  20. Relaxation Approximations to Shallow Water and Pollutant Transport Department of Sciences, Division of Mathematics,

    E-Print Network [OSTI]

    Katsaounis, Theodoros D.

    1 Relaxation Approximations to Shallow Water and Pollutant Transport Equations A.I. Delis solution of shallow water flows and the transport and diffusion of pollutant in such flows. By first can be considered as an alternative to classical finite difference methods. Keywords--Shallow water

  1. Safeguards and Security Program References

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

    2005-08-26T23:59:59.000Z

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

  2. Safeguard Security and Awareness Program

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

    2002-10-02T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2010-07-01T23:59:59.000Z

    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 methodology can be adapted for evaluating and assessing the safeguardability of nuclear facilities – both existing, as well as those still on the drawing board. The advantages of the Facility Safeguardability Analysis is that it would not only give the facility designer an analytical method for evaluating and assessing the safeguards measures and approaches for the prospective facility, but also the ability to optimize the design of the facility process for enhancing facility safeguardability. The following report explains the need for Facility Safeguardability Analysis and explains how it could be used in the Safeguards-by-Design, in support of the design and construction of nuclear facilities.

  4. Safeguards and Security Program

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

    2011-07-21T23:59:59.000Z

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

  5. Safeguards and Security Program

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

    2005-08-26T23:59:59.000Z

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

  6. NEAMS safeguards and separations

    SciTech Connect (OSTI)

    Sadasivan, Pratap [Los Alamos National Laboratory; De Paoli, David W [ORNL

    2011-01-25T23:59:59.000Z

    This presentation provides a program management update on the Safeguards and Separations Integrated Performance and Safety Code (IPSC) program in the DOE Nuclear Energy Advanced Modeling and Simulation (NEAMS). It provides an overview of FY11 work packages at multiple DOE Labs and includes material on challenge problem definitions for the IPSC effort.

  7. Safeguards and Security Program

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

    2010-12-29T23:59:59.000Z

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

  8. Statistics applied to safeguards

    SciTech Connect (OSTI)

    Picard, R.R.

    1993-05-01T23:59:59.000Z

    Statistical methods are central to safeguards work. Measurements forming the basis of much materials accountancy are not perfect - ``perfect`` in the sense of being error free. Other sessions in this course address the destructive and nondestructive measurement of nuclear material, together with the inherent limitations in those measurements. The bottom line is that measurement errors are a fact of life and, since we can`t eliminate them, we have to find a rational way to deal with them. Which leads to the world of statistics. Beyond dealing with measurement errors, another area of statistical application involves the sampling of items for verification. Inspectors from the IAEA and domestic regulatory agencies periodically visit operating facilities and make measurements of selected items. By comparing their own measured values to those declared by the facilities, increased confidence is obtained. If verification measurements were not expensive, time consuming, and disruptive to operations, perhaps verification of 100% of the inventories would be desirable. In reality, many constraints lead to inspection of only a portion of those inventories. Drawing inferences about a larger ``population`` of declared items in a facility based on verification information obtained from a sample of those items is a statistical problem. There are few texts on statistics in safeguards. The lengthy exposition ``IAEA Safeguards: Statistical Concepts and Techniques`` and the US NRC book edited by Bowen and Bennet are two good sources of general information. In the next section, the subject of measurement quality is addressed. The third section covers the evaluation of MUFs, and discusses the related subjects of error propagation and sequential analysis. The final section covers verification, inspection sample size calculations, and the D statistic. The text is written at an elementary level, with references to the safeguards literature for more detailed treatment.

  9. Statistics applied to safeguards

    SciTech Connect (OSTI)

    Picard, R.R.

    1993-01-01T23:59:59.000Z

    Statistical methods are central to safeguards work. Measurements forming the basis of much materials accountancy are not perfect - perfect'' in the sense of being error free. Other sessions in this course address the destructive and nondestructive measurement of nuclear material, together with the inherent limitations in those measurements. The bottom line is that measurement errors are a fact of life and, since we can't eliminate them, we have to find a rational way to deal with them. Which leads to the world of statistics. Beyond dealing with measurement errors, another area of statistical application involves the sampling of items for verification. Inspectors from the IAEA and domestic regulatory agencies periodically visit operating facilities and make measurements of selected items. By comparing their own measured values to those declared by the facilities, increased confidence is obtained. If verification measurements were not expensive, time consuming, and disruptive to operations, perhaps verification of 100% of the inventories would be desirable. In reality, many constraints lead to inspection of only a portion of those inventories. Drawing inferences about a larger population'' of declared items in a facility based on verification information obtained from a sample of those items is a statistical problem. There are few texts on statistics in safeguards. The lengthy exposition IAEA Safeguards: Statistical Concepts and Techniques'' and the US NRC book edited by Bowen and Bennet are two good sources of general information. In the next section, the subject of measurement quality is addressed. The third section covers the evaluation of MUFs, and discusses the related subjects of error propagation and sequential analysis. The final section covers verification, inspection sample size calculations, and the D statistic. The text is written at an elementary level, with references to the safeguards literature for more detailed treatment.

  10. Full spectrum optical safeguard

    DOE Patents [OSTI]

    Ackerman, Mark R. (Albuquerque, NM)

    2008-12-02T23:59:59.000Z

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

  11. Safeguards Laboratory (SL) | ORNL

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton n uSTEM-ASafeguards &Safeguards

  12. Us-Japan cooperation on safeguards

    SciTech Connect (OSTI)

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

    2009-01-01T23:59:59.000Z

    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.

  13. Master Safeguards and Security Agreements

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

    1988-02-03T23:59:59.000Z

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

  14. Safeguards and Security Program

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

    1995-09-28T23:59:59.000Z

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

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

    Office of Environmental Management (EM)

    Program, acronyms and abbereviations - DOE M 470.4-7 Safeguards and Security Program, acronyms and abbereviations - DOE M 470.4-7 August 26, 2005 Canceled Safeguards and Security...

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

    SciTech Connect (OSTI)

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

    2010-06-16T23:59:59.000Z

    The renaissance of efforts to expand the use of nuclear energy requires the parallel development of a renewed and more sophisticated work force. Growth in the nuclear sector with high standard of safety, safeguards and security requires skilled staff for design, operations, inspections etc. High-quality nuclear technology educational programs are diminished from past years, and the ability of universities to attract students and to meet future staffing requirements of the nuclear industry is becoming seriously compromised. Thus, education and training in nuclear engineering and sciences is one of the cornerstones for the nuclear sector. Teaching in the nuclear field still seems strongly influenced by national history but it is time to strengthen resources and collaborate. Moreover with the current nuclear security threats it becomes critical that nuclear technology experts master the basic principles not only of safety, but also of nuclear safeguards, nonproliferation and nuclear security. In Europe the European Nuclear Education Network (ENEN) Association has established the certificate 'European Master of Science in Nuclear Engineering (EMSNE)' as the classic nuclear engineering program covering reactor operation and nuclear safety. However, it does not include courses on nonproliferation, safeguards, or dual-use technologies. The lack of education in nuclear safeguards was tackled by the European Safeguards Research and Development Association (ESARDA), through development and implementation of safeguards course modules. Since 2005 the ESARDA Working Group, called the Training and Knowledge Management Working Group, (TKMWG) has worked with the Joint Research Centre (JRC) in Ispra, Italy to organize a Nuclear Safeguards and Nonproliferation course. This five-day course is held each spring at the JRC, and continues to show increasing interest as evidenced by the positive responses of international lecturers and students. The standard set of lectures covers a broad range of subjects, including nuclear material accountancy principles, legal definitions and the regulatory base and inspection tools and techniques. This 60% core part is given by representatives from regulatory bodies (The International Atomic Energy Agency (IAEA), Institute for Radiological Protection and Nuclear Safety, Directorate General for Nuclear Energy and Transport), industry (AREVA, British Nuclear Group), and research (Stockholm University, Hamburg University, Joint Research Centre-Institute of Transuranic Elements, and Joint Research Centre-Institute for the Protection of the Citizen). The remaining part is completed with topical lectures addressed by invited lecturers, such as from Pacific Northwest National Laboratory and the IAEA addressing topics of physical protection, illicit trafficking, the Iraq case study, exercises, including satellite imagery interpretation etc. With this structure of a stable core plus a variable set of invited lectures, the course will remain sustainable and up-to-date. A syllabus provides the students a homogeneous set of information material in nuclear safeguards and nonproliferation matters at the European and international level. In this way, the ESARDA TKMWG aims to contribute to a two-fold scientific-technical and political-juridical education and training.

  17. UNCLASSIFIED UNCLASSIFIED Nuclear Materials Management & Safeguards...

    National Nuclear Security Administration (NNSA)

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

  18. Nuclear Resonance Fluorescence for Safeguards Applications

    SciTech Connect (OSTI)

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

    2011-02-04T23:59:59.000Z

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

  19. Implementing Safeguards-by-Design

    SciTech Connect (OSTI)

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

    2010-02-01T23:59:59.000Z

    Executive Summary Excerpt Safeguards-by-Design (SBD) is an approach to the design and construction of nuclear facilities whereby safeguards are designed-in from the very beginning. It is a systematic and structured approach for fully integrating international and national safeguards (MC&A), physical security, and other proliferation barriers into the design and construction process for nuclear facilities. SBD is primarily a project management or project coordination challenge, and this report focuses on that aspect of SBD. The present report continues the work begun in 2008 and focuses specifically on the design process, or project management and coordination - the planning, definition, organization, coordination, scheduling and interaction of activities of the safeguards experts and stakeholders as they participate in the design and construction of a nuclear facility. It delineates the steps in a nuclear facility design and construction project, in order to provide the project context within which the safeguards design activities take place, describes the involvement of safeguards experts in the design process, the nature of their analyses, interactions and decisions, as well as describing the documents created and how they are used. Designing and constructing a nuclear facility is an extremely complex undertaking. The stakeholders in an actual project are many – owner, operator, State regulators, nuclear facility primary contractor, subcontractors (e.g. instrument suppliers), architect engineers, project management team, safeguards, safety and security experts, in addition to the IAEA and its team. The purpose of the present report is to provide a common basis for discussions amongst stakeholders to collaboratively develop a SBD approach that will be both practically useful and mutually beneficial. The principal conclusions from the present study are: • In the short term, the successful implementation of SBD is principally a project management problem. • 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.

  20. Apparatus for safeguarding a radiological source

    DOE Patents [OSTI]

    Bzorgi, Fariborz M

    2014-10-07T23:59:59.000Z

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

  1. Nuclear materials safeguards for the future

    SciTech Connect (OSTI)

    Tape, J.W.

    1995-12-31T23:59:59.000Z

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

  2. Safeguards instrumentation: a computer-based catalog

    SciTech Connect (OSTI)

    Fishbone, L.G.; Keisch, B.

    1981-08-01T23:59:59.000Z

    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.

  3. Safeguards Envelope Progress FY08

    SciTech Connect (OSTI)

    Robert Bean; Richard Metcalf; Aaron Bevill

    2008-09-01T23:59:59.000Z

    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.

  4. Process Monitoring for Nuclear Safeguards

    SciTech Connect (OSTI)

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

    2009-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Not Available

    1988-10-01T23:59:59.000Z

    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.

  6. Development of laser induced breakdown spectroscopy instrumentatin for safeguards applications

    SciTech Connect (OSTI)

    Barefield Il, James E [Los Alamos National Laboratory; Clegg, Samuel M [Los Alamos National Laboratory; Le, Loan A [Los Alamos National Laboratory; Lopez, Leon N [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    In September 2006, a Technical Meeting on Application of Laser Spectrometry Techniques in IAEA Safeguards was held at IAEA headquarters (HQ). One of the principal recommendations from this meeting was the need to 'pursue the development of novel complementary access instrumentation based on laser induced breakdown spectroscopy (LIBS) 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. This meeting was held at IAEA HQ from July 7-11,2008 and hosted by the Novel Technologies Unit (NTU). The meeting was attended by 12 LIBS experts from the Czech Republic, the European Commission, France, the Republic of Korea, the United States of America, Germany, the United Kingdom of Great Britain, Canada, and Northern Ireland. After a presentation of the needs of the IAEA inspectors, the LIBS experts were in agreement that needs as presented could be partially or fully fulfilled using LIBS instrumentation. The needs of the IAEA inspectors were grouped in the following broad categories: (1) Improvements to in-field measurements/environmental sampling; (2) Monitoring status of activity in a Hot Cell; (3) Verifying status of activity at a declared facility via process monitoring; and (4) Need for pre-screening of environmental samples before analysis. Under the Department of Energy/National Nuclear Security Administration (DOE/NNSA) Next Generation Safeguards Initiative (NGSI) Los Alamos National Laboratory is exploring three potential applications of LIBS for international safeguards. As part of this work, we are developing: (1) a user-friendly man-portable LIBS system to characterize samples across a wide range of elements in the periodic table from hydrogen up to heavy elements like plutonium and uranium; (2) a LIBS system that can be deployed in harsh environments such as gloveboxes and hot cells providing relative compositional analysis of process streams for example ratios like Cm/Pu and Cm/U; and (3) an inspector field deployable system that can be used to analyze the elemental composition of microscopic quantities of samples containing plutonium and uranium. In this paper we will describe our current development and performance testing results both in a fixed lab and measurements in field deployable configurations using LIBS instrumentation developed for applications to international safeguards.

  7. Simulation Enabled Safeguards Assessment Methodology

    SciTech Connect (OSTI)

    Robert Bean; Trond Bjornard; Thomas Larson

    2007-09-01T23:59:59.000Z

    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.

  8. Acoustic techniques in nuclear safeguards

    SciTech Connect (OSTI)

    Olinger, C.T.; Sinha, D.N.

    1995-07-01T23:59:59.000Z

    Acoustic techniques can be employed to address many questions relevant to current nuclear technology needs. These include establishing and monitoring intrinsic tags and seals, locating holdup in areas where conventional radiation-based measurements have limited capability, process monitoring, monitoring containers for corrosion or changes in pressure, and facility design verification. These acoustics applications are in their infancy with respect to safeguards and nuclear material management, but proof-of-principle has been demonstrated in many of the areas listed.

  9. Nuclear Safeguards and Security Challenge:

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for Renewable Energy:Nanowire3627 Federal Register /76Safeguards and Security Challenge:

  10. Safeguards Envelope Progress FY10

    SciTech Connect (OSTI)

    Richard Metcalf

    2010-10-01T23:59:59.000Z

    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.

  11. Safeguards for Uranium Extraction (UREX) +1a Process 

    E-Print Network [OSTI]

    Feener, Jessica S.

    2011-08-08T23:59:59.000Z

    safeguards approach is needed to show that a commercially sized UREX+ facility can be safeguarded to current international standards. A detailed safeguards approach for a UREX+1a reprocessing facility has been developed. The approach includes the use...

  12. PIA - Savannah River Nuclear Solutions Electronic Safeguards...

    Energy Savers [EERE]

    System (E3S) PIA - Savannah River Nuclear Solutions Electronic Safeguards Security System (E3S) More Documents & Publications PIA - 10th International Nuclear Graphite...

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

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

    ARCHIVED DOE O 470.1 Chg 1, Safeguards and Security Program by Website Administrator Functional areas: Environment, Safety, and Health, Hazardous Materials, Radiation Protection,...

  14. ALASKA DEPARTMENT OF LABOR & WORKFORCE DEVELOPMENT Division of Workers' Compensation

    E-Print Network [OSTI]

    115512, Juneau AK 99811-5512 REPORT OF OCCUPATIONAL INJURY OR ILLNESS AWCB Case Number (Division Use Only # 38. Give Details of How Injury or Illness Happened 39. Injury / Illness Due to Machine / Product Failure? YES NO 40. Mechanical Guard / Safeguards Provided? YES NO 41. List Any Machine / Substance

  15. Safeguards and security requirements for weapons plutonium disposition in light water reactors

    SciTech Connect (OSTI)

    Thomas, L.L.; Strait, R.S. [Lawrence Livermore National Lab., CA (United States). Fission Energy and Systems Safety Program

    1994-10-01T23:59:59.000Z

    This paper explores the issues surrounding the safeguarding of the plutonium disposition process in support of the United States nuclear weapons dismantlement program. It focuses on the disposition of the plutonium by burning mixed oxide fuel in light water reactors (LWR) and addresses physical protection, material control and accountability, personnel security and international safeguards. The S and S system needs to meet the requirements of the DOE Orders, NRC Regulations and international safeguards agreements. Experience has shown that incorporating S and S measures into early facility designs and integrating them into operations provides S and S that is more effective, more economical, and less intrusive. The plutonium disposition safeguards requirements with which the US has the least experience are the implementation of international safeguards on plutonium metal; the large scale commercialization of the mixed oxide fuel fabrication; and the transportation to and loading in the LWRs of fresh mixed oxide fuel. It is in these areas where the effort needs to be concentrated if the US is to develop safeguards and security systems that are effective and efficient.

  16. ORO Office Safeguards and Security Clearance Tracking System...

    Energy Savers [EERE]

    Office Safeguards and Security Clearance Tracking System and Visitor Control System PIA, Oak Ridge Operations Office ORO Office Safeguards and Security Clearance Tracking System...

  17. Organization of ISI by Divisions and Constituent Units Information Sciences Division

    E-Print Network [OSTI]

    Bandyopadhyay, Antar

    Biological Sciences Division Agricultural and Ecological Research Unit Human Genetics Unit Biological Unit Canteen Security Unit Medical Welfare Unit Telephone Unit Transport Unit Guest House Audio Visual

  18. Gas Centrifuge Enrichment Plant Safeguards System Modeling

    SciTech Connect (OSTI)

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

    2006-06-05T23:59:59.000Z

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

  19. Safeguards and Security Independent Oversight Program

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

    1998-12-23T23:59:59.000Z

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

  20. Safeguards and security issues during facility transition

    SciTech Connect (OSTI)

    Smith, M.R. [USDOE Office of Safeguards and Security, Washington, DC (United States); Zack, N.R. [Los Alamos National Lab., NM (United States). Safeguards Systems Group

    1993-12-31T23:59:59.000Z

    The transition of Department of Energy (DOE) production facilities to those destined for decontamination and decommissioning (D and D) must consider traditional safeguards and security requirements governing nuclear materials. Current DOE safeguards and security policy establishes specific requirements for the removal of facilities and waste from safeguards. However, the current physical security policy does not differentiate the protection of waste from usable materials. Other transition issues include: access of uncleared individuals, positioning security zones, nuclear material holdup, accounting for difficult-to-measure materials, inventory difference and resolution, and radiological/toxicological sabotage. Safeguards and security goals for facility transitioning must provide a workable, efficient and cost-effective system for accounting and protecting nuclear material. In depth protection strategies utilizing combinations of safeguards and security systems should be developed to meet these goals.

  1. Enhanced safeguards via solution monitoring

    SciTech Connect (OSTI)

    Burr, T.; Wangen, L.

    1996-09-01T23:59:59.000Z

    Solution monitoring is defined as the essentially continuous monitoring of solution level, density, and temperature in all tanks in the process that contain, or could contain, safeguards-significant quantities of nuclear material. This report describes some of the enhancements that solution monitoring could make to international safeguards. The focus is on the quantifiable benefits of solution monitoring, but qualitatively, solution monitoring can be viewed as a form of surveillance. Quantitatively, solution monitoring can in some cases improve diversion detection probability. For example, the authors show that under certain assumptions, solution monitoring can be used to reduce the standard deviation of the annual material balance, {sigma}{sub MB}, from approximately 17 kg to approximately 4 kg. Such reduction in {sigma}{sub MB} will not always be possible, as they discuss. However, in all cases, solution monitoring would provide assurance that the measurement error models are adequate so that one has confidence in his estimate of {sigma}{sub MB}. Some of the results in this report were generated using data that were simulated with prototype solution monitoring software that they are developing. An accompanying document describes that software.

  2. Separations and safeguards model integration.

    SciTech Connect (OSTI)

    Cipiti, Benjamin B.; Zinaman, Owen

    2010-09-01T23:59:59.000Z

    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.

  3. Safeguards Envelope Progress FY09

    SciTech Connect (OSTI)

    Richard Metcalf; Robert Bean

    2009-09-01T23:59:59.000Z

    The Safeguards Envelope is a strategy to determine a set of specific operating parameters which nuclear facilities may operate within to maximize safeguards effectiveness without sacrificing safety or plant efficiency. This paper details advanced statistical techniques will be applied to real plant process monitoring (PM) data from the Idaho Chemical Processing Plant (ICPP). As a result of the U.S. having no operating nuclear chemical reprocessing plants, there has been a strong interest in obtaining process monitoring data from the ICPP. The ICPP was shut down in 1996 and a recent effort has been made to retrieve the PM data from storage in a data mining effort. 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- testing7.

  4. FAQS Qualification Card - Safeguards and Security | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport in Representative Geologic MediaTreatment | Department ofMechanicalSafeguards and

  5. Transportation

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

    Transportation Home Agenda Awards Exhibitors Lodging Posters Registration Transportation Workshops Contact Us User Meeting Archives Users' Executive Committee Getting to Berkeley...

  6. Transportation

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

    Transportation Print Home Agenda Awards Exhibitors Lodging Posters Registration Transportation Workshops Contact Us User Meeting Archives Users' Executive Committee Getting to...

  7. safeguards

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby Dietrich57/%2A0/%2A en4/%2A2/%2A/%2A en

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

    SciTech Connect (OSTI)

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

    2012-08-01T23:59:59.000Z

    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.

  9. IAEA Safeguards: Past, Present, and Future

    SciTech Connect (OSTI)

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

    2012-06-14T23:59:59.000Z

    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.

  10. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    Energy Research and Development Division FINAL PROJECT REPORT SMART GRID ROADMAP and Development Division funding efforts are focused on the following RD&D program areas: · Buildings EndUse Energy Efficiency · Renewable Energy Technologies · Transportation The Smart Grid Roadmap

  11. Remote monitoring for international safeguards

    SciTech Connect (OSTI)

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

    1997-09-01T23:59:59.000Z

    Remote monitoring is not a new technology, and its application to safeguards relevant activities has been examined for a number of years. On behalf of the US Department of Energy and international partners, remote monitoring systems have been emplaced in nuclear facilities and laboratories in various parts of the world. The experience gained from these field trials of remote monitoring systems has shown the viability of the concept of using integrated monitoring systems. Although a wide variety of sensors has been used in the remote monitoring field trials conducted to date, the possible range of instrumentation that might be used has scarcely been touched. As the technology becomes widespread, large amounts of data will become available to inspectors responsible for safeguards activities at the sites. Effective use of remote monitoring will require processing, archiving, presenting, and assessing of these data. To provide reasonable efficiency in the application of this technology, data processing should be done in a careful and organized manner. The problem will be not an issue of poring over scant records but of surviving under a deluge of information made possible by modern technology. Fortunately, modern technology, which created the problem of the data glut, is available to come to the assistance of those inundated by data. Apart from the technological problems, one of the most important aspects of remote monitoring is the potential constraint related to the transmission of data out of a facility or beyond national borders. Remote monitoring across national borders can be seriously considered only in the context of a comprehensive, transparent, and open implementation regime.

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

    SciTech Connect (OSTI)

    NONE

    1996-07-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    NONE

    1997-07-01T23:59:59.000Z

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

  14. Feasibility of x ray fluorescence for spent fuel safeguards

    SciTech Connect (OSTI)

    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

    2010-01-01T23:59:59.000Z

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

  15. The Concept of Goals-Driven Safeguards

    SciTech Connect (OSTI)

    R. Wigeland; T Bjornard; B. Castle

    2009-02-01T23:59:59.000Z

    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.

  16. Advanced safeguards for the nuclear renaissance

    SciTech Connect (OSTI)

    Miller, Michael C [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

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

  17. Safeguards and Security Program Planning and Management

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

    2005-08-26T23:59:59.000Z

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

  18. Safeguards and Security Program Planning and Management

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

    2005-08-26T23:59:59.000Z

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

  19. Integrated Safeguards and Security Management (ISSM) Policy

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

    2001-05-08T23:59:59.000Z

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

  20. Safeguards and Security Program and Project Management

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

    2013-04-18T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2008-10-22T23:59:59.000Z

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

  2. AFCI Safeguards Enhancement Study: Technology Development Roadmap

    SciTech Connect (OSTI)

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

    2008-12-31T23:59:59.000Z

    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.

  3. Advanced Safeguards Approaches for New Reprocessing Facilities

    SciTech Connect (OSTI)

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

    2007-06-24T23:59:59.000Z

    U.S. efforts to promote the international expansion of nuclear energy through the Global Nuclear Energy Partnership (GNEP) will result in a dramatic expansion of nuclear fuel cycle facilities in the United States. New demonstration facilities, such as the Advanced Fuel Cycle Facility (AFCF), the Advanced Burner Reactor (ABR), and the Consolidated Fuel Treatment Center (CFTC) will use advanced nuclear and chemical process technologies that must incorporate increased proliferation resistance to enhance nuclear safeguards. The ASA-100 Project, “Advanced Safeguards Approaches for New Nuclear Fuel Cycle Facilities,” commissioned by the NA-243 Office of NNSA, has been tasked with reviewing and developing advanced safeguards approaches for these demonstration facilities. Because one goal of GNEP is developing and sharing proliferation-resistant nuclear technology and services with partner nations, the safeguards approaches considered are consistent with international safeguards as currently implemented by the International Atomic Energy Agency (IAEA). This first report reviews possible safeguards approaches for the new fuel reprocessing processes to be deployed at the AFCF and CFTC facilities. Similar analyses addressing the ABR and transuranic (TRU) fuel fabrication lines at AFCF and CFTC will be presented in subsequent reports.

  4. Transportation

    E-Print Network [OSTI]

    Vinson, Steve

    2013-01-01T23:59:59.000Z

    Transportation in ancient Egypt entailed the use of boats2007 Land transport in Roman Egypt: A study of economics andDieter 1991 Building in Egypt: Pharaonic stone masonry. New

  5. Chemical Technology Division annual technical report 1997

    SciTech Connect (OSTI)

    NONE

    1998-06-01T23:59:59.000Z

    The Chemical Technology (CMT) Division is a diverse technical organization with principal emphases in environmental management and development of advanced energy sources. The Division conducts research and development in three general areas: (1) development of advanced power sources for stationary and transportation applications and for consumer electronics, (2) management of high-level and low-level nuclear wastes and hazardous wastes, and (3) electrometallurgical treatment of spent nuclear fuel. The Division also performs basic research in catalytic chemistry involving molecular energy resources, mechanisms of ion transport in lithium battery electrolytes, and the chemistry of technology-relevant materials and electrified interfaces. In addition, the Division operates the Analytical Chemistry Laboratory, which conducts research in analytical chemistry and provides analytical services for programs at Argonne National Laboratory (ANL) and other organizations. Technical highlights of the Division`s activities during 1997 are presented.

  6. The state-level approach: moving beyond integrated safeguards

    SciTech Connect (OSTI)

    Tape, James W [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

    The concept of a State-Level Approach (SLA) for international safeguards planning, implementation, and evaluation was contained in the Conceptual Framework for Integrated Safeguards (IS) agreed in 2002. This paper describes briefly the key elements of the SLA, including State-level factors and high-level safeguards objectives, and considers different cases in which application of the SLA methodology could address safeguards for 'suspect' States, 'good' States, and Nuclear Weapons States hosting fuel cycle centers. The continued use and further development of the SLA to customize safeguards for each State, including for States already under IS, is seen as central to effective and efficient safeguards for an expanding nuclear world.

  7. Safeguards Envelope: The First Steps

    SciTech Connect (OSTI)

    Richard Metcalf; Jean Ragusa; Robert Bean

    2008-03-01T23:59:59.000Z

    The possibility exists for real time accountancy and assay of nuclear materials as they move through a reprocessing facility. This project aims to establish working parameters and local figures of merit to identify possible diversion in real time with minimal operational impact. Factors such as pH, NOX gas concentration, flow speeds and radiation fields are rarely taken into account in safeguards methodologies and will be included to increase the confidence of location and assay of nuclear materials. An adaptable, real data model is being created of the contactors of the Advanced Fuel Cycle Facility and will be analyzed using the appropriate modeling codes. This model will then be subjected to three, diversion scenarios and a figure of merit methodology will be utilized to create the operational parameters under which these diversion scenarios would be detected. This analysis for figure of merit methodology will include statistical fluctuations, operator error, and a rudimentary analysis of transient conditions. The long term goal of the project includes expansion universally over the plant, methods of detection without requiring access to proprietary information, and an evaluation of the requirements for future figure of merit methodologies.

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

    SciTech Connect (OSTI)

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

    2009-07-12T23:59:59.000Z

    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

  9. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    supplies, dry cooling systi Energy Research and Development Division FINAL PROJECT REPORT INLET AIR SPRAY COOLINGUse Energy Efficiency · Renewable Energy Technologies · Transportation Inlet Air Spray Cooling

  10. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    Energy Research and Development Division FINAL PROJECT REPORT INTEGRATING BIOENERGETICS, SPACIAL · Transportation Integrating Bioenergetics, Spatial Scales, and Population Dynamics for Environmental Flow

  11. Training in Environmental Analyses for Safeguards

    SciTech Connect (OSTI)

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

    2009-05-28T23:59:59.000Z

    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.

  12. SAFEGUARDS ENVELOPE: PREVIOUS WORK AND EXAMPLES

    SciTech Connect (OSTI)

    Richard Metcalf; Aaron Bevill; William Charlton; Robert Bean

    2008-07-01T23:59:59.000Z

    The future expansion of nuclear power will require not just electricity production but fuel cycle facilities such as fuel fabrication and reprocessing plants. As large reprocessing facilities are built in various states, they must be built and operated in a manner to minimize the risk of nuclear proliferation. Process monitoring has returned to the spotlight as an added measure that can increase confidence in the safeguards of special nuclear material (SNM). Process monitoring can be demonstrated to lengthen the allowable inventory period by reducing accountancy requirements, and to reduce the false positive indications. The next logical step is the creation of a Safeguards Envelope, a set of operational parameters and models to maximize anomaly detection and inventory period by process monitoring while minimizing operator impact and false positive rates. A brief example of a rudimentary Safeguards Envelope is presented, and shown to detect synthetic diversions overlaying a measured processing plant data set. This demonstration Safeguards Envelope is shown to increase the confidence that no SNM has been diverted with minimal operator impact, even though it is based on an information sparse environment. While the foundation on which a full Safeguards Envelope can be built has been presented in historical demonstrations of process monitoring, several requirements remain yet unfulfilled. Future work will require reprocessing plant transient models, inclusion of “non-traditional” operating data, and exploration of new methods of identifying subtle events in transient processes.

  13. Fundamentals of materials accounting for nuclear safeguards

    SciTech Connect (OSTI)

    Pillay, K.K.S. (comp.)

    1989-04-01T23:59:59.000Z

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

  14. Nuclear Chemistry Division annual report FY83

    SciTech Connect (OSTI)

    Struble, G. (ed.)

    1983-01-01T23:59:59.000Z

    The purpose of the annual reports of the Nuclear Chemistry Division is to provide a timely summary of research activities pursued by members of the Division during the preceding year. Throughout, details are kept to a minimum; readers desiring additional information are encouraged to read the referenced documents or contact the authors. The Introduction presents an overview of the Division's scientific and technical programs. Next is a section of short articles describing recent upgrades of the Division's major facilities, followed by sections highlighting scientific and technical advances. These are grouped under the following sections: nuclear explosives diagnostics; geochemistry and environmental sciences; safeguards technology and radiation effect; and supporting fundamental science. A brief overview introduces each section. Reports on research supported by a particular program are generally grouped together in the same section. The last section lists the scientific, administrative, and technical staff in the Division, along with visitors, consultants, and postdoctoral fellows. It also contains a list of recent publications and presentations. Some contributions to the annual report are classified and only their abstracts are included in this unclassified portion of the report (UCAR-10062-83/1); the full article appears in the classified portion (UCAR-10062-83/2).

  15. Evaluating alternative responses to safeguards alarms

    SciTech Connect (OSTI)

    Al-Ayat, R.A.; Judd, B.R.; McCord, R.K.

    1982-04-15T23:59:59.000Z

    This paper describes a quantitative approach to help evaluate and respond to safeguards alarms. These alarms may be generated internally by a facility's safeguards systems or externally by individuals claiming to have stolen special nuclear material (SNM). This approach can be used to identify the most likely cause of an alarm - theft, hoax, or error - and to evaluate alternative responses to alarms. Possible responses include conducting investigations, initiating measures to recover stolen SNM, and replying to external threats. Based on the results of each alarm investigation step, the evaluation revises the likelihoods of possible causes of an alarm, and uses this information to determine the optimal sequence of further responses. The choice of an optimal sequence of responses takes into consideration the costs and benefits of successful thefts or hoaxes. These results provide an analytical basis for setting priorities and developing contingency plans for responding to safeguards alarms.

  16. Integrated international safeguards concepts for fuel reprocessing

    SciTech Connect (OSTI)

    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.

    1981-12-01T23:59:59.000Z

    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.

  17. Division of Finance Division of Finance Alignment

    E-Print Network [OSTI]

    Hayden, Nancy J.

    Division of Finance Division of Finance Alignment September 11, 2014 1 #12;Division of Finance of Finance Goal of the DF Alignment Project The internal and external alignment of the Division of Finance of Finance The Process We Followed 17 Meetings17 Meetings 120+ Pages of Data 103 Themes 12 Meta Themes Goals

  18. The evolution of information-driven safeguards

    SciTech Connect (OSTI)

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

    2010-10-14T23:59:59.000Z

    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.

  19. Safeguards and Security Program Planning and Management

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

    2005-08-26T23:59:59.000Z

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

  20. Reactor monitoring and safeguards using antineutrino detectors

    E-Print Network [OSTI]

    N. S. Bowden

    2008-09-15T23:59:59.000Z

    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.

  1. Personal views on integrated safeguards and the status of safeguards R&D in the united states.

    SciTech Connect (OSTI)

    Tape, J. W. (James W.)

    2003-01-01T23:59:59.000Z

    Nearly one year ago, the International Atomic Energy Agency (IAEA) completed the conceptual framework for integrated safeguards .' This important document, which was the product of extensive efforts by the Secretariat, the Director General's Standing Advisory Group on Safeguards Implementation (SAGSI), and outside experts over a number of years, provides a basis for discussions of proposed approaches to integrated safeguards . I will refer to this framework paper to share with you my personal views of integrated safeguards .

  2. 1998 Chemical Technology Division Annual Technical Report.

    SciTech Connect (OSTI)

    Ackerman, J.P.; Einziger, R.E.; Gay, E.C.; Green, D.W.; Miller, J.F.

    1999-08-06T23:59:59.000Z

    The Chemical Technology (CMT) Division is a diverse technical organization with principal emphases in environmental management and development of advanced energy sources. The Division conducts research and development in three general areas: (1) development of advanced power sources for stationary and transportation applications and for consumer electronics, (2) management of high-level and low-level nuclear wastes and hazardous wastes, and (3) electrometallurgical treatment of spent nuclear fuel. The Division also performs basic research in catalytic chemistry involving molecular energy resources, mechanisms of ion transport in lithium battery electrolytes, and the chemistry of technology-relevant materials. In addition, the Division operates the Analytical Chemistry Laboratory, which conducts research in analytical chemistry and provides analytical services for programs at Argonne National Laboratory (ANL) and other organizations. Technical highlights of the Division's activities during 1998 are presented.

  3. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    efforts are focused on securing stable and economical storage, transportation, and delivery of natural gas-Use Energy Efficiency · Renewable Energy Technologies · Transportation California Natural Gas StorageEnergy Research and Development Division FINAL PROJECT REPORT CALIFORNIA NATURAL GAS STORAGE

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

    SciTech Connect (OSTI)

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

    1998-08-01T23:59:59.000Z

    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.

  5. Advanced Safeguards Approaches for New Fast Reactors

    SciTech Connect (OSTI)

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

    2007-12-15T23:59:59.000Z

    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.

  6. Evaluating safeguard effectiveness against violent insiders

    SciTech Connect (OSTI)

    Al-Ayat, R.A.; Fortney, D.S.

    1990-07-16T23:59:59.000Z

    The threat posed by a violent insiders presents a major challenge to safeguards managers. These insiders, in addition to their ability to exploit their special authorities, access, and knowledge of facility operations and safeguards, could use violence to defeat safeguards components and personnel. In protecting against theft of special nuclear material, facilities have emphasized the use of perimeter protection and physical barriers to protect against attacks by an outsider adversary group. Recently emphasis has begun to shift toward the implementation of hardware and procedural measures to protect against nonviolent insiders. Approaches are also needed to help assess the effectiveness of protection against those insiders who are willing to use violence. In this paper we describe an approach we're developing for dealing with violent insiders. We begin by categorizing insiders according to whether they are active or passive, rational or irrational, and whether they are willing to use force against safeguards components or coworkers. We define characteristics of each category, and describe the extent to which each category is adequately modelled by existing evaluation tools. We also discuss several modelling issues posed by active insiders, including: entry of contraband; reluctance to use violence; neutralization of insiders; and the ability to switch modes of attack between force, stealth, and deceit. 5 refs., 2 figs.

  7. The integration of process monitoring for safeguards.

    SciTech Connect (OSTI)

    Cipiti, Benjamin B.; Zinaman, Owen R.

    2010-09-01T23:59:59.000Z

    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.

  8. IBM Software Solution Brief Safeguarding the cloud

    E-Print Network [OSTI]

    IBM Software Solution Brief Safeguarding the cloud with IBM Security solutions Maintain visibility and control with proven security solutions for public, private and hybrid clouds Highlights Address cloud internal and external users, data, applications and workloads as they move to and from the cloud Regain

  9. International safeguards: Accounting for nuclear materials

    SciTech Connect (OSTI)

    Fishbone, L.G.

    1988-09-28T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2010-04-01T23:59:59.000Z

    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.

  11. Superconducting Magnet Division

    E-Print Network [OSTI]

    Superconducting Magnet Division DOE NP Program Review - July 06 1 Brookhaven Magnet Division - Nuclear Physics Program Support Activities Superconducting Magnet Program RHIC Operations Support Spin Summary Peter Wanderer, DOE review, July 25, 2006 Acting Head, Superconducting Magnet Division #12

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

    SciTech Connect (OSTI)

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

    2011-10-10T23:59:59.000Z

    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 to facility modifications or new designs • Modifications of the design that could mitigate a potential safeguards issue or facilitate a more efficient application of the safeguards approach • Possible innovative ideas for more efficient application of safeguards • The potential for changes in elements of the safeguard approach that may be required by IAEA as a result of facility design features and characteristics • Other potential concerns These issues will then be presented to the IAEA and the state regulator to be resolved in a timely manner, ensuring that the planned safeguards approach is acceptable and compatible with the facility design. The proposed approach should be validated by application to suitable facilities to assess its utility, comprehensiveness, and cost-effectiveness. The approach and example application should also be reviewed by industry to confirm the conclusions reached in the DOE review.

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

    SciTech Connect (OSTI)

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

    1990-11-01T23:59:59.000Z

    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.

  14. International inspection activity impacts upon DOE safeguards requirements

    SciTech Connect (OSTI)

    Zack, N.R. [Los Alamos National Lab., NM (United States). Safeguards Systems Group; Crawford, D.W. [USDOE Office of Safeguards and Security, Washington, DC (United States)

    1995-09-01T23:59:59.000Z

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

  15. Finance Division Employee Status Form Finance Division

    E-Print Network [OSTI]

    Crews, Stephen

    Finance Division Employee Status Form Finance Division CB 1225, 104 Airport Drive Chapel Hill, NC Phone: 919-962-7242 finance.unc.edu Failure to Follow Instructions Below Will Delay Processing Today information in five areas: 1. Division-wide emergency call tree 2. Finance Web site contacts 3. Departmental

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

    SciTech Connect (OSTI)

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

    2010-01-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2010-01-01T23:59:59.000Z

    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.

  18. SRS delayed neutron instruments for safeguards measurements

    SciTech Connect (OSTI)

    Studley, R.V. [Westinghouse SRC, Aiken, SC (United States)

    1993-12-31T23:59:59.000Z

    Six analytical systems measuring delayed neutrons have been used for safeguards measurements at the Savannah River Site (SRS). A predecessor, the 252Cf Activation Analysis Facility installed at the Savannah River Technology Center (formally SR Laboratory) has been used since 1974 to analyze small samples, measuring both delayed neutrons and gammas. The six shufflers, plus one currently being fabricated, were developed, designed and fabricated by the LANL N-1 group. These shufflers have provided safeguards measurements of product (2 each), in-process scrap (2 each plus a conceptual replacement) and process waste (2 each plus one being fabricated). One shuffler for scrap assay was the first shuffler to be installed (1978) in a process. Another (waste) was the first installed in a process capable of assaying barrels. A third (waste) is the first pass-through model and a fourth (product) is the most precise ({+-}.12%) and accurate NDA instrument yet produced.

  19. Point of Contact: Division Director: Alan S. Icenhour, Ph.D.

    E-Print Network [OSTI]

    areas. Leadership Areas: Nuclear Radiation Detection Safeguards Systems Development, Testing Nonproliferation and Safeguards Education Facilities: Radiation Detection Laboratories Safeguards Laboratory

  20. Science and Technology Challenges for International Safeguards

    SciTech Connect (OSTI)

    Mark Schanfein

    2009-07-01T23:59:59.000Z

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

  1. Safeguard Requirements for Fusion Power Plants

    SciTech Connect (OSTI)

    Robert J. Goldston and Alexander Glaser

    2012-08-10T23:59:59.000Z

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

  2. RESEARCH UPDATE Ecology Division

    E-Print Network [OSTI]

    1 RESEARCH UPDATE Ecology Division Biotype has changed its name to Ecotype! Following the re-organisation of Forest Research into five science Divisions and three Support Divisions, the former Woodland Ecology Branches to form the new Ecology Division. We decided to give the divisional newsletter a new name (and

  3. Innovative cement helps DOE safeguard nuclear facilities | Argonne...

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

    Innovative cement helps DOE safeguard nuclear facilities By Jared Sagoff * April 25, 2008 Tweet EmailPrint ARGONNE, Ill. - When Argonne materials scientists Arun Wagh and Dileep...

  4. Safeguards and Security for Program and Project Management

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

    2013-08-15T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Philip Casey Durst; Robert Bean

    2010-07-01T23:59:59.000Z

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

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

    Broader source: Energy.gov [DOE]

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

  7. Safeguards and Security Oversight and Assessments Implementation Guide

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

    2007-12-21T23:59:59.000Z

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

  8. Plutonium finishing plant safeguards and security systems replacement study

    SciTech Connect (OSTI)

    Klear, P.F.; Humphrys, K.L.

    1994-12-01T23:59:59.000Z

    This document provides the preferred alternatives for the replacement of the Safeguards and Security systems located at the Hanford Plutonium Finishing Plant.

  9. FAQS Job Task Analyses - Safeguards and Security General Technical...

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

    Base More Documents & Publications FAQS Qualification Card - Safeguards and Security General Technical Base FAQS Job Task Analyses - General Technical Base FAQS Qualification Card...

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

    SciTech Connect (OSTI)

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

    2009-09-01T23:59:59.000Z

    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. Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the US Department of Energy, quarter ending March 31, 1993

    SciTech Connect (OSTI)

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

    1993-04-01T23:59:59.000Z

    This quarterly report discusses activities in the Safeguards Technology Program (STP) which is a program in LLNL`s Nuclear Chemistry Division that develop advanced, nondestructive-analysis (NDA) technology for measurement of special nuclear materials. The work focuses on R&D relating to x{minus} and gamma-ray spectrometry techniques and to the development of computer codes for interpreting the spectral data obtained by these techniques.

  12. The future of IAEA safeguards: challenges and responses

    SciTech Connect (OSTI)

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

    2011-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Robert Bean; Casey Durst

    2009-10-01T23:59:59.000Z

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

  14. Safeguards and security modeling for electrochemical plants

    SciTech Connect (OSTI)

    Cipiti, B.B.; Duran, F.A.; Mendoza, L.A.; Parks, M.J.; Dominguez, D.; Le, T.D. [Sandia National Laboratories, PO Box 5800 MS 0747, Albuquerque, NM 87185 (United States)

    2013-07-01T23:59:59.000Z

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

  15. Secret Objective Standoff: International Safeguards Educational Exercise

    SciTech Connect (OSTI)

    Okowita, Samantha L [ORNL

    2014-01-01T23:59:59.000Z

    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.

  16. Safeguarding Truck-Shipped Wholesale and Retail Fuels (STSWRF)

    E-Print Network [OSTI]

    Safeguarding Truck-Shipped Wholesale and Retail Fuels (STSWRF) Oak Ridge National Laboratory at the wholesaler/distributor level or below. This presents additional challenges in tracking untaxed fuel after approved ORNL's plan to conduct a Phase II Pilot Test titled Safeguarding Truck-Shipped Wholesale

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

    SciTech Connect (OSTI)

    Mark Schanfein; Shirley Johnson

    2012-02-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Shipley, J.P. (comp.)

    1982-09-01T23:59:59.000Z

    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.

  19. Fuzzy risk analysis for nuclear safeguards

    SciTech Connect (OSTI)

    Zardecki, A.

    1993-01-01T23:59:59.000Z

    Analysis of a safeguards system, based on the notion of fuzzy sets and linguistic variables, concerns such as complexity and inherent imprecision in estimating the possibility of loss or compromise. The automated risk analysis allows the risk to be determined for an entire system based on estimates for lowest level components and the component proportion. In addition, for each component (asset) the most effective combination of protection mechanisms against a given set of threats is determined. A distinction between bar and featured risk is made.

  20. Fuzzy risk analysis for nuclear safeguards

    SciTech Connect (OSTI)

    Zardecki, A.

    1993-05-01T23:59:59.000Z

    Analysis of a safeguards system, based on the notion of fuzzy sets and linguistic variables, concerns such as complexity and inherent imprecision in estimating the possibility of loss or compromise. The automated risk analysis allows the risk to be determined for an entire system based on estimates for lowest level components and the component proportion. In addition, for each component (asset) the most effective combination of protection mechanisms against a given set of threats is determined. A distinction between bar and featured risk is made.

  1. Safeguards and Security Systems | ornl.gov

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton nSafeguards and Security Systems

  2. International Nuclear Safeguards | National Nuclear Security Administration

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes | National NuclearInterlibrary LoanSafeguards | National Nuclear

  3. Technology transfer significance of the International Safeguards Project Office

    SciTech Connect (OSTI)

    Marcuse, W.; Waligura, A.J.

    1988-06-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Mladineo, Stephen V.; Frazar, Sarah L.

    2012-01-31T23:59:59.000Z

    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.

  5. Chemical Engineering Division fuel cycle programs. Quarterly progress report, April-June 1979. [Pyrochemical/dry processing; waste encapsulation in metal; transport in geologic media

    SciTech Connect (OSTI)

    Steindler, M.J.; Ader, M.; Barletta, R.E.

    1980-09-01T23:59:59.000Z

    For pyrochemical and dry processing materials development included exposure to molten metal and salt of Mo-0.5% Ti-0.07% Ti-0.01% C, Mo-30% W, SiC, Si/sub 2/ON/sub 2/, ZrB/sub 2/-SiC, MgAl/sub 2/O/sub 4/, Al/sub 2/O/sub 3/, AlN, HfB/sub 2/, Y/sub 2/O/sub 3/, BeO, Si/sub 3/N/sub 4/, nickel nitrate-infiltrated W, W-coated Mo, and W-metallized alumina-yttria. Work on Th-U salt transport processing included solubility of Th in liquid Cd, defining the Cd-Th and Cd-Mg-Th phase diagrams, ThO/sub 2/ reduction experiments, and electrolysis of CaO in molten salt. Work on pyrochemical processes and associated hardware for coprocessing U and Pu in spent FBR fuels included a second-generation computer model of the transport process, turntable transport process design, work on the U-Cu-Mg system, and U and Pu distribution coefficients between molten salt and metal. Refractory metal vessels are being service-life tested. The chloride volatility processing of Th-based fuel was evaluated for its proliferation resistance, and a preliminary ternary phase diagram for the Zn-U-Pu system was computed. Material characterization and process analysis were conducted on the Exportable Pyrochemical process (Pyro-Civex process). Literature data on oxidation of fissile metals to oxides were reviewed. Work was done on chemical bases for the reprocessing of actinide oxides in molten salts. Flowsheets are being developed for the processing of fuel in molten tin. Work on encapsulation of solidified radioactive waste in metal matrix included studies of leach rate of crystalline waste materials and of the impact resistance of metal-matrix waste forms. In work on the transport properties of nuclear waste in geologic media, adsorption of Sr on oolitic limestone was studied, as well as the migration of Cs in basalt. Fitting of data on the adsorption of iodate by hematite to a mathematical model was attempted.

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

    SciTech Connect (OSTI)

    Not Available

    1987-03-01T23:59:59.000Z

    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. Electrochemically Modulated Separation for Plutonium Safeguards

    SciTech Connect (OSTI)

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

    2013-12-31T23:59:59.000Z

    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.

  8. DESIGN INFORMATION VERIFICATION FOR NUCLEAR SAFEGUARDS

    SciTech Connect (OSTI)

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

    2009-07-01T23:59:59.000Z

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

  9. Division of Agriculture,

    E-Print Network [OSTI]

    Ray, David

    DAFVM Division of Agriculture, Forestry, and Veterinary M e d i c i n e Visit us online at www to the Mississippi State University Division of Agriculture, Forestry, and Veterinary Medicine. Discrimination based-3-14) Mississippi State University's Division of Agriculture, Forestry, and Veterinary Medicine, or DAFVM

  10. DIVISION OF GRADUATE STUDIES

    E-Print Network [OSTI]

    Palffy-Muhoray, Peter

    recipients at the time of their graduation to monitor and project the scientific workforce. Between 1961DIVISION OF GRADUATE STUDIES 2012-2013 ACADEMIC YEAR REpORT Excellence in Action Division of Graduate Studies #12;Division of Graduate Studies Kent State University 2012 - 2013 Academic Year Report

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

    SciTech Connect (OSTI)

    Long, Jon D. [Y-12 National Security Complex] [Y-12 National Security Complex; McGinnis, Brent R [ORNL] [ORNL; Morgan, James B [ORNL] [ORNL; Whitaker, Michael [ORNL] [ORNL; Lockwood, Mr. Dunbar [U.S. Department of Energy, NNSA] [U.S. Department of Energy, NNSA; Shipwash, Jacqueline L [ORNL] [ORNL

    2011-01-01T23:59:59.000Z

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

  12. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    Energy Research and Development Division FINAL PROJECT REPORT SAIC SOLAR DISHUse Energy Efficiency · Energy Innovations Small Grants · EnergyRelated Environmental Research · EnergyUse Energy Efficiency · Renewable Energy Technologies · Transportation Solar Dish Concentrator

  13. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    Energy Research and Development Division FINAL PROJECT REPORT HYBRID SOLAR LIGHTINGUse Energy Efficiency · Energy Innovations Small Grants · EnergyRelated Environmental Research · EnergyUse Energy Efficiency · Renewable Energy Technologies · Transportation Hybrid Solar Lighting

  14. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    ENERGY BALANCE UPDATE AND DECOMPOSITION ANALYSIS FOR THE INDUSTRY AND BUILDING SECTORS APRIL 2013 · Transportation California Energy Balance Update and Decomposition Analysis for the Industry and Building Energy Research and Development Division FINAL PROJECT REPORT CALIFORNIA

  15. Energy Research and Development Division DRAFT PROJECT REPORT

    E-Print Network [OSTI]

    Use Energy Efficiency · Renewable Energy Technologies · Transportation Natural Gas Energy Efficiency Energy Research and Development Division DRAFT PROJECT REPORT NATURAL GAS ENERGY EFFICIENCY in Buildings ­ Roadmap for Future Research is the final report for the Buildings Natural Gas Roadmap

  16. Chemical Technology Division annual technical report, 1996

    SciTech Connect (OSTI)

    NONE

    1997-06-01T23:59:59.000Z

    CMT is a diverse technical organization with principal emphases in environmental management and development of advanced energy sources. It conducts R&D in 3 general areas: development of advanced power sources for stationary and transportation applications and for consumer electronics, management of high-level and low-level nuclear wastes and hazardous wastes, and electrometallurgical treatment of spent nuclear fuel. The Division also performs basic research in catalytic chemistry involving molecular energy resources, mechanisms of ion transport in lithium battery electrolytes, materials chemistry of electrified interfaces and molecular sieves, and the theory of materials properties. It also operates the Analytical Chemistry Laboratory, which conducts research in analytical chemistry and provides analytical services for programs at ANL and other organizations. Technical highlights of the Division`s activities during 1996 are presented.

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

    SciTech Connect (OSTI)

    Smith, D.B. (comp.)

    1986-01-01T23:59:59.000Z

    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.

  18. Safeguards Evaluation Method for evaluating vulnerability to insider threats

    SciTech Connect (OSTI)

    Al-Ayat, R.A.; Judd, B.R.; Renis, T.A.

    1986-01-01T23:59:59.000Z

    As protection of DOE facilities against outsiders increases to acceptable levels, attention is shifting toward achieving comparable protection against insiders. Since threats and protection measures for insiders are substantially different from those for outsiders, new perspectives and approaches are needed. One such approach is the Safeguards Evaluation Method. This method helps in assessing safeguards vulnerabilities to theft or diversion of special nuclear meterial (SNM) by insiders. The Safeguards Evaluation Method-Insider Threat is a simple model that can be used by safeguards and security planners to evaluate safeguards and proposed upgrades at their own facilities. The method is used to evaluate the effectiveness of safeguards in both timely detection (in time to prevent theft) and late detection (after-the-fact). The method considers the various types of potential insider adversaries working alone or in collusion with other insiders. The approach can be used for a wide variety of facilities with various quantities and forms of SNM. An Evaluation Workbook provides documentation of the baseline assessment; this simplifies subsequent on-site appraisals. Quantitative evaluation is facilitated by an accompanying computer program. The method significantly increases an evaluation team's on-site analytical capabilities, thereby producing a more thorough and accurate safeguards evaluation.

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

    SciTech Connect (OSTI)

    Smith, D.B. (comp.)

    1984-09-01T23:59:59.000Z

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

  20. Safeguards Approaches for Black Box Processes or Facilities

    SciTech Connect (OSTI)

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

    2013-09-25T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Ehinger, M.H.

    1989-01-01T23:59:59.000Z

    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.

  2. Panel on protection and management of plutonium: Subpanel on safeguards and security

    SciTech Connect (OSTI)

    Tape, J.W.

    1995-07-01T23:59:59.000Z

    Nuclear materials safeguards and security systems are described in the context of the nuclear nonproliferation regime. Materials of interest to safeguards, threats, proposals to strengthen International Atomic Energy Agency safeguards, evolving safeguards issues and requirements, system effectiveness, and elements of a global nuclear materials management regime are discussed. Safeguards are seen as an essential element of nuclear materials management, but not a driver for decisions regarding nuclear power or the disposal of excess weapon nuclear materials.

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

    SciTech Connect (OSTI)

    Pepper S. E.

    2014-10-10T23:59:59.000Z

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

  4. Environmental monitoring for nuclear safeguards. Background paper

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    To assure that states are not violating their Non-Proliferation Treaty commitments, the International Atomic Energy Agency (IAEA) must verify that states do not possess convert nuclear facilities-a mission that prior to the 1991 Gulf War, it had neither the political backing nor the resources to conduct. The IAEA recognizes the importance of this new mission and is in the process of assuming it. One of the tools it is exploring to provide some indication of the presence of secret, or undeclared, nuclear activities and facilities is environmental monitoring. Modern sampling and analysis technologies provide powerful tools to detect the presence of characteristic substances that are likely to be emitted by such illicit activities. This background paper examines the prospects for such technologies to improve nuclear safeguards. It concludes that environmental monitoring can greatly increase the ability to detect undeclared activity at declared, or known, sites, and it can significantly increase the chances of detecting and locating undeclared sites.

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

    SciTech Connect (OSTI)

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

    2008-10-17T23:59:59.000Z

    Key component of the Next Generation Safeguards Initiative (NGSI) launched by the National Nuclear Security Administration is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. Two pilot programs at university level, involving 44 students, were initiated and implemented in spring-summer 2008 and linked to hands-on internships at LANL or LLNL. During the internships, students worked on specific safeguards-related projects with a designated Laboratory Mentor to provide broader exposure to nuclear materials management and information analytical techniques. The Safeguards and Nuclear Material Management pilot program was a collaboration between the Texas A&M University (TAMU), Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). It included a 16-lecture course held during a summer internship program. The instructors for the course were from LANL together with TAMU faculty and LLNL experts. The LANL-based course was shared with the students spending their internship at LLNL via video conference. A week-long table-top (or hands-on) exercise on was also conducted at LANL. The student population was a mix of 28 students from a 12 universities participating in a variety of summer internship programs held at LANL and LLNL. A large portion of the students were TAMU students participating in the NGSI pilot. The International Nuclear Safeguards Policy and Information Analysis pilot program was implemented at the Monterey Institute for International Studies (MIIS) in cooperation with LLNL. It included a two-week intensive course consisting of 20 lectures and two exercises. MIIS, LLNL, and speakers from other U.S. national laboratories (LANL, BNL) delivered lectures for the audience of 16 students. The majority of students were senior classmen or new master's degree graduates from MIIS specializing in nonproliferation policy studies. Other university/organizations represented: University of California in LA, Stanford University, and the IAEA. Four of the students that completed this intensive course participated in a 2-month internship at LLNL. The conclusions of the two pilot courses and internships was a NGSI Summer Student Symposium, held at LLNL, where 20 students participated in LLNL facility tours and poster sessions. The Poster sessions were designed to provide a forum for sharing the results of their summer projects and providing experience in presenting their work to a varied audience of students, faculty and laboratory staff. The success of bringing together the students from the technical and policy pilots was notable and will factor into the planning for the continued refinement of their two pilot efforts in the coming years.

  6. Hazardous Material Transportation Safety (South Dakota)

    Broader source: Energy.gov [DOE]

    This legislation authorizes the Division of Highway Safety, in the Department of Public Safety, to promulgate regulations pertaining to the safe transportation of hazardous materials by a motor...

  7. Safeguards for Uranium Extraction (UREX) +1a Process

    E-Print Network [OSTI]

    Feener, Jessica S.

    2011-08-08T23:59:59.000Z

    of nuclear material accountancy (MA), containment and surveillance (C/S) and solution monitoring (SM). Facility information was developed for a hypothesized UREX+1a plant with a throughput of 1000 Metric Tons Heavy Metal (MTHM) per year. Safeguard goals...

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

    SciTech Connect (OSTI)

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

    1995-12-01T23:59:59.000Z

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

  9. advanced safeguards approaches: Topics by E-print Network

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

    to the international community as a possible means to shorten that state?s nuclear latency. If a safeguards approach could be developed for a fuel cycle featuring one of...

  10. Development of Pattern Recognition Options for Combining Safeguards Subsystems

    SciTech Connect (OSTI)

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

    2012-08-24T23:59:59.000Z

    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).

  11. Energy Division progress report, fiscal years 1994--1995

    SciTech Connect (OSTI)

    Moser, C.I. [ed.

    1996-06-01T23:59:59.000Z

    At ORNL, the Energy Division`s mission is to provide innovative solutions to energy and related issues of national and global importance through interdisciplinary research and development. Its goals and accomplishments are described in this progress report for FY 1994 and FY 1995. The Division`s expenditures in FY 1995 totaled 44.9 million. Sixty percent of the divisions work was supported by the US DOE. Other significant sponsors include the US DOT, the US DOD, other federal agencies, and some private organizations. The Division`s programmatic activities cover three main areas: (1) analysis and assessment, (2) transportation systems, and (3) energy use and delivery technologies. Analysis and assessment activities involve energy and resource analysis, preparation of environmental assessments and impact statements, and impact statements, research on emergency preparedness, analysis of energy and environmental needs in developing countries, and transportation analysis. Transportation systems research seeks to improve the quality of both civilian and military transportation efforts. Energy use and delivery technologies focus on building equipment, building envelopes, (walls, roofs, attics, and materials), improvement of energy efficiency in buildings, and electric power systems.

  12. Influence of safeguards and fire protection on criticality safety

    SciTech Connect (OSTI)

    Six, D E

    1980-01-01T23:59:59.000Z

    There are several positive influences of safeguards and fire protection on criticality safety. Experts in each discipline must be aware of regulations and requirements of the others and work together to ensure a fault-tree design. EG and G Idaho, Inc., routinely uses an Occupancy-Use Readiness Manual to consider all aspects of criticality safety, fire protection, and safeguards. The use of the analytical tree is described.

  13. Energy Technology Division research summary - 1999.

    SciTech Connect (OSTI)

    NONE

    1999-03-31T23:59:59.000Z

    The Energy Technology Division provides materials and engineering technology support to a wide range of programs important to the US Department of Energy. As shown on the preceding page, the Division is organized into ten sections, five with concentrations in the materials area and five in engineering technology. Materials expertise includes fabrication, mechanical properties, corrosion, friction and lubrication, and irradiation effects. Our major engineering strengths are in heat and mass flow, sensors and instrumentation, nondestructive testing, transportation, and electromechanics and superconductivity applications. The Division Safety Coordinator, Environmental Compliance Officers, Quality Assurance Representative, Financial Administrator, and Communication Coordinator report directly to the Division Director. The Division Director is personally responsible for cultural diversity and is a member of the Laboratory-wide Cultural Diversity Advisory Committee. The Division's capabilities are generally applied to issues associated with energy production, transportation, utilization, or conservation, or with environmental issues linked to energy. As shown in the organization chart on the next page, the Division reports administratively to the Associate Laboratory Director (ALD) for Energy and Environmental Science and Technology (EEST) through the General Manager for Environmental and Industrial Technologies. While most of our programs are under the purview of the EEST ALD, we also have had programs funded under every one of the ALDs. Some of our research in superconductivity is funded through the Physical Research Program ALD. We also continue to work on a number of nuclear-energy-related programs under the ALD for Engineering Research. Detailed descriptions of our programs on a section-by-section basis are provided in the remainder of this book.

  14. Argonne Physics Division - ATLAS

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

    ATLAS Operations personnel, and to various experimental instrument specialists in the Physics Division. The PAC members will review each proposal for scientific merit and...

  15. Integrated Safeguards and Security Management Self-Assessment 2004

    SciTech Connect (OSTI)

    Lunford, Dan; Ramsey, Dwayne

    2005-04-01T23:59:59.000Z

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

  16. Termination of Safeguards on ULWBR Material

    SciTech Connect (OSTI)

    Ivan R. Thomas; Ernest L. Laible

    2008-07-01T23:59:59.000Z

    The Department of Energy (DOE), Office of Environmental Management, has approved the disposition of 31 metric tons of Unirradiated Light Water Breeder Reactor (ULWBR) material in canisters stored within dry wells of the Underground Fuel Storage Facility at the Idaho Nuclear Technology and Engineering Center (INTEC). This unirradiated material consists primarily of ceramic pellets of thorium oxide in stainless steel cladding, but it also contains 300 kilograms of uranium that is 98 wt% U-233. The ULWBR material was not processed at the INTEC because it was incompatible with prior chemical separation schemes. Other economical recovery options have not been identified, and expressions of interest for consolidating the material with existing projects at other DOE sites have not been received. The U-233 could be used for producing the medical isotope Actinium-225, but the proof-of-principle demonstration and follow-on pilot program have not been developed to the point of requiring production quantities of U-233. Consequently, the selected disposition of the ULWBR material was burial as Low Level Waste at the Nevada Test Site (NTS), which required terminating safeguards controls for the contained Category II quantity of Attractiveness Level D special nuclear material (SNM). The requested termination followed the twelve point evaluation criteria of the Historical Defense Program Discard Guidance and included a security analysis for evaluating the risks of theft, diversion, and radiological sabotage associated with the material. Continuity of knowledge in the book inventory was assured by documenting that the original shipper’s measurements accurately reflected the quantities of materials received and that the ULWBR materials had remained under adequate physical protection and had been subject to periodic physical inventories. The method selected for substantiating the book values as the basis for terminating safeguards was the nondestructive assay used during physical inventories. Shipping arrangements included refurbishing a licensed cask to be reused over the duration of the termination process. An accompanying batching plan and shipping schedule were developed to accommodate multiple commercial shipments of Category III quantities of SNM in the selected cask, such that all canisters would be received at NTS prior to the expiration of the nonrenewable cask license.

  17. Consequence Management, Safeguards & Non-Proliferation Tools...

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

    capabilities for DTRA operational modeling applications, and refining and using the hybrid transport capability to analyze a wide range of neutron and gamma detection...

  18. Superconducting Magnet Division

    E-Print Network [OSTI]

    Gupta, Ramesh

    Superconducting Magnet Division Permanent Magnet Designs with Large Variations in Field Strength the residual field of the magnetized bricks by concentrating flux lines at the iron pole. Low Field Design Medium Field Design Superconducting Magnet Division Dipole and Quadrupole Magnets for RHIC e

  19. Hypertension Research Division

    E-Print Network [OSTI]

    Berdichevsky, Victor

    Hypertension & Vascular Research Division Department of Internal Medicine Jeffrey L. Garvin, Ph.D. ­ Division Head #12;Prevalence of Hypertension in U.S. Men by Age and Ethnicity 18 ­ 29 30 ­ 39 40 ­ 49 50 Prevalence of High BP Adapted from Burt et al. Hypertension 1995;25:305. 25 50 75 #12;Introduction

  20. Superconducting Magnet Division

    E-Print Network [OSTI]

    McDonald, Kirk

    Superconducting Magnet Division Ramesh Gupta 20T Target Solenoid with HTS Insert Solenoid Capture Laboratory New York, USA http://www.bnl.gov/magnets/staff/gupta #12;Superconducting Magnet Division Ramesh of HTS may significantly reduce the amount of Tungsten shielding · Summary #12;Superconducting Magnet

  1. SAFEGUARDS AND SECURITY INTEGRATION WITH SAFETY ANALYSIS

    SciTech Connect (OSTI)

    Hearn, J; James Lightner, J

    2007-04-13T23:59:59.000Z

    The objective of this paper is to share the Savannah River Site lessons learned on Safeguards and Security (S&S) program integration with K-Area Complex (KAC) safety basis. The KAC Documented Safety Analysis (DSA), is managed by the Washington Savannah River Company (WSRC), and the S&S program, managed by Wackenhut Services, Incorporated--Savannah River Site (WSI-SRS). WSRC and WSI-SRS developed a contractual arrangement to recognize WSI-SRS requirements in the KAC safety analysis. Design Basis Threat 2003 (DBT03) security upgrades required physical modifications and operational changes which included the availability of weapons which could potentially impact the facility safety analysis. The KAC DSA did not previously require explicit linkage to the S&S program to satisfy the safety analysis. WSI-SRS have contractual requirements with the Department of Energy (DOE) which are separate from WSRC contract requirements. The lessons learned will include a discussion on planning, analysis, approval of the controls and implementation issues.

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

    SciTech Connect (OSTI)

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

    2010-02-01T23:59:59.000Z

    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.

  3. PHYSICS DIVISION CHEMICAL HYGIENE PLAN

    E-Print Network [OSTI]

    Kemner, Ken

    PHYSICS DIVISION CHEMICAL HYGIENE PLAN 2008 Prepared by _________________________________________________ T. Mullen Physics Division Chemical Hygiene Officer Reviewed by ___________________________________________________ J. Woodring Site Chemical Hygiene Officer Approved

  4. ORNL Energy and Transportation Science Division

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin of Contamination in ManyDepartment of Order No.of Energy OPCOPSAID|65: LNGOREMofORNL

  5. Energy and Transportation Science Division (ETSD)

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisitingContractElectron-StateEnergyHeavyDepartment of Energy

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

    SciTech Connect (OSTI)

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

    2009-04-01T23:59:59.000Z

    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.

  7. Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities

    SciTech Connect (OSTI)

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

    2007-12-15T23:59:59.000Z

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

  8. Task team approach to safeguards and security designs

    SciTech Connect (OSTI)

    Zack, N.R. (Los Alamos National Lab., NM (United States)); Wilkey, D.D. (USDOE Idaho Operations Office, Idaho Falls, ID (United States))

    1991-01-01T23:59:59.000Z

    In 1987, a US Department of Energy (DOE) supported task team was organized at the request of the DOE Idaho Field Office (DOE-ID) to provide support for safeguards and security (S S) designs of the Special Isotope Separation (SIS) facility. Prior to deferral of the project, the SIS facility was to be constructed at the Idaho National Engineering Laboratory (INEL) to produce weapons grade plutonium from DOE owned fuel grade plutonium. The task team was assembled to provide the resources necessary to assure that safeguards and security considerations were included as an integral part of the design of the facility, and that SIS designs would take advantage of available technology in the areas of physical security, measurements, accountability, and material and personnel tracking. The task team included personnel from DOE/Office of Safeguards and Security (DOE-OSS), DOE-ID, DOE contractors, and the national laboratories providing a wide range of expertise and experience. The team reviewed proposed designs and provided recommendations for safeguards and security features in each stage of the design process. The value of this approach to safeguards and security designs will be discussed with respect to benefits, lessons learned, and recommendations for future applications. 5 refs.

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

    SciTech Connect (OSTI)

    Johnson, Shirley J.; Ehinger, Michael

    2010-08-07T23:59:59.000Z

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

  10. Energy Technology Division research summary -- 1994

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    Research funded primarily by the NRC is directed toward assessing the roles of cyclic fatigue, intergranular stress corrosion cracking, and irradiation-assisted stress corrosion cracking on failures in light water reactor (LWR) piping systems, pressure vessels, and various core components. In support of the fast reactor program, the Division has responsibility for fuel-performance modeling and irradiation testing. The Division has major responsibilities in several design areas of the proposed International Thermonuclear Experimental Reactor (ITER). The Division supports the DOE in ensuring safe shipment of nuclear materials by providing extensive review of the Safety Analysis Reports for Packaging (SARPs). Finally, in the nuclear area they are investigating the safe disposal of spent fuel and waste. In work funded by DOE`s Energy Efficiency and Renewable Energy, the high-temperature superconductivity program continues to be a major focal point for industrial interactions. Coatings and lubricants developed in the division`s Tribology Section are intended for use in transportation systems of the future. Continuous fiber ceramic composites are being developed for high-performance heat engines. Nondestructive testing techniques are being developed to evaluate fiber distribution and to detect flaws. A wide variety of coatings for corrosion protection of metal alloys are being studied. These can increase lifetimes significant in a wide variety of coal combustion and gasification environments.

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

    SciTech Connect (OSTI)

    Curtis, Michael M.

    2007-07-31T23:59:59.000Z

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

  12. Export Controls and International Safeguards: Strengthening Nonproliferation through Interdisciplinary Integration

    SciTech Connect (OSTI)

    Peterson, Danielle J.; Goorevich, Richard; Hooper, Rich; Scheinman, Lawrence; Tape, James W.

    2008-11-03T23:59:59.000Z

    International safeguards and export controls are central to ensuring international confidence in the peaceful uses of nuclear materials and technologies and to achieving adequate oversight on the transfer and use of nuclear materials, technology, and equipment required for the development of proliferation-sensitive parts of the nuclear fuel cycle. Although the independent strengths of international safeguards and export controls rely largely on universal adherence, there may be opportunities to exploit the shared strengths of these systems. This article provides background information on the separate evolution of export controls and international safeguards, considers how these two elements of the nonproliferation regime interact, and identifies some possible avenues that could, over time, lead to wholly integrated activities.

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

    SciTech Connect (OSTI)

    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)

    1994-07-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Not Available

    1980-12-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Duran, Felicia Angelica; Cipiti, Benjamin B.

    2009-10-01T23:59:59.000Z

    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.

  16. EA-1640: Final Environmental Assessment and Finding of No Significant...

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

    Telecommunications Buildings, K-1070-CD Burial Ground, K-806 and K-814 McKinney Ridge Radio Repeater Stations, and the Transportation Safeguards Division Facility (a National...

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

    SciTech Connect (OSTI)

    Dreicer, M; Anzelon, G A; Essner, J T; Dougan, A D; Doyle, J; Boyer, B; Hypes, P; Sokava, E; Wehling, F; Martin, J; Charlton, W

    2009-06-16T23:59:59.000Z

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

  18. A perspective on safeguarding and monitoring of excess military plutonium

    SciTech Connect (OSTI)

    Sutcliffe, W.G.

    1994-10-02T23:59:59.000Z

    The purpose of this paper is to provide a perspective and framework for the development of safeguarding and monitoring procedures for the various stages of disposition of excess military plutonium. The paper briefly outlines and comments on some of the issues involved in safeguarding and monitoring excess military plutonium as it progresses from weapons through dismantlement, to fabrication as reactor fuel, to use in a reactor, and finally to storage and disposal as spent fuel. {open_quotes}Military{close_quotes} refers to ownership, and includes both reactor-grade and weapon-grade plutonium. {open_quotes}Excess{close_quotes} refers to plutonium (in any form) that a government decides is no longer needed for military use and can be irrevocably removed from military stockpiles. Many of the issues and proposals presented in this paper are based on, or are similar to, those mentioned in the National Academy of Sciences (NAS) report on excess military plutonium. Safeguards for plutonium disposition are discussed elsewhere in terms of requirements established by the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission (NRC), and the International Atomic Energy Agency (IAEA). Here, the discussion is less specific. The term {open_quotes}safeguarding{close_quotes} is used broadly to refer to materials control and accountancy (MC&A), containment and surveillance (C&S), and physical protection of nuclear materials by the state that possesses those materials. This is also referred to as material protection, control, and accountancy (MPCA). The term {open_quotes}safeguarding{close_quotes} was chosen for brevity and to distinguish MPCA considered in this paper from international or IAEA safeguards. {open_quotes}Monitoring{close_quotes} is used to refer to activities designed to assure another party (state or international organization) that the nuclear materials of the host state (the United States or Russia) are secure and not subject to unauthorized use.

  19. Argonne Physics Division - ATLAS

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

    call 911 on the internal phones (or 252-1911 on cell phones) Safety Tom Mullen, Physics Division Safety Engineer. Please Note: If you have any comments or concerns regarding...

  20. Director, Division of Investigations

    Broader source: Energy.gov [DOE]

    The Federal Energy Regulatory Commission is looking for an experienced, highly skilled executive to serve as Director of the Division of Investigations (DOI) in the Office of Enforcement (OE). The...

  1. Division Student Liaisons

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

    None Fire Protection (FP-DO) Robert J. Farris (Rob) 667-9045 sirraf@lanl.gov K493 Nuclear Criticality Safety None Operations Support Division (OS-DO) None Radiological...

  2. Guidance Systems Division ,

    Office of Legacy Management (LM)

    Oockec No. 10-0772 22 OCT 1981 Bcndlx CorporaLion ' Guidance Systems Division , ATTN: Mr. Wf 11 la,,, Hnrr,,or Manngar, PlanL Englne0rtny Teterboro, New Jersey 07608 uwm STATES...

  3. Application of the sources code in nuclear safeguards

    SciTech Connect (OSTI)

    Beddingfield, D. H. (David H.)

    2002-01-01T23:59:59.000Z

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

  4. Energy Technology Division research summary 1997.

    SciTech Connect (OSTI)

    NONE

    1997-10-21T23:59:59.000Z

    The Energy Technology Division provides materials and engineering technology support to a wide range of programs important to the US Department of Energy. As shown on the preceding page, the Division is organized into ten sections, five with concentrations in the materials area and five in engineering technology. Materials expertise includes fabrication, mechanical properties, corrosion, friction and lubrication, and irradiation effects. Our major engineering strengths are in heat and mass flow, sensors and instrumentation, nondestructive testing, transportation, and electromechanics and superconductivity applications. The Division Safety Coordinator, Environmental Compliance Officers, Quality Assurance Representative, Financial Administrator, and Communication Coordinator report directly to the Division Director. The Division Director is personally responsible for cultural diversity and is a member of the Laboratory-wide Cultural Diversity Advisory Committee. The Division's capabilities are generally applied to issues associated with energy production, transportation, utilization or conservation, or with environmental issues linked to energy. As shown in the organization chart on the next page, the Division reports administratively to the Associate Laboratory Director (ALD) for Energy and Environmental Science and Technology (EEST) through the General Manager for Environmental and Industrial Technologies. While most of our programs are under the purview of the EEST ALD, we also have had programs funded under every one of the ALDs. Some of our research in superconductivity is funded through the Physical Research Program ALD. We also continue to work on a number of nuclear-energy-related programs under the ALD for Engineering Research. Detailed descriptions of our programs on a section-by-section basis are provided in the remainder of this book. This Overview highlights some major trends. Research related to the operational safety of commercial light water nuclear reactors (LWRS) is funded by the US Nuclear Regulatory Commission (NRC). In addition to our ongoing work on environmentally assisted cracking and steam generator integrity, a major new multiyear program has been initiated to assess the performance of high-burnup fuel during loss-of-coolant accidents. The bulk of the NRC research work is carried out in four ET sections: Corrosion: Mechanics of Materials; Irradiation Performance: and Sensors, Instrumentation, and Nondestructive Evaluation. The Transportation of Hazardous Materials Section is the other main contributor; staff from that Section have worked closely with NRC staff to draft a new version of the NRC Standard Review Plan that will be used to provide guidance to NRC reviewers of applications for the renewal of nuclear plant licenses.

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

    SciTech Connect (OSTI)

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

    2009-02-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Hase, Kevin R. [Los Alamos National Laboratory; Hawkins Erpenbeck, Heather [Los Alamos National Laboratory; Boyer, Brian D. [Los Alamos National Laboratory

    2012-07-10T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Nock,C.; Hoffheins,B.

    2008-07-13T23:59:59.000Z

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

  8. The US Support program to IAEA Safeguards - 2008

    SciTech Connect (OSTI)

    Pepper,S.

    2008-06-09T23:59:59.000Z

    The U.S. Support Program to IAEA Safeguards (USSP) was established in 1977 to provide technical assistance to the IAEA Department of Safeguards. Since that time the U.S. Department of State has provided funding of over $200 million and over 900 tasks have been completed by USSP contractors on behalf of the KEA. The USSP is directed by a U.S. interagency subcommittee known as the Subgroup on Safeguards Technical Support (SSTS) and is managed by the International Safeguards Project Office (ISPO) at Brookhaven National Laboratory. In recent years, the SSTS and ISPO have identified priorities to guide the process of determining which IAEA requests are aligned with US. policy and will be funded. The USSP priorities are reviewed and updated prior to the USSP Annual Review Meeting which is hosted by the International Atomic Energy Agency (IAEA) each spring in Vienna, Austria. This paper will report on the 2008 USSP priorities and be an introduction for a session which will consist of four papers on USSP priorities and four other papers related to USSP activities.

  9. advanced safeguards technology: Topics by E-print Network

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

    advanced safeguards technology First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 February 2000 Advanced...

  10. Evaluation of three new technolgies for international safeguards

    SciTech Connect (OSTI)

    Stanbro, W.D.; Rodriguez, C.A.; Olinger, C.T.; Cremers, T.L.

    1993-01-01T23:59:59.000Z

    Los Alamos National Laboratory is examining a number of promising technologies that could increase the effectiveness and efficiency of international nuclear safeguards. The techniques described in this paper include video image processing, infrared imaging, and acoustic resonance spectroscopy. Each of these techniques offers unique advantages in the implementation of an inspection regime.

  11. Nuclear fission and nuclear safeguards: Common technologies and challenges

    SciTech Connect (OSTI)

    Keepin, G.R.

    1989-01-01T23:59:59.000Z

    Nuclear fission and nuclear safeguards have much in common, including the basic physical phenomena and technologies involved as well as the commitments and challenges posed by expanding nuclear programs in many countries around the world. The unique characteristics of the fission process -- such as prompt and delayed neutron and gamma ray emission -- not only provide the means of sustaining and controlling the fission chain reaction, but also provide unique ''signatures'' that are essential to quantitative measurement and effective safeguarding of key nuclear materials (notably /sup 239/Pu and /sup 235/U) against theft, loss, or diversion. In this paper, we trace briefly the historical emergence of safeguards as an essential component of the expansion of the nuclear enterprise worldwide. We then survey the major categories of passive and active nondestructive assay techniques that are currently in use or under development for rapid, accurate measurement and verification of safe-guarded nuclear materials in the many forms in which they occur throughout the nuclear fuel cycle. 23 refs., 14 figs.

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

    SciTech Connect (OSTI)

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

    1986-02-01T23:59:59.000Z

    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.

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

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

    1998-02-10T23:59:59.000Z

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

  14. Process monitoring in support of International Atomic Energy Agency safeguards

    SciTech Connect (OSTI)

    Ehinger, M.H.; Wachter, J.W.; Hebble, T.L.; Kerr, H.T.

    1987-08-01T23:59:59.000Z

    A review of previous efforts in process monitoring for safeguards was conducted. Previous efforts touched on various concepts and a few specific applications, but none was comprehensive in addressing all aspects of a process monitoring application for safeguards. This report develops prototypical process monitoring concepts that can be incorporated into the International Atomic Energy Agency's (IAEA's) general safeguards approach for fuel reprocessing plants. This effort considers existing approaches, recognizing limitations and needed improvements. Prototypical process monitoring applications are developed and proposed for implementation and demonstration in the Integrated Equipment Test facility, which is located at the Oak Ridge National Laboratory. The specific information needed to accomplish the process monitoring objectives are defined, and the mechanics for obtaining that information are described. Effort is given to the identification and assessment of potential impacts and benefits associated with process monitoring concepts, with particular attention to IAEA, state, and plant operator interests. The historical development of process monitoring is described and the implications of using process monitoring in international safeguards are discussed. Specific process process monitoring applications for demonstration in the IET facility are developed in Sects. 6 through 14. 1 fig.

  15. Safeguards Issues at Nuclear Reactors and Enrichment Plants

    SciTech Connect (OSTI)

    Boyer, Brian D [Los Alamos National Laboratory

    2012-08-15T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Robert Bean

    2010-09-01T23:59:59.000Z

    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.

  17. A Cost Effective, Integrated and Smart Radioactive Safeguard System 

    E-Print Network [OSTI]

    Singh, Harneet

    2012-02-14T23:59:59.000Z

    consequences. In order to protect this precious resource and ensure its use for the good of mankind, safeguard systems are more important than ever. Current Market solutions are wide ranged but have a large number of disadvantages, some of which include high...

  18. Progress Towards Deployable Antineutrino Detectors for Reactor Safeguards

    SciTech Connect (OSTI)

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

    2010-04-05T23:59:59.000Z

    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.

  19. Nuclear reactor safeguards and monitoring with antineutrino detectors A. Bernsteina)

    E-Print Network [OSTI]

    Gratta, Giorgio

    Nuclear reactor safeguards and monitoring with antineutrino detectors A. Bernsteina) Sandia of nuclear reactor types, including power reactors, research reactors, and plutonium production reactors-understood principles that govern the core's evolution in time, can be used to determine whether the reactor is being

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

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

    2004-01-07T23:59:59.000Z

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

  1. China in the World Trade Organization: Antidumping and Safeguards

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    China in the World Trade Organization: Antidumping and Safeguards Patrick A. Messerlin China finds of antidumping measures, but (so far) one of the smallest users of such measures. China's World Trade China's recent antidumping enforcement; how China could minimize its exposure to foreign antidumping

  2. Earth Sciences Division annual report 1990

    SciTech Connect (OSTI)

    NONE

    1991-06-01T23:59:59.000Z

    This Annual Report presents summaries of selected representative research activities grouped according to the principal disciplines of the Earth Sciences Division: Reservoir Engineering and Hydrogeology, Geology and Geochemistry, and Geophysics and Geomechanics. Much of the Division`s research deals with the physical and chemical properties and processes in the earth`s crust, from the partially saturated, low-temperature near-surface environment to the high-temperature environments characteristic of regions where magmatic-hydrothermal processes are active. Strengths in laboratory and field instrumentation, numerical modeling, and in situ measurement allow study of the transport of mass and heat through geologic media -- studies that now include the appropriate chemical reactions and the hydraulic-mechanical complexities of fractured rock systems. Of particular note are three major Division efforts addressing problems in the discovery and recovery of petroleum, the application of isotope geochemistry to the study of geodynamic processes and earth history, and the development of borehole methods for high-resolution imaging of the subsurface using seismic and electromagnetic waves. In 1989 a major DOE-wide effort was launched in the areas of Environmental Restoration and Waste Management. Many of the methods previously developed for and applied to deeper regions of the earth will in the coming years be turned toward process definition and characterization of the very shallow subsurface, where man-induced contaminants now intrude and where remedial action is required.

  3. Chemistry Division Department of Biological

    E-Print Network [OSTI]

    Heller, Barbara

    1 Chemistry Division Department of Biological and Chemical Sciences, Illinois Institute-13 Chemistry Division invites nominations for Kilpatrick Fellowship for the academic year 2012's Chemistry Department from 1947­1960. Mary Kilpatrick was a chemistry faculty member from 1947

  4. Superconducting Magnet Division

    E-Print Network [OSTI]

    Ohta, Shigemi

    Superconducting Magnet Division MAGNETIC DESIGN OF E-LENS SOLENOID AND CORRECTOR SYSTEM FOR RHIC* R.6 A gun collectors gun Combined Horizontal and Vertical Corrector Design Both types of dipole correctors. Gupta, M. Anerella, W. Fischer, G. Ganetis, X. Gu, A. Ghosh, A. Jain, P. Kovach, A. Marone, S. Plate, A

  5. Solid State Division

    SciTech Connect (OSTI)

    Green, P.H.; Watson, D.M. (eds.)

    1989-08-01T23:59:59.000Z

    This report contains brief discussions on work done in the Solid State Division of Oak Ridge National Laboratory. The topics covered are: Theoretical Solid State Physics; Neutron scattering; Physical properties of materials; The synthesis and characterization of materials; Ion beam and laser processing; and Structure of solids and surfaces. (LSP)

  6. integration division Human Systems

    E-Print Network [OSTI]

    integration division Human Systems Eye-Movement Metrics: Non-Intrusive Quantitative Tools for Monitoring Human Visual Performance Objective Approach Impact A reliable quantitative yet non-intrusive methodologies that provide quantitative yet non-intrusive measures of human visual performance for use

  7. Security Division 2007 Annual Report

    E-Print Network [OSTI]

    Computer Security Division 2007 Annual Report #12;TAble of ConTenTS Welcome Division Organization The Computer Security Division Responds to the Federal Information Security Management Act of 2002 Security Information Technology 15 Security Testing and Metrics 17 Validation Programs and Laboratory Accreditation 17

  8. Computer, Computational, and Statistical Sciences Division

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

    Computing CCS Division Computer, Computational, and Statistical Sciences Division Computational physics, computer science, applied mathematics, statistics and the integration of...

  9. Using Highly Interactive Virtual Environments for Safeguards Activities

    SciTech Connect (OSTI)

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

    2010-01-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Auerbach, C.

    1985-04-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    David L. Chichester

    2008-04-01T23:59:59.000Z

    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.

  12. Protection and Control of Safeguards and Security Interests

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

    1994-07-15T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    1982-04-01T23:59:59.000Z

    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.

  14. Safeguards and security issues for the disposition of fissile materials

    SciTech Connect (OSTI)

    Jaeger, C.D.; Moya, R.W.; Duggan, R.A.; Mangan, D.L.; Tolk, K.M. [Sandia National Labs., Albuquerque, NM (United States); Rutherford, D.; Fearey, B. [Los Alamos National Lab., NM (United States); Moore, L. [Lawrence Livermore National Lab., CA (United States)

    1995-07-01T23:59:59.000Z

    The Department of Energy`s Office of Fissile Material Disposition (FMD) is analyzing long-term storage and disposition options for surplus weapons-usable fissile materials, preparing a programmatic environmental impact statement (PEIS), preparing for a record of decision (ROD) regarding this material and conducting other activities. The primary security objectives of this program are to reduce major security risks and strengthen arms reduction and nonproliferation (NP). To help achieve these objectives, a safeguards and security (S&S) team consisting of participants from Sandia, Los Alamos, and Lawrence Livermore National Laboratories was established. The S&S activity for this program is a cross-cutting task which addresses all of the FMD program options. It includes both domestic and international safeguards and includes areas such as physical protection, nuclear materials accountability and material containment and surveillance. This paper will discuss the activities of the Fissile Materials Disposition Program (FMDP) S&S team as well as some specific S&S issues associated with various FMDP options/facilities. Some of the items to be discussed include the threat, S&S requirements, S&S criteria for assessing risk, S&S issues concerning fissile material processing/facilities, and international and domestic safeguards.

  15. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    the aircraft off the ground for each mission. i #12;PREFACE The California Energy Commission Energy Research/Agricultural/Water End-Use Energy Efficiency · Renewable Energy Technologies · Transportation California AutonomousEnergy Research and Development Division FINAL PROJECT REPORT CALIFORNIA AUTONOMOUS UNMANNED AERIAL

  16. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    Energy Research and Development Division FINAL PROJECT REPORT TIME OF USE WATER METER IMPACTS · Transportation Time-of-Use Water Meter Impacts on Customer Water Use is the final report for the Time of Use This report was prepared as the result of work sponsored by the California Energy Commission. It does

  17. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    Energy Research and Development Division FINAL PROJECT REPORT RADIANT HEATING AND COOLING AND MEASURED HOME PERFORMANCE FOR CALIFORNIA HOMES JUNE 2013 CEC-500-2013-153 Prepared for: California Energy-Use Energy Efficiency · Renewable Energy Technologies · Transportation Radiant Heating and Cooling

  18. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    Energy Research and Development Division FINAL PROJECT REPORT NATURAL GAS OPTIMIZED ADVANCED HEAVY · Renewable Energy Technologies · Transportation Natural Gas-optimized Advanced Heavy-duty Engine is the final&R 412 88, Gothenburg, Sweden Telephone: +46-31-3220998 Mobile: +46-7390-20998 Contract Number: PIR-08

  19. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    -Use Energy Efficiency · Renewable Energy Technologies · Transportation The Value of Natural Gas StorageEnergy Research and Development Division FINAL PROJECT REPORT THE VALUE OF NATURAL GAS STORAGE AND THE IMPACT OF RENEWABLE GENERATION ON CALIFORNIA'S NATURAL GAS INFRASTRUCTURE DECEMBER 2009 CEC-500

  20. Energy Research and Development Division FINAL PROJECT REPORT

    E-Print Network [OSTI]

    · Renewable Energy Technologies · Transportation Production of Substituted Natural Gas from the Wet Organic Renewable natural gas has been identified by the California Energy Commission as an important alternativeEnergy Research and Development Division FINAL PROJECT REPORT Production of Substituted Natural

  1. Packaging and Transfer or Transportation of Materials of National Security Interest

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

    2000-09-29T23:59:59.000Z

    To establish requirements and responsibilities for the Transportation Safeguards System (TSS) packaging and transportation and onsite transfer of nuclear explosives, nuclear components, Naval nuclear fuel elements, Category I and Category II special nuclear materials, special assemblies, and other materials of national security interest. Cancels: DOE 5610.12 and DOE 5610.14.

  2. Mission | APS Engineering Support Division

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

    APS Engineering Support Division (AES) Search Button About Welcome Overview Visiting the APS Mission & Goals Find People Organization Charts Committees Job Openings User...

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

    SciTech Connect (OSTI)

    Daniel Shy

    2014-08-01T23:59:59.000Z

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

  4. Advanced Process Monitoring Techniques for Safeguarding Reprocessing Facilities

    SciTech Connect (OSTI)

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

    2010-11-30T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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

    2010-04-05T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2009-10-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    1997-03-01T23:59:59.000Z

    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.

  8. Extended Evaluations of the Commercial Spectrometer Systems for Safeguards Applications

    SciTech Connect (OSTI)

    Duc T. Vo

    1999-08-01T23:59:59.000Z

    Safeguards applications require the best of the spectrometer system with excellent resolution, stability, and throughput. Instruments must perform well in all situations and environments. Data communication to the computer should be convenient, fast, and reliable. The software should have all the necessary tools and be easy to use. Portable systems should be small in size, lightweight, and have a long battery life. Nine commercially available spectrometer systems are tested with five different germanium detectors. Considering the performance of the Digital Signal Processors (DSP), digital-based spectroscope y may become the way of future gamma-ray spectroscopy.

  9. Materials management in an internationally safeguarded fuels reprocessing plant

    SciTech Connect (OSTI)

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

    1980-04-01T23:59:59.000Z

    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. NGSI Safeguards by Design | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA groupTubahq.na.govSecurityMaintaining theSan Jose-San|NGSI Safeguards by Design |

  11. Safeguards and Security for Program and Project Management - DOE

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton nSafeguards and Security

  12. Energy Division annual progress report for period ending September 30, 1993

    SciTech Connect (OSTI)

    Wolff, P.P. [ed.

    1994-07-01T23:59:59.000Z

    One of 17 research divisions at Oak Ridge National Laboratory, Energy Division`s mission is to provide innovative solutions to energy and related issues of national and global importance through interdisciplinary research and development. Its goals and accomplishments are described in this annual progress report for FY1993. Energy Division is committed to (1) understanding the mechanisms by which societies make choices in energy use; (2) improving society`s understanding of the environmental, social, and economic implications of technological change; (3) developing and transferring energy-efficient technologies; (4) improving transportation policy and planning; (5) enhancing basic knowledge in the social sciences as related to energy and associated issues. Energy Division`s expenditures in FY1993 totaled $42 million. The work was supported by the US DOE, DOD, many other federal agencies, and some private organizations. Disciplines of the 126.5 technical staff members include engineering, social sciences, physical and life sciences, and computer sciences and data systems. The division`s programmatic activities cover three main areas: (1) analysis and assessment, (2) energy use and delivery technologies, and (3) transportation systems. Analysis and assessment activities involve energy and resource analysis, preparation of environmental assessments and impact statements, research on emergency preparedness, transportation analysis, and analysis of energy and environmental needs in developing countries. Energy use and delivery technologies focus on electric power systems, building equipment, building envelopes (walls, foundations, roofs, attics, and materials), and methods to improve energy efficiency in existing buildings. Transportation systems research is conducted both to improve the quality of civilian transportation and for sponsors within the US military to improve the efficiency of deployment, scheduling, and transportation coordination.

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

    SciTech Connect (OSTI)

    Gilligan, Kimberly [ORNL

    2014-01-01T23:59:59.000Z

    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).1 The executive summary is available at the following link: http://nnsa.energy.gov/sites/default/files/nnsa/inlinefiles/NGSI_Report.pdf.

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

    SciTech Connect (OSTI)

    Kollar, Lenka; Mathews, Caroline E.

    2009-07-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2011-10-05T23:59:59.000Z

    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. Systems Division NO. REV. NO.

    E-Print Network [OSTI]

    Rathbun, Julie A.

    Conditioning Unit (PCU) is compatible with a solar panel array. The Solar Panel Simulator and the PCU Test SetAerospace Systems Division NO. REV. NO. EATM-17 PCU - SOLAR PANEL SIMULATOR TEST REPORT:' Courtois ~ll~K. Hsi #12;MO. REV. MO. EATM-17 ~ Systems Division PCU - Solar Panel Simulator Test Report

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

    SciTech Connect (OSTI)

    Duncan, Cristen L.; Heinberg, Cynthia L.; Killinger, Mark H.; Goodey, Kent O.; Kryuchkov, Eduard F.; Geraskin, Nikolai I.; Silaev, Maxim E.; Sokova, Elena K.; Ford, David G.

    2010-04-20T23:59:59.000Z

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

  18. New Measures to Safeguard Gas Centrifuge Enrichment Plants

    SciTech Connect (OSTI)

    Whitaker, Jr., James [ORNL; Garner, James R [ORNL; Whitaker, Michael [ORNL; Lockwood, Dunbar [U.S. Department of Energy, NNSA; Gilligan, Kimberly V [ORNL; Younkin, James R [ORNL; Hooper, David A [ORNL; Henkel, James J [ORNL; Krichinsky, Alan M [ORNL

    2011-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2011-10-01T23:59:59.000Z

    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.

  20. Application of safeguards technology in DOE's environmental restoration program

    SciTech Connect (OSTI)

    Eccleston, G.W.; Baker, M.P.; Hansen, W.R.; Lucas, M.C.; Markin, J.T.; Phillips, J.R.

    1990-01-01T23:59:59.000Z

    During the last two decades, the Department of Energy's Office of Safeguards and Security (DOE/OSS) has supported the research and development of safeguards systems analysis methodologies and nondestructive assay (NDS) technology for characterizing, monitoring, and accounting nuclear materials. This paper discusses methodologies and NDA instrumentation developed by the DOE/OSS program that could be applied in the Environmental Restoration Program. NDA instrumentation could be used for field measurements during site characterization and to monitor nuclear materials, heavy metals, and other hazardous materials during site remediation. Systems methodologies can minimize the expenditure of resources and help specify appropriate combinations of NDA instrumentation and chemical analyses to characterize a variety of materials quickly and reduce personnel exposure in hazardous environments. A training program is available to teach fundamental and advanced principles and approaches to characterize and quantify nuclear materials properly and to organize and analyze measurement information for decision making. The ability to characterize the overall volume and distribution of materials at a waste site is difficult because of the inhomogeneous distribution of materials, the requirement for extreme sensitivity, and the lack of resources to collect and chemically analyze a sufficient number of samples. Using a systems study approach based on statistical sampling, the resources necessary to characterize a site can be enhanced by appropriately combining in situ and field NDA measurements with laboratory analyses. 35 refs., 1 figs., 2 tabs.

  1. Safeguards and Security Technology Development Directory. FY 1993

    SciTech Connect (OSTI)

    Not Available

    1993-06-01T23:59:59.000Z

    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.

  2. ENERGY & ENVIRONMENT DIVISION ANNUAL REPORT 1979

    E-Print Network [OSTI]

    Cairns, E.J.

    2010-01-01T23:59:59.000Z

    Population Impacts of Geothermal Energy Development in thethe DOE Division of Geothermal Energy. S. L. Phillips and E.to DOE Division of Geothermal Energy, January 30, 1980.

  3. EARTH SCIENCES DIVISION ANNUAL REPORT 1978

    E-Print Network [OSTI]

    Authors, Various

    2012-01-01T23:59:59.000Z

    of Energy's Division of Geothermal Energy has undertaken aand Ghormley, E. L. , 1976. Geothermal energy conversion andof the Division of Geothermal Energy, and is compatible with

  4. Energy Division annual progress report for period ending September 30, 1991

    SciTech Connect (OSTI)

    Stone, J.N. [ed.

    1992-04-01T23:59:59.000Z

    The Energy Division is one of 17 research divisions at Oak Ridge Laboratory. Its goals and accomplishments are described in this annual progress report for FY 1991. The division`s total expenditures in FY 1991 were $39.1 million. The work is supported by the US Department of Energy, US Department of Defense, many other federal agencies, and some private organizations. Disciplines of the 124 technical staff members include engineering, social sciences, physical and life sciences, and mathematics and statistics. The Energy Division`s programmatic activities focus on three major areas: (1) analysis and assessment, (2) energy conservation technologies, and (3) military transportation systems. Analysis and assessment activities cover energy and resource analysis, the preparation of environmental assessments and impact statements, research on waste management, analysis of emergency preparedness for natural and technological disasters, analysis of the energy and environmental needs of developing countries, technology transfer, and analysis of civilian transportation. Energy conservation technologies include electric power systems, building equipment (thermally activated heat pumps, advanced refrigeration systems, novel cycles), building envelopes (walls, foundations, roofs, attics, and materials), and technical issues for improving energy efficiency in existing buildings. Military transportation systems concentrate on research for sponsors within the US military on improving the efficiency of military deployment, scheduling, and transportation coordination.

  5. Developing the Next Generation of International Safeguards and Nonproliferation Experts: Highlights of Select Activities at the National Laboratories

    SciTech Connect (OSTI)

    Reed, J; Mathews, C; Kirk, B; Lynch, P; Doyle, J; Meek, E; Pepper, S; Metcalf, R

    2010-03-31T23:59:59.000Z

    With many safeguards experts in the United States at or near retirement age, and with the growing and evolving mission of international safeguards, attracting and educating a new generation of safeguards experts is an important element of maintaining a credible and capable international safeguards system. The United States National Laboratories, with their rich experience in addressing the technical and policy challenges of international safeguards, are an important resource for attracting, educating, and training future safeguards experts. This presentation highlights some of the safeguards education and professional development activities underway at the National Laboratories. These include university outreach, summer courses, internships, mid-career transition, knowledge retention, and other projects. The presentation concludes with thoughts on the challenge of interdisciplinary education and the recruitment of individuals with the right balance of skills and backgrounds are recruited to meet tomorrow's needs.

  6. Safeguards and Security Research and Development progress report, October 1992--September 1993

    SciTech Connect (OSTI)

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

    1994-10-01T23:59:59.000Z

    This report describes the activities carried out by the Los Alamos Safeguards and Security Research and Development program. Part 1 covers the three project phases that are part of the development of the technology essential to continuing improvements in the practice of safeguards and security. Examples include advanced portal monitor technology, digital image analysis for materials control, neutron multiplicity counting techniques, and development of a tomographic gamma-ray scanner. It 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 2 covers international safeguards activities, including technology developed for direct application in the international community, support to the IAEA, and bilateral technical exchanges with many other States, such as Argentina, Brazil, China, France, Japan, Russia, and the Ukraine. Part 3 highlights a variety of projects, including several in computer security R and D, direct support of the IAEA through the Program of Technical Assistance to IAEA Safeguards, and safeguards projects funded by the US Department of State, the DOE`s Office of Technology Development, the US Nuclear Regulatory Commission, Japan, and Germany. A few examples of these projects are the support to the Westinghouse Hanford Company efforts in data acquisition and control for the hydrogen mitigation tests on high-level-waste Tank 101-SY, nondestructive assay development for Warhead Dismantlement, and instrumentation system development for the Siemans mixed-oxide fuel fabrication plant in Germany. 75 refs.

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

    SciTech Connect (OSTI)

    Michael Holzemer; Alan Carvo

    2012-04-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Queirolo,A.

    2008-06-13T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2009-01-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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

    2009-01-01T23:59:59.000Z

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

  11. Physics division annual report 2006.

    SciTech Connect (OSTI)

    Glover, J.; Physics

    2008-02-28T23:59:59.000Z

    This report highlights the activities of the Physics Division of Argonne National Laboratory in 2006. The Division's programs include the operation as a national user facility of ATLAS, the Argonne Tandem Linear Accelerator System, research in nuclear structure and reactions, nuclear astrophysics, nuclear theory, investigations in medium-energy nuclear physics as well as research and development in accelerator technology. The mission of nuclear physics is to understand the origin, evolution and structure of baryonic matter in the universe--the core of matter, the fuel of stars, and the basic constituent of life itself. The Division's research focuses on innovative new ways to address this mission.

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

    SciTech Connect (OSTI)

    Richard Metcalf; Robert Bean

    2009-10-01T23:59:59.000Z

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

  13. Energy Division annual progress report for period ending September 30, 1990

    SciTech Connect (OSTI)

    Selden, R.H. (ed.)

    1991-06-01T23:59:59.000Z

    The Energy Division is one of 17 research divisions at Oak Ridge National Laboratory. The goals and accomplishments of the Energy Division are described in this annual progress report for FY 1990. The Energy Division is a multidisciplinary research organization committed to (1) increasing the knowledge and understanding of how societies make choices in energy use; (2) improving society's understanding of the environmental, social, and economic implications of technological change; (3) developing and transferring energy efficient technologies; and (4) developing improved transportation planning and policy. Disciplines of the 129 staff members include engineering, social sciences, physical and life sciences, and mathematics and statistics. The Energy Division's programmatic activities focus on three major areas: (1) analysis and assessment, (2) energy conservation technologies, and (3) military transportation systems. Analysis and assessment activities cover energy and resource analysis, the preparation of environmental assessments and impact statements, research on waste management, analysis of emergency preparedness for natural and technological disasters, analysis of the energy and environmental needs of developing countries, technology transfer, and analysis of civilian transportation. Energy conservation technologies include building equipment (thermally activated heat pumps, chemical heat pumps, refrigeration systems, novel cycles), building enveloped (walls, foundations, roofs, attics, and materials), retrofits for existing buildings, and electric power systems. Military transportation systems concentrate on research for sponsors within the US military on improving the efficiency of military deployment, scheduling, and transportation coordination. 48 refs., 34 figs., 7 tabs.

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

    SciTech Connect (OSTI)

    Morgan, James B [ORNL; White-Horton, Jessica L [ORNL

    2012-01-01T23:59:59.000Z

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

  15. The uranium cylinder assay system for enrichment plant safeguards

    SciTech Connect (OSTI)

    Miller, Karen A [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Marlow, Johnna B [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Rael, Carlos D [Los Alamos National Laboratory; Iwamoto, Tomonori [JNFL; Tamura, Takayuki [JNFL; Aiuchi, Syun [JNFL

    2010-01-01T23:59:59.000Z

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

  16. Nuclear Reactor Safeguards and Monitoring with Antineutrino Detectors

    E-Print Network [OSTI]

    Adam Bernstein; Yifang Wang; Giorgio Gratta; Todd West

    2001-08-01T23:59:59.000Z

    Cubic-meter-sized antineutrino detectors can be used to non-intrusively, robustly and automatically monitor and safeguard a wide variety of nuclear reactor types, including power reactors, research reactors, and plutonium production reactors. Since the antineutrino spectra and relative yields of fissioning isotopes depend on the isotopic composition of the core, changes in composition can be observed without ever directly accessing the core itself. Information from a modest-sized antineutrino detector, coupled with the well-understood principles that govern the core's evolution in time, can be used to determine whether the reactor is being operated in an illegitimate way. A group at Sandia is currently constructing a one cubic meter antineutrino detector at the San Onofre reactor site in California to demonstrate these principles.

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

    SciTech Connect (OSTI)

    Pabian, Frank Vincent [Los Alamos National Laboratory

    2010-09-16T23:59:59.000Z

    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.

  18. Physics Division computer facilities

    SciTech Connect (OSTI)

    Cyborski, D.R.; Teh, K.M.

    1995-08-01T23:59:59.000Z

    The Physics Division maintains several computer systems for data analysis, general-purpose computing, and word processing. While the VMS VAX clusters are still used, this past year saw a greater shift to the Unix Cluster with the addition of more RISC-based Unix workstations. The main Divisional VAX cluster which consists of two VAX 3300s configured as a dual-host system serves as boot nodes and disk servers to seven other satellite nodes consisting of two VAXstation 3200s, three VAXstation 3100 machines, a VAX-11/750, and a MicroVAX II. There are three 6250/1600 bpi 9-track tape drives, six 8-mm tapes and about 9.1 GB of disk storage served to the cluster by the various satellites. Also, two of the satellites (the MicroVAX and VAX-11/750) have DAPHNE front-end interfaces for data acquisition. Since the tape drives are accessible cluster-wide via a software package, they are, in addition to replay, used for tape-to-tape copies. There is however, a satellite node outfitted with two 8 mm drives available for this purpose. Although not part of the main cluster, a DEC 3000 Alpha machine obtained for data acquisition is also available for data replay. In one case, users reported a performance increase by a factor of 10 when using this machine.

  19. DIVISION 16 -ELECTRICAL 16000 GENERAL

    E-Print Network [OSTI]

    DIVISION 16 - ELECTRICAL _____________________________________________________________ 16000 GENERAL A. Design Considerations 1. All drawing, specifications and construction shall conform to the following: National Electrical Code National Electrical Safety Code National Fire Protection Association

  20. Division 1137 property control system

    SciTech Connect (OSTI)

    Pastor, D.J.

    1982-01-01T23:59:59.000Z

    An automated data processing property control system was developed by Mobile and Remote Range Division 1137. This report describes the operation of the system and examines ways of using it in operational planning and control.

  1. Lawrence Berkeley National Laboratory Engineering Division Office

    E-Print Network [OSTI]

    /4867399 DMAttia@lbl.gov Administrative Staff Glenda Fish Division Office Administrator 510/4867123 GJFish

  2. Energy Division annual progress report for period ending September 30, 1992

    SciTech Connect (OSTI)

    Counce, D.M.; Wolff, P.P. [eds.

    1993-04-01T23:59:59.000Z

    Energy Division`s mission is to provide innovative solutions to energy and related Issues of national and global importance through interdisciplinary research and development. Its goals and accomplishments are described in this annual progress report for FY 1992. Energy Division`s total expenditures in FY 1992 were $42.8 million. The work is supported by the US Department of Energy, the US Department of Defense, many other federal agencies, and some private organizations. Disciplines of the 116.5 technical staff members include engineering, social sciences, physical and life sciences, and mathematics and statistics. The division`s programmatic activities cover three main areas: (1) analysis and assessment, (2) energy conservation technologies, and (3) military transportation systems. Analysis and assessment activities involve energy and resource analysis, preparation of environmental assessments and impact statements, research on waste management, technology transfer, analysis of energy and environmental needs in developing countries, and civilian transportation analysis. Energy conservation technologies focus on electric power systems, building envelopes (walls, foundations, roofs, attics, and materials), and methods to improve energy efficiency in existing buildings. Military transportation systems conduct research for sponsors within the US military to improve the efficiency of military deployment, scheduling, and transportation coordination. Much of Energy Division`s research is valuable to other organizations as well as to sponsors. This information is disseminated by the staff`s involvement in professional and trade organizations and workshops; joint research with universities and private-sector firms; collaboration with state and local governments; presentation of work at conferences; and publication of research results in journals, reports, and conference proceedings.

  3. Solid State Division progress report for period ending September 30, 1984

    SciTech Connect (OSTI)

    Green, P.H.; Watson, D.M. (eds.)

    1985-03-01T23:59:59.000Z

    During the reporting period, relatively minor changes have occurred in the research areas of interest to the Division. Nearly all the research of the Division can be classified broadly as mission-oriented basic research. Topics covered include: theoretical solid state physics; surface and near-surface properties of solids; defects in solids; transport properties of solids; neutron scattering; and preparation and characterization of research materials. (GHT)

  4. Isotope and Nuclear Chemistry Division annual report, FY 1983

    SciTech Connect (OSTI)

    Heiken, J.H.; Lindberg, H.A. (eds.)

    1984-05-01T23:59:59.000Z

    This report describes progress in the major research and development programs carried out in FY 1983 by the Isotope and Nuclear Chemistry Division. It covers radiochemical diagnostics of weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production, separation, and applications (including biomedical applications); element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced analytical techniques; development and applications; atmospheric chemistry and transport; and earth and planetary processes.

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

    SciTech Connect (OSTI)

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

    2014-08-08T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2014-09-30T23:59:59.000Z

    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.

  7. Design of a Safeguards Instrument for Plutonium Quantification in an Electrochemical Refining System 

    E-Print Network [OSTI]

    Le Coq, Annabelle G

    2013-06-25T23:59:59.000Z

    There has been a strong international interest in using pyroprocessing to close the fast nuclear reactor fuel cycle and reprocess spent fuel efficiently. To commercialize pyroprocessing, safeguards technologies are required to be developed...

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

    SciTech Connect (OSTI)

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

    2012-04-01T23:59:59.000Z

    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.

  9. A framework for nuclear facility safeguard evaluation using probabilistic methods and expert elicitation

    E-Print Network [OSTI]

    Iamsumang, Chonlagarn

    2010-01-01T23:59:59.000Z

    With the advancement of the next generation of nuclear fuel cycle facilities, concerns of the effectiveness of nuclear facility safeguards have been increasing due to the inclusion of highly enriched material and reprocessing ...

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

    SciTech Connect (OSTI)

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

    2012-12-01T23:59:59.000Z

    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.

  11. JOINT UNITED STATES/IAEA PROPOSED APPROACH FOR SAFEGUARDS DURING PLUTONIUM STABILIZATION, PACKAGING, AND SHIPMENT

    SciTech Connect (OSTI)

    L. KWEI; B. SMITH; ET AL

    2001-02-01T23:59:59.000Z

    For safety reasons, the U.S. Department of Energy (DOE) is preparing to stabilize and package plutonium oxide currently subject to International Atomic Energy Agency safeguards at the Rocky Flats Environmental Technology Site (RFETS) beginning in the year 2001. The Hanford Site will also stabilize and package plutonium materials under IAEA safeguards. The U.S. and the IAEA began consultations in late 1996 to develop an approach to the application of safeguards during stabilization and packaging. With the plans to ship RFETS plutonium to Savannah River for interim storage prior to final disposition, this work has been extended to include safeguards during shipment. This paper will discuss the elements of a joint U.S./IAEA proposal for this task.

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

    SciTech Connect (OSTI)

    Philip Casey Durst; Mark Schanfein

    2012-08-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    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

    2009-01-01T23:59:59.000Z

    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 outlined in the NGSI will be discussed.

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

    SciTech Connect (OSTI)

    JOE,J.

    2007-07-08T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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.

    2010-09-13T23:59:59.000Z

    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.

  16. (Edition 27 of ORNL-5198) Center for Transportation Analysis

    E-Print Network [OSTI]

    Pennycook, Steve

    #12;ORNL-6981 (Edition 27 of ORNL-5198) Center for Transportation Analysis Energy and Transportation Science Division TRANSPORTATION ENERGY DATA BOOK: EDITION 27 Stacy C. Davis Susan W. Diegel Oak Efficiency and Renewable Energy U.S. Department of Energy Prepared by the Oak Ridge National Laboratory Oak

  17. Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control

    SciTech Connect (OSTI)

    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.

    1998-07-07T23:59:59.000Z

    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.

  18. Computer Sciences and Mathematics Division | ornl.gov

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

    Computer Sciences and Mathematics Division SHARE Computer Sciences and Mathematics Division The Computer Science and Mathematics Division (CSMD) is ORNL's premier source of basic...

  19. Computational Sciences and Engineering Division | ornl.gov

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

    Computational Sciences and Engineering Division SHARE Computational Sciences and Engineering Division The Computational Sciences and Engineering Division is a major research...

  20. Authentication of reprocessing plant safeguards data through correlation analysis

    SciTech Connect (OSTI)

    Burr, T.L.; Wangen, L.E.; Mullen, M.F.

    1995-04-01T23:59:59.000Z

    This report investigates the feasibility and benefits of two new approaches to the analysis of safeguards data from reprocessing plants. Both approaches involve some level of plant modeling. All models involve some form of mass balance, either applied in the usual way that leads to material balances for individual process vessels at discrete times or applied by accounting for pipe flow rates that leads to material balances for individual process vessels at continuous times. In the first case, material balances are computed after each tank-to-tank transfer. In the second case, material balances can be computed at any desired time. The two approaches can be described as follows. The first approach considers the application of a new multivariate sequential test. The test statistic is a scalar, but the monitored residual is a vector. The second approach considers the application of recent nonlinear time series methods for the purpose of empirically building a model for the expected magnitude of a material balance or other scalar variable. Although the report restricts attention to monitoring scalar time series, the methodology can be extended to vector time series.

  1. Review of selected dynamic material control functions for international safeguards

    SciTech Connect (OSTI)

    Lowry, L.L.

    1980-09-01T23:59:59.000Z

    With the development of Dynamic Special Nuclear Material Accounting and Control systems used in nuclear manufacturing and reprocessing plants, there arises the question as to how these systems affect the IAEA inspection capabilities. The systems in being and under development provide information and control for a variety of purposes important to the plant operator, the safeguards purpose being one of them. This report attempts to judge the usefulness of these dynamic systems to the IAEA and have defined 12 functions that provide essential information to it. If the information acquired by these dynamic systems is to be useful to the IAEA, the inspectors must be able to independently verify it. Some suggestions are made as to how this might be done. But, even if it should not be possible to verify all the data, the availability to the IAEA of detailed, simultaneous, and plant-wide information would tend to inhibit a plant operator from attempting to generate a floating or fictitious inventory. Suggestions are made that might be helpful in the design of future software systems, an area which has proved to be fatally deficient in some systems and difficult in all.

  2. EMCAS, an evaluation methodology for safeguards and security systems

    SciTech Connect (OSTI)

    Eggers, R.F.; Giese, E.W.; Bichl, F.J.

    1987-07-01T23:59:59.000Z

    EMCAS is an evaluation methodology for safeguards and security systems. It provides a score card of projected or actual system performance for several areas of system operation. In one area, the performance of material control and accounting and security systems, which jointly defend against the insider threat to divert or steal special nuclear material (SNM) using stealth and deceit, is evaluated. Time-dependent and time-independent risk equations are used for both diversion and theft risk calculations. In the case of loss detection by material accounting, a detailed timeliness model is provided to determine the combined effects of loss detection sensitivity and timeliness on the overall effectiveness of the material accounting detection procedure. Calculated risks take into account the capabilities of process area containment/surveillance, material accounting mass balance tests, and physical protection barriers and procedures. In addition, EMCAS evaluates the Material Control and Accounting (MCandA) System in the following areas: (1) system capability to detect errors in the official book inventory of SNM, using mass balance accounting methods, (2) system capability to prevent errors from entering the nuclear material data base during periods of operation between mass balance tests, (3) time to conduct inventories and resolve alarms, and (4) time lost from production to carry out material control and accounting loss detection activities.

  3. EMCAS: An evaluation methodology for safeguards and security systems

    SciTech Connect (OSTI)

    Eggers, R.F.; Giese, E.W.; Bichl, F.J.

    1987-01-01T23:59:59.000Z

    EMCAS is an evaluation methodology for safeguards and security systems. It provides a score card of projected or actual system performance for several areas of system operation. In one area, the performance of material control and accounting and security systems, which jointly defend against the insider threat to divert or steal special nuclear material (SNM) using stealth and deceit, is evaluated. Time-dependent and time-independent risk equations are used for both diversion and theft risk calculations. In the case of loss detection by material accounting, a detailed timeliness model is provided to determine the combined effects of loss detection sensitivity and timeliness on the overall effectiveness of the material accounting detection procedure. Calculated risks take into account the capabilities of process area containment/surveillance, material accounting mass balance tests, and physical protection barriers and procedures. In addition, EMCAS evaluates the Material Control and Accounting (MC and A) System in the following areas: (1) system capability to detect errors in the official book inventory of SNM, using mass balance accounting methods, (2) system capability to prevent errors from entering the nuclear material data base during periods of operation between mass balance tests, (3) time to conduct inventories and resolve alarms, and (4) time lost from production to carry out material control and accounting loss detection activities. 3 figs., 5 tabs.

  4. Applications of a portable MCA in nuclear safeguards

    SciTech Connect (OSTI)

    Halbig, J.K.; Klosterbuer, F.; Cameron, R.A.

    1986-02-01T23:59:59.000Z

    In 1981 a small, battery-operated multichannel analyzer (MCA) prototype developed at Los Alamos National Laboratory was delivered to the International Atomic Energy Agency (IAEA). The intent was to produce an instrument for inspector (nonscientist) use. Automated measurement programs were built into the MCA. An enhanced, commercially produced MCA is now available, which was patterned after and is software compatible with the prototype. After an extensive review of the hardware and software of the available portable MCAs, the IAEA has chosen this MCA to be used by IAEA inspectors throughout the world. Inspectors from the EURATOM Directorate of Safeguards are also using these MCAs in inspections throughout Europe. While this MCA's portability and programmability make it ideally suited for infield applications, its powerful built-in intelligence and communications protocol make it a strong candidate for distributed data acquisition and control systems. The user-instrument interface philosophy is so easy to use that in domestic and international training schools, the operators manual is not used.

  5. Materials accounting and international safeguards for MOX facilities

    SciTech Connect (OSTI)

    Pillay, K.K.S.; Picard, R.R.; Hafer, J.F.

    1989-01-01T23:59:59.000Z

    Our experience with mixed oxide (MOX) fuel fabrication facilities leads us to conclude that there is inadequate guidance available to plant and process designers to make materials accounting systems timely, efficient, and minimally intrusive. A well designed state system for accounting and control of nuclear materials would be beneficial to plant operations and verification by the International Atomic Energy Agency (IAEA) or state regulatory agencies. Among the difficult accounting problems that arise in a large-scale MOX facility are the following: (1) process steps (such as the blending and splitting of powders) that require the accounting system to track material flow, calculate quantities based on previous measurements, and propagate uncertainties as part of data analysis; (2) extensive buffer storage areas involving long residence times that necessitate frequent corrections for material loss from radioactive decay; and (3) facility accounting at one level (for example, fuel pins) that must be reconciled with verification measurements at another level (for example, pin trays or assemblies). Approaches to addressing these problems include designing a special facility, simulating material flow, developing software for near-real-time materials accounting, and establishing achievable verification goals. This paper elaborates on these problems and proposes approaches to a materials accounting system design that considers facility, state, and IAEA safeguards and verification objectives. 11 refs., 1 fig., 1 tab.

  6. DIVISION 6 -WOOD AND PLASTICS 06000 GENERAL

    E-Print Network [OSTI]

    DIVISION 6 - WOOD AND PLASTICS ________________________________________________________________________ 06000 GENERAL 1. For both woods and plastics, special attention is called to matters of flame spread-dried. 3. For exterior wood or plastic framed structures, see Division 4 for dimensions of Sample Panel

  7. Sumit Mukhopadhyay Earth Sciences Division

    E-Print Network [OSTI]

    Ajo-Franklin, Jonathan

    -reactive transport in saturated and unsaturated porous and fractured media Subsurface carbon dioxide sequestration temperature logging for characterization of fractured unsaturated zone Mathematical modeling of fluid flow Modeling of heat and vapor transport processes in geothermal reservoirs Modeling of reactive transport

  8. Education Strategy Team Policy Division

    E-Print Network [OSTI]

    Rambaut, Andrew

    Education Strategy Team Policy Division DFID 1 Palace Street London SW1E 5HE 30 October 2009 TEL fellowships in India under the Wellcome Trust/DBT India Alliance2 . We believe that such investment is vital/Global-health-research/WTX055734.htm 2 Wellcome Trust/DBT India Alliance: http://www.wellcomedbt.org/index.htm #12;to support

  9. Publishing Division The Edinburgh Building

    E-Print Network [OSTI]

    Rosenberger, Alfred H.

    Publishing Division The Edinburgh Building Shaftesbury Road Cambridge CB2 2RU, UK TELEPHONE 01223 Building, Cambridge CB2 2RU, UK 40 West 20th Street, New York NY 10011-4211, USA 477 Williamstown Road Record [1] walter carl hartwig 2 The origin of primates [5] david tab rasmussen The earliest primates

  10. Biosciences Division Media Mentions | Clean Energy | ORNL

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

    Biosciences Division Publications Newsletters Organizational Charts Research Highlights Media Mentions Clean Energy Home | Science & Discovery | Clean Energy | Supporting...

  11. Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories

    Office of Legacy Management (LM)

    Radiological Condition of the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories Cheswick, Pennsylvania -. -, -- AGENCY: Office of Operational Safety, Department...

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

    SciTech Connect (OSTI)

    Beddingfield, David H [Los Alamos National Laboratory; Lafleur, Adrienne M [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    PEPPER, S.; OSIECKI, C.

    2006-07-16T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Demuth, Scott F [Los Alamos National Laboratory; Grice, Thomas [NRC; Lockwood, Dunbar [DOE/NA-243

    2010-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Dr. Mark Schanfein; Philip Casey Durst

    2012-07-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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)

    2009-10-01T23:59:59.000Z

    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.

  17. Finance Division EXTRA MILE AWARD PROGRAM

    E-Print Network [OSTI]

    Crews, Stephen

    Finance Division EXTRA MILE AWARD PROGRAM Nomination Form Instructions Any fulltime or parttime permanent or temporary SPA employee within the Finance Division who works 20 or more provided. The seven major departments within the Finance Division to choose from are described below

  18. Analytical Chemistry Division's sample transaction system

    SciTech Connect (OSTI)

    Stanton, J.S.; Tilson, P.A.

    1980-10-01T23:59:59.000Z

    The Analytical Chemistry Division uses the DECsystem-10 computer for a wide range of tasks: sample management, timekeeping, quality assurance, and data calculation. This document describes the features and operating characteristics of many of the computer programs used by the Division. The descriptions are divided into chapters which cover all of the information about one aspect of the Analytical Chemistry Division's computer processing.

  19. EARTH SCIENCES Lower-Division Requirements

    E-Print Network [OSTI]

    Constable, Steve

    2012-2013 EARTH SCIENCES Lower-Division Requirements Math 20A_____ 20B_____ 20C_____ 20D (BILD 3) _____ SIO 50* _____ Group A: Earth Science Upper-Division Core Requirements (all courses _____ Introduction to Geophysics SIO 104 _____ Paleobiology and History of Life* Group B: Upper-Division Earth

  20. Computer Security Division 2008 Annual Report

    E-Print Network [OSTI]

    Computer Security Division 2008 Annual Report #12;TAble of ConTenTS Welcome 1 Division Organization 2 The Computer Security Division Responds to the Federal Information Security Management Act of 2002 3 Security Management and Assistance Group (SMA) 4 FISMA Implementation Project 4 Publications

  1. Transportation Demand

    Annual Energy Outlook 2013 [U.S. Energy Information Administration (EIA)]

    energy consumption across the nine Census Divisions (see Figure 5) and over ten fuel types. Each fuel type is modeled according to fuel-specific technology attributes...

  2. MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1980

    E-Print Network [OSTI]

    Searcy, Alan W.

    2010-01-01T23:59:59.000Z

    of trans­ uranium organometallic chemistry, particularlyfor Uranium Isotope Separation," Chemistry Division, IsotopeOlander, "Uranium Enrichment by Laser," Chemistry Division,

  3. analytical sciences division: Topics by E-print Network

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

    Division Environmental Management and Restoration Websites Summary: Chemical Sciences and Engineering Division Director Assoc Director Ops Assoc Director Science Yates...

  4. MATERIALS AND MOLECULAR RESEARCH DIVISION. ANNUAL REPORT 1980

    E-Print Network [OSTI]

    Searcy, Alan W.

    2010-01-01T23:59:59.000Z

    for Uranium Isotope Separation," Chemistry Division, Isotopeof trans­ uranium organometallic chemistry, particularlyOlander, "Uranium Enrichment by Laser," Chemistry Division,

  5. An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle

    SciTech Connect (OSTI)

    Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K. NNL

    2011-01-13T23:59:59.000Z

    Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/ or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

  6. An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle

    SciTech Connect (OSTI)

    Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Boyer, B. D. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K., NNL

    2010-11-24T23:59:59.000Z

    Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

  7. Development and Evaluation of a Safeguards System Concept for a Pebble-Fueled High Temperature Gas-cooled Reactor 

    E-Print Network [OSTI]

    Gitau, Ernest Travis Ngure

    2012-10-19T23:59:59.000Z

    the world, adequate methods for safeguarding the reactor must be developed. Current safeguards methods for the pebble-fueled HTGR focus on extensive, redundant containment and surveillance (C/S) measures or a combination of item-type and bulk-type material...

  8. Proceedings of the ASME Fuel Cell Division 2000: The 2000 ASME International Mechanical Engineering Congress & Exposition

    E-Print Network [OSTI]

    Wang, Chao-Yang

    Proceedings of the ASME Fuel Cell Division ­ 2000: The 2000 ASME International Mechanical ANALYSIS OF TRANSPORT AND REACTION IN PROTON EXCHANGE MEMBRANE FUEL CELLS Sukkee Um and C.Y. Wang exchange membrane (PEM) fuel cells with a Nafion 117 membrane and an interdigitated flow field

  9. Energy Division annual progress report for period ending September 30, 1991

    SciTech Connect (OSTI)

    Stone, J.N. (ed.)

    1992-04-01T23:59:59.000Z

    The Energy Division is one of 17 research divisions at Oak Ridge Laboratory. Its goals and accomplishments are described in this annual progress report for FY 1991. The division's total expenditures in FY 1991 were $39.1 million. The work is supported by the US Department of Energy, US Department of Defense, many other federal agencies, and some private organizations. Disciplines of the 124 technical staff members include engineering, social sciences, physical and life sciences, and mathematics and statistics. The Energy Division's programmatic activities focus on three major areas: (1) analysis and assessment, (2) energy conservation technologies, and (3) military transportation systems. Analysis and assessment activities cover energy and resource analysis, the preparation of environmental assessments and impact statements, research on waste management, analysis of emergency preparedness for natural and technological disasters, analysis of the energy and environmental needs of developing countries, technology transfer, and analysis of civilian transportation. Energy conservation technologies include electric power systems, building equipment (thermally activated heat pumps, advanced refrigeration systems, novel cycles), building envelopes (walls, foundations, roofs, attics, and materials), and technical issues for improving energy efficiency in existing buildings. Military transportation systems concentrate on research for sponsors within the US military on improving the efficiency of military deployment, scheduling, and transportation coordination.

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

    SciTech Connect (OSTI)

    Boyer, Brian D [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2011-02-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Pan, Paul Y [Los Alamos National Laboratory

    2010-12-10T23:59:59.000Z

    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.

  13. Health, Safety, and Environment Division

    SciTech Connect (OSTI)

    Wade, C [comp.] [comp.

    1992-01-01T23:59:59.000Z

    The primary responsibility of the Health, Safety, and Environmental (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environmental protection. These activities are designed to protect the worker, the public, and the environment. Meeting these responsibilities requires expertise in many disciplines, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science and engineering, analytical chemistry, epidemiology, and waste management. New and challenging health, safety, and environmental problems occasionally arise from the diverse research and development work of the Laboratory, and research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed, to study specific problems for the Department of Energy. The results of these programs help develop better practices in occupational health and safety, radiation protection, and environmental science.

  14. Division of Administration and Finance Parking and Transportation Services

    E-Print Network [OSTI]

    Bittner, Eric R.

    COMMUNITY INVITED TO GIVE INPUT ON RECOMMENDED FY 14 AND FY 15 PARKING PERMIT RATES Houston April 29, 2013, faculty and staff representatives, has approved the FY14 and FY15 proposed parking permit rates

  15. Division of Administration and Finance Parking and Transportation Services

    E-Print Network [OSTI]

    Bittner, Eric R.

    @central.uh.edu BOARD OF REGENTS APPROVES 2013-2014 PARKING PERMIT PRICES Houston, May 23, 2013 ­ The University of Houston System Board of Regents has approved the parking permit prices for the 2013-2014 academic year. Click here to see a complete listing of the rates. Those who have not yet purchased a permit

  16. Hawaii Department of Transportation Highways Division | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to: navigation, search OpenEI ReferenceJumpEnergyStrategy |Hatchet RidgeInformation Hawaii

  17. Accelerator and Fusion Research Division: summary of activities, 1983

    SciTech Connect (OSTI)

    Not Available

    1984-08-01T23:59:59.000Z

    The activities described in this summary of the Accelerator and Fusion Research Division are diverse, yet united by a common theme: it is our purpose to explore technologically advanced techniques for the production, acceleration, or transport of high-energy beams. These beams may be the heavy ions of interest in nuclear science, medical research, and heavy-ion inertial-confinement fusion; they may be beams of deuterium and hydrogen atoms, used to heat and confine plasmas in magnetic fusion experiments; they may be ultrahigh-energy protons for the next high-energy hadron collider; or they may be high-brilliance, highly coherent, picosecond pulses of synchrotron radiation.

  18. California Division of Water Rights | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:Power LP Biomass Facilityin Charts Jump28TransportationDivision of

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

    SciTech Connect (OSTI)

    Coleman, RL

    2002-10-21T23:59:59.000Z

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

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

    ScienceCinema (OSTI)

    Thomas D'Agostino

    2010-09-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2011-01-01T23:59:59.000Z

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

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

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

    2003-08-19T23:59:59.000Z

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

  3. Reactor antineutrino monitoring with a plastic scintillator array as a new safeguards method

    E-Print Network [OSTI]

    S. Oguri; Y. Kuroda; Y. Kato; R. Nakata; Y. Inoue; C. Ito; M. Minowa

    2014-05-23T23:59:59.000Z

    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.

  4. MINOR for Natural Resources Conservation Conserving Earth's biological diversity and safeguarding the benefits or "ecosystem services"

    E-Print Network [OSTI]

    Schweik, Charles M.

    . Environmental Resources NRC 390E Evolution and Conservation (3cr-sprg) NRC 575 Case Studies in Conservation NRC for Natural Resources Conservation Conserving Earth's biological diversity and safeguarding the benefits resources conservation. In this minor, students learn about the ecology of terrestrial and aquatic

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

    SciTech Connect (OSTI)

    Ward,R.; Rosenthal,M.

    2009-07-12T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2010-01-01T23:59:59.000Z

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

  7. Development of a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities 

    E-Print Network [OSTI]

    Rauch, Eric B.

    2010-07-14T23:59:59.000Z

    this type of reactor desirable also make it suspicious to the international community as a possible means to shorten that state?s nuclear latency. If a safeguards approach could be developed for a fuel cycle featuring one of these reactors, it would ease...

  8. Applications of virtual reality to nuclear safeguards and non-proliferation

    SciTech Connect (OSTI)

    Stansfield, S.

    1996-12-31T23:59:59.000Z

    This paper presents several applications of virtual reality relevant to the areas of nuclear safeguards and non-proliferation. Each of these applications was developed to the prototype stage at Sandia National Laboratories` Virtual Reality and Intelligent Simulation laboratory. These applications include the use of virtual reality for facility visualization, training of inspection personnel, and security and monitoring of nuclear facilities.

  9. Role of IAEA (International Atomic Energy Agency) safeguards in confidence building

    SciTech Connect (OSTI)

    Augustson, R.H.

    1989-01-01T23:59:59.000Z

    In this paper, I will examine some attributes of confidence building and connect them with how the International Atomic Energy Agency (IAEA) interacts with its member states in carrying out its safeguards function. These interactions and the structure set up to define them help maintain and strengthen confidence between the IAEA and the member states and among these states. 3 refs.

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

    SciTech Connect (OSTI)

    Gouveia, Fernando; Metcalf, Richard Royce Madison

    2010-07-01T23:59:59.000Z

    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.

  11. Abstract: The challenges in nuclear safeguards and in nuclear security have significantly changed over the last decades. On the one side nuclear safeguards evolved from the simple verifica9on of declared amounts of material to a more informa9on driven app

    E-Print Network [OSTI]

    Abstract: The challenges in nuclear safeguards and in nuclear security have significantly changed over the last decades. On the one side nuclear safeguards evolved-doctoral researcher where he analysed dissolu9on residues from reprocessing of nuclear fuels

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

    SciTech Connect (OSTI)

    Laughter, Mark D [ORNL; Whitaker, J Michael [ORNL; Howell, John [University of Glasgow

    2010-01-01T23:59:59.000Z

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

  13. IAEA SAFEGUARDS DURING PLUTONIUM STABILIZATION AT HANFORDS PLUTONIUM FINISHING PLANT (PFP)

    SciTech Connect (OSTI)

    MCRAE, L.P.

    2004-02-20T23:59:59.000Z

    The Vault at the Plutonium Finishing Plan (PFP) became subject to the International Atomic Energy Agency (IAEA) safeguards beginning in 1994 as part of the US excess fissile material program. The inventory needed to be stabilized and repackaged for long-term storage to comply with Defense Nuclear Facilities Safety Board Recommendation 94-1. In 1998, the United States began negotiations with IAEA to develop methods to maintain safeguards as this material was stabilized and repackaged. The Design Information Questionnaire was revised and submitted to the IAEA in 2002 describing how PFP would be modified to accommodate the stabilization process line. The operation plan for 2003 was submitted describing the proposed schedules for removing materials for stabilization. Stabilization and repackaging activities for the safeguarded plutonium began in January 2003 and were completed in December 2003. The safeguards approach implemented at the Hanford Site was a combination of the original baseline approach augmented by a series of five vault additions of stabilized materials followed by five removals of unstabilized materials. IAEA containment and surveillance measures were maintained until the unstabilized material was removed. Following placement of repackaged material (most from the original safeguarded stock) into the storage vault, the IAEA conducted inventory change verification measurements and then established containment and surveillance. As part of the stabilization campaign, the IAEA developed new measurement methods and calibration standards representative of the materials and packaging. The annual physical inventory verification was conducted on the normal IAEA schedule following the fourth additional/removal phase. Plant activities and the impacts on operations are described.

  14. On Making Relational Division Comprehensible

    E-Print Network [OSTI]

    McCann, Lester I.

    pno jno qty S1 P1 J1 200 ... ... ... ... S5 P6 J4 500 FIE 2003 ­ p.8/33 #12;A More Practical Example,pno(SPJ) and pno(weight=17(P)) sno pno pno S1 P1 P2 S2 P3 P3 S2 P5 S3 P3 S3 P4 S4 P6 S5 P1 S5 P2 S5 P3 S5 P4 S5 P5 S5 P6 FIE 2003 ­ p.10/33 #12;Division in Relational Algebra Idea: Find the values that do

  15. Colorado Air Pollution Control Division - Construction Permits...

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library Web Site: Colorado Air Pollution Control Division - Construction Permits Forms and Air Pollutant Emission Notices (APENs)...

  16. EARTH SCIENCES DIVISION. ANNUAL REPORT 1977.

    E-Print Network [OSTI]

    Witherspoon, P.A.

    2011-01-01T23:59:59.000Z

    8erkeley Laboratory (LBL), the Earth Sciences Division, wasactivation analysis: rare earth element distribution (D)can be used to generate earth- quake records for use in

  17. Enforcement Letter, Westinghouse Waste Isolation Division - October...

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

    to Westinghouse Waste Isolation Division related to Quality Assurance and Occupational Radiation Protection Noncompliances at the Waste Isolation Pilot Plant On October 3, 2000,...

  18. Sandia National Laboratories: Internal Combustion Engine Division...

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

    Internal Combustion Engine Division conference CRF Researchers Received "Best Paper" Award for Paper Presented at American Society of Mechanical Engineers' (ASME) 2012 Internal...

  19. Chemical Sciences Division | Advanced Materials |ORNL

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

    reduce costs, and minimize the environmental impact in the production of rare-earth metals and alloys. The division's Nuclear Analytical Chemistry and Isotopics...

  20. ORNL/TM-2009/222 Center for Transportation Analysis

    E-Print Network [OSTI]

    . ESTIMATION OF GASOLINE CONSUMPTION BY PUBLIC SECTOR..............41 5.1 Federal Civilian Motor/Commercial Sectors..............................................29 4.3 Off-highway Gasoline Consumption by EquipmentORNL/TM-2009/222 Center for Transportation Analysis Energy and Transportation Science Division OFF

  1. TRANSPORTATION ENERGY FORECASTS AND ANALYSES FOR THE 2009

    E-Print Network [OSTI]

    Page Manager FOSSIL FUELS OFFICE Mike Smith Deputy Director FUELS AND TRANSPORTATION DIVISION Melissa, Weights and Measurements/Gary Castro, Allan Morrison, John Mough, Ed Williams Clean Energy FuelsCALIFORNIA ENERGY COMMISSION TRANSPORTATION ENERGY FORECASTS AND ANALYSES FOR THE 2009 INTEGRATED

  2. Energy and Environmental Systems Division 1981 research review

    SciTech Connect (OSTI)

    Not Available

    1982-04-01T23:59:59.000Z

    To effectively manage the nation's energy and natural resources, government and industry leaders need accurate information regarding the performance and economics of advanced energy systems and the costs and benefits of public-sector initiatives. The Energy and Environmental Systems Division (EES) of Argonne National Laboratory conducts applied research and development programs that provide such information through systems analysis, geophysical field research, and engineering studies. During 1981, the division: analyzed the production economics of specific energy resources, such as biomass and tight sands gas; developed and transferred to industry economically efficient techniques for addressing energy-related resource management and environmental protection problems, such as the reclamation of strip-mined land; determined the engineering performance and cost of advanced energy-supply and pollution-control systems; analyzed future markets for district heating systems and other emerging energy technologies; determined, in strategic planning studies, the availability of resources needed for new energy technologies, such as the imported metals used in advanced electric-vehicle batteries; evaluated the effectiveness of strategies for reducing scarce-fuel consumption in the transportation sector; identified the costs and benefits of measures designed to stabilize the financial condition of US electric utilities; estimated the costs of nuclear reactor shutdowns and evaluated geologic conditions at potential sites for permanent underground storage of nuclear waste; evaluated the cost-effectiveness of environmental regulations, particularly those affecting coal combustion; and identified the environmental effects of energy technologies and transportation systems.

  3. Physics Division ESH Bulletin 02-7 New Physics Division Procedure

    E-Print Network [OSTI]

    Physics Division ESH Bulletin 02-7 New Physics Division Procedure Applies to disablement of Physics-Interlock Disablement form is completed and given to the ESH Officer for filing 6/10/02 INTERLOCKS, TEMPORARY DISABLEMENT FILE maintained by Physics Division ESH Officer) #12;

  4. Local Transportation

    E-Print Network [OSTI]

    Local Transportation. Transportation from the Airport to Hotel. There are two types of taxi companies that operate at the airport: special and regular taxis (

  5. Greening Transportation

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

    Transportation Goal 2: Greening Transportation LANL supports and encourages employees to reduce their personal greenhouse gas emissions by offering various commuting and work...

  6. Chamber transport

    SciTech Connect (OSTI)

    OLSON,CRAIG L.

    2000-05-17T23:59:59.000Z

    Heavy ion beam transport through the containment chamber plays a crucial role in all heavy ion fusion (HIF) scenarios. Here, several parameters are used to characterize the operating space for HIF beams; transport modes are assessed in relation to evolving target/accelerator requirements; results of recent relevant experiments and simulations of HIF transport are summarized; and relevant instabilities are reviewed. All transport options still exist, including (1) vacuum ballistic transport, (2) neutralized ballistic transport, and (3) channel-like transport. Presently, the European HIF program favors vacuum ballistic transport, while the US HIF program favors neutralized ballistic transport with channel-like transport as an alternate approach. Further transport research is needed to clearly guide selection of the most attractive, integrated HIF system.

  7. West Virginia University Division of Human Resources

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    on the WVU Division of Human Resources Web page hr.wvu.edu. In the event of a conflict between the current posted version and this printed copy, the posted version on the Web page is controlling. Page 1 of 2 of this administrative procedure has been posted on the WVU Division of Human Resources Web page hr.wvu.edu. In the event

  8. West Virginia University Division of Human Resources

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    on the WVU Division of Human Resources Web page hr.wvu.edu. In the event of a conflict between the current posted version and this printed copy, the posted version on the Web page is controlling. Page 1 of 3 Division of Human Resources Web page hr.wvu.edu. In the event of a conflict between the current posted

  9. West Virginia University Division of Human Resources

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    on the WVU Division of Human Resources Web page hr.wvu.edu. In the event of a conflict between the current posted version and this printed copy, the posted version on the Web page is controlling. Page 1 of 2 been posted on the WVU Division of Human Resources Web page hr.wvu.edu. In the event of a conflict

  10. West Virginia University Division of Human Resources

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    Division of Human Resources Web page hr.wvu.edu. In the event of a conflict between the current posted version and this printed copy, the posted version on the Web page is controlling. Page 1 of 2 Employment been posted on the WVU Division of Human Resources Web page hr.wvu.edu. In the event of a conflict

  11. West Virginia University Division of Human Resources

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    Division of Human Resources Web page hr.wvu.edu. In the event of a conflict between the current posted version and this printed copy, the posted version on the Web page is controlling. Page 1 of 2 Access been posted on the WVU Division of Human Resources Web page hr.wvu.edu. In the event of a conflict

  12. Satellite Meteorology and Climatology Division Roadmap

    E-Print Network [OSTI]

    Kuligowski, Bob

    Satellite Meteorology and Climatology Division Roadmap NOAA NESDIS Center for Satellite Applications and Research #12;SMCD Roadmap 2 NOAA/NESDIS/STAR Satellite Meteorology and Climatology Division Roadmap September 2005 NOAA Science Center, 5200 Auth Road, Room 712, Camp Springs, MD 20746 #12;SMCD

  13. Nuclear Engineering Division Think, explore, discover, innovate

    E-Print Network [OSTI]

    Kemner, Ken

    : "Application of an Annular Metallic Fuel with Lower Gas Plenum for Sodium- cooled Fast Reactor") ANS N. Stauff Award ANS K. Laurin-Kovitz 2013 Best Paper Award in Reactor Physics Division (RPD) (Paper Title Nuclear Society E. Merzari, H. Ninokata(***) 2010 Best Paper in Reactor Physics Division (RPD) American

  14. Progress Report on Power Division Work Plan

    E-Print Network [OSTI]

    RPS & impacts on PNW · Analysis of negative wholesale power prices · Wind Integration Forum · Maintain balancing" DR pilot programs · Tracking Smart Grid Demo Project ­ ­ Will include "conventional" and "load/windProgress Report on Power Division Work Plan Power Committee Meeting October 2010 1 #12;The Division

  15. EMS Division Potential Benefits of Selected

    E-Print Network [OSTI]

    driven by a high speed gas turbine supplied power to a 400 HP superconductive homopolar motor during at Overcome by New Technology: Cryocoolers & Cu Fiber brushes2 #12;EMS Division Baseline with Multi-turn Field Coil Multi-turn Armature Cryostat Steel Flux Return #12;EMS Division Homopolar Motor Technology

  16. LEADERSHIP TRAINING DIVISION Undergraduate Program Application

    E-Print Network [OSTI]

    Emmons, Scott

    LEADERSHIP TRAINING DIVISION Undergraduate Program Application 1 For more information: Questions in school: College: School in Israel: (if applicable): Major/Minor: High School: #12;LEADERSHIP TRAINING DIVISION Undergraduate Program Application 2 QUEST LEADERSHIP FELLOWSHIP The mission of Quest is to inspire

  17. Materials Sciences Division 1990 annual report

    SciTech Connect (OSTI)

    Not Available

    1990-12-31T23:59:59.000Z

    This report is the Materials Sciences Division`s annual report. It contains abstracts describing materials research at the National Center for Electron Microscopy, and for research groups in metallurgy, solid-state physics, materials chemistry, electrochemical energy storage, electronic materials, surface science and catalysis, ceramic science, high tc superconductivity, polymers, composites, and high performance metals.

  18. PHYSICS DIVISION ESH BULLETIN 07-02

    E-Print Network [OSTI]

    , and sealed or open celled lead-acid. No batteries should be disposed of in the trash. HOW TO MANAGE USED the Division Waste Generator to dispose lead-acid (car) batteries or if you have any questions. ReferencePHYSICS DIVISION ESH BULLETIN 07-02 BATTERY RECYCLING May 21, 2007 ORNL recycles all types

  19. Aviation Human Factors Division Institute of Aviation

    E-Print Network [OSTI]

    AHFD Aviation Human Factors Division Institute of Aviation University of Illinois at Urbana Systems Monitoring and Control Gavin R. Essenberg, Douglas A. Wiegmann, Aviation Human Factors Division experiments with more difficult path selection tasks might reveal if there are advantages for motion. Overall

  20. School of Art Division of Graphic Design

    E-Print Network [OSTI]

    Moore, Paul A.

    .372.7763 419.372.6955 fax lyoung@bgsu.edu www.bgsu.edu/art BOWLING GREEN STATE UNIVERSITY Division of Graphic.bgsu.edu/art BOWLING GREEN STATE UNIVERSITY 1) Be of Junior (60+ hours) or Senior (90+ hours) standing withinSchool of Art Division of Graphic Design 1020 Fine Arts Center Bowling Green, Ohio 43403-0204 419

  1. Fixed Income Division Nomura International plc

    E-Print Network [OSTI]

    Macrina, Andrea

    Fixed Income Division © Nomura International plc Symmetry methods for quadratic Gaussian models International plc Outline Motivation The quadratic Gaussian distribution The quadratic Gaussian process The quadratic Gaussian model #12;Fixed Income Division 3© Nomura International plc Part 1 Motivation #12;Fixed

  2. Physics division annual report 2005.

    SciTech Connect (OSTI)

    Glover, J.; Physics

    2007-03-12T23:59:59.000Z

    This report highlights the research performed in 2005 in the Physics Division of Argonne National Laboratory. The Division's programs include operation of ATLAS as a national user facility, nuclear structure and reaction research, nuclear theory, medium energy nuclear research and accelerator research and development. The mission of Nuclear Physics is to understand the origin, evolution and structure of baryonic matter in the universe--the matter that makes up stars, planets and human life itself. The Division's research focuses on innovative new ways to address this mission and 2005 was a year of great progress. One of the most exciting developments is the initiation of the Californium Rare Ion Breeder Upgrade, CARIBU. By combining a Cf-252 fission source, the gas catcher technology developed for rare isotope beams, a high-resolution isobar separator, and charge breeding ECR technology, CARIBU will make hundreds of new neutron-rich isotope beams available for research. The cover illustration shows the anticipated intensities of low-energy beams that become available for low-energy experiments and for injection into ATLAS for reacceleration. CARIBU will be completed in early 2009 and provide us with considerable experience in many of the technologies developed for a future high intensity exotic beam facility. Notable results in research at ATLAS include a measurement of the isomeric states in {sup 252}No that helps pin down the single particle structure expected for superheavy elements, and a new low-background measurement of {sup 16}N beta-decay to determine the {sup 12}C({alpha},{gamma}){sup 16}O reaction rate that is so important in astrophysical environments. Precise mass measurements shed new light on the unitarity of the quark weak-mixing matrix in the search for physics beyond the standard model. ATLAS operated for 4686 hours of research in FY2005 while achieving 95% efficiency of beam delivery for experiments. In Medium-Energy Physics, radium isotopes were trapped in an atom trap for the first time, a major milestone in an innovative search for the violation of time-reversal symmetry. New results from HERMES establish that strange quarks carry little of the spin of the proton and precise results have been obtained at JLAB on the changes in quark distributions in light nuclei. New theoretical results reveal that the nature of the surfaces of strange quark stars. Green's function Monte Carlo techniques have been extended to scattering problems and show great promise for the accurate calculation, from first principles, of important astrophysical reactions. Flame propagation in type 1A supernova has been simulated, a numerical process that requires considering length scales that vary by factors of eight to twelve orders of magnitude. Argonne continues to lead in the development and exploitation of the new technical concepts that will truly make an advanced exotic beam facility, in the words of NSAC, 'the world-leading facility for research in nuclear structure and nuclear astrophysics'. Our science and our technology continue to point the way to this major advance. It is a tremendously exciting time in science for these new capabilities hold the keys to unlocking important secrets of nature. The great progress that has been made in meeting the exciting intellectual challenges of modern nuclear physics reflects the talents and dedication of the Physics Division staff and the visitors, guests and students who bring so much to the research.

  3. Earth Sciences Division Research Summaries 2006-2007

    E-Print Network [OSTI]

    DePaolo, Donald

    2008-01-01T23:59:59.000Z

    the commencement of the Earth Sciences Division 30 yearstelling. Happy Anniversary! Earth Sciences Division ears YTritium in Engineered and Earth Materials Stefan Finsterle,

  4. APS Engineering Support Division (AES) | Advanced Photon Source

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

    APS Engineering Support Division (AES) The APS Engineering Support Division provides reliable operations and technical support to the Advanced Photon Source user community. AES...

  5. Master safeguards and security agreements and protection program planning orders and guide

    SciTech Connect (OSTI)

    Hensley, B.

    1988-01-01T23:59:59.000Z

    This paper discusses the Master Safeguards and Security Agreement (MSSA) and Protection Program Planning (PPP) orders of the Department of Energy (DOE). Both orders establish DOE policy, requirements, responsibilities, and authorities for the development and implementation of MSSA's and associated planning documents. The MSSA subcommittee to the Policy Development Task Force was responsible for the development of the MSSA order. Unlike other subcommittees that were involved in updating existing orders, the AMSSA subcommittee produced the initial version of the MSSA order. The subcommittee included representation from DOE outlay program offices with Headquarters and field office safeguards and security expertise. The PPP order was developed by a separate subcommittee and included representation mainly from the Task Force itself. It was completed much later than the other orders and remains under review within the Department.

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

    SciTech Connect (OSTI)

    Hockert, John; Burbank, Roberta L.

    2010-04-13T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Brim, Cornelia P.

    2013-03-04T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Brim, Cornelia P.

    2013-04-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Tackentien,J.

    2008-06-12T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Schanfein, Mark J; Gouveia, Fernando S

    2010-07-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2012-11-09T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2013-01-26T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2011-07-01T23:59:59.000Z

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

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

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

    2006-12-15T23:59:59.000Z

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

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

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

    2006-12-15T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2014-11-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Ku, J.H.; Choung, W.M.; You, G.S.; Moon, S.I.; Park, S.H.; Kim, H.D. [Korea Atomic Energy Research Institute - KAERI, 989-111 Daeduk-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2013-07-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Beddingfield, David H [Los Alamos National Laboratory; Gerhart, Jeremy J [Los Alamos National Laboratory; Kawakubo, Yoko [JAEA

    2009-01-01T23:59:59.000Z

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

  19. ASSESS (Analytic System and Software for Evaluating Safeguards and Security) update: Current status and future developments

    SciTech Connect (OSTI)

    Al-Ayat, R.A. (Lawrence Livermore National Lab., CA (USA)); Cousins, T.D. (USDOE, Washington, DC (USA)); Hoover, E.R. (Sandia National Labs., Albuquerque, NM (USA))

    1990-07-15T23:59:59.000Z

    The Analytic System and Software for Evaluating Safeguards and Security (ASSESS) has been released for use by DOE field offices and their contractors. In October, 1989, we offered a prototype workshop to selected representatives of the DOE community. Based on the prototype results, we held the first training workshop at the Central Training Academy in January, 1990. Four additional workshops are scheduled for FY 1990. ASSESS is a state-of-the-art analytical tool for management to conduct integrated evaluation of safeguards systems at facilities handling facilities. Currently, ASSESS focuses on the threat of theft/diversion of special nuclear material by insiders, outsiders, and a special form of insider/outsider collusion. ASSESS also includes a neutralization module. Development of the tool is continuing. Plans are underway to expand the capabilities of ASSESS to evaluate against violent insiders, to validate the databases, to expand the neutralization module, and to assist in demonstrating compliance with DOE Material Control and Accountability (MC A) Order 5633.3. These new capabilities include the ability to: compute a weighted average for performance capability against a spectrum of insider adversaries; conduct defense-in-depth analyses; and analyze against protracted theft scenarios. As they become available, these capabilities will be incorporated in our training program. ASSESS is being developed jointly by Lawrence Livermore and Sandia National Laboratories under the sponsorship of the Department of Energy (DOE) Office of Safeguards and Security.

  20. Status of Safeguards and Separations Model Development at Plant and Molecular Levels

    SciTech Connect (OSTI)

    de Almeida, Valmor F [ORNL; Hay, Benjamin [ORNL; DePaoli, David W [ORNL

    2009-10-01T23:59:59.000Z

    A primary goal of the Safeguards and Separations IPSC effort is the development of process modeling tools that allow dynamic simulations of separations plant operations under various configurations and conditions, and integration of relevant safeguards analyses. A requirement of the effort is to develop codes on modern, expandable architectures, with flexibility to explore and evaluate a wide range of process options. During FY09, efforts at ORNL have been focused on two priority tasks toward achieving the IPSC goal: (1) a top-down exploration of architecture - Subtask 1: Explore framework for code development and integration for plant-level simulation; and (2) a bottom-up fundamental modeling effort - Subtask 2: Development of molecular-level agent design code. Subtask 1 is important because definition and development of architecture is a key issue for the overall effort, as selection of an overall approach and code/data requirements is a necessary first step in the organization, design and development of separations and safeguards codes that will be incorporated. The agent design effort of Subtask 2 is a molecular-level modeling effort that has a direct impact on a near-term issue of the Separations and Waste Forms Campaign. A current focus of experimental efforts is the development of robust agents and processes for separation of Am/Cm. Development of enhanced agent-design codes will greatly accelerate discovery and experimental testing.

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

    SciTech Connect (OSTI)

    MCRAE, L.P.

    2004-06-30T23:59:59.000Z

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

  2. Microsoft PowerPoint - 9_SUZANNE_ANI_NMMSS_2014 MCA-SAni.pptx

    National Nuclear Security Administration (NNSA)

    Material Safety & Safeguards Division of Fuel Cycle Safety & Safeguards Material Control & Accounting Branch At the NRC... Office of Nuclear Material Safety & Safeguards...

  3. Biology and Medicine Division: Annual report 1986

    SciTech Connect (OSTI)

    Not Available

    1987-04-01T23:59:59.000Z

    The Biology and Medicine Division continues to make important contributions in scientific areas in which it has a long-established leadership role. For 50 years the Division has pioneered in the application of radioisotopes and charged particles to biology and medicine. There is a growing emphasis on cellular and molecular applications in the work of all the Division's research groups. The powerful tools of genetic engineering, the use of recombinant products, the analytical application of DNA probes, and the use of restriction fragment length polymorphic DNA are described and proposed for increasing use in the future.

  4. Chemical Sciences Division annual report 1994

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    The division is one of ten LBL research divisions. It is composed of individual research groups organized into 5 scientific areas: chemical physics, inorganic/organometallic chemistry, actinide chemistry, atomic physics, and chemical engineering. Studies include structure and reactivity of critical reaction intermediates, transients and dynamics of elementary chemical reactions, and heterogeneous and homogeneous catalysis. Work for others included studies of superconducting properties of high-{Tc} oxides. In FY 1994, the division neared completion of two end-stations and a beamline for the Advanced Light Source, which will be used for combustion and other studies. This document presents summaries of the studies.

  5. Earth Sciences Division collected abstracts: 1979

    SciTech Connect (OSTI)

    Henry, A.L.; Schwartz, L.L.

    1980-04-30T23:59:59.000Z

    This report is a compilation of abstracts of papers, internal reports, and talks presented during 1979 at national and international meetings by members of the Earth Sciences Division, Lawrence Livermore Laboratory. The arrangement is alphabetical (by author). For a given report, a bibliographic reference appears under the name of each coauthor, but the abstract iself is given only under the name of the first author or the first Earth Sciences Division author. A topical index at the end of the report provides useful cross references, while indicating major areas of research interest in the Earth Sciences Division.

  6. Physics Division annual report 2004.

    SciTech Connect (OSTI)

    Glover, J.

    2006-04-06T23:59:59.000Z

    This report highlights the research performed in 2004 in the Physics Division of Argonne National Laboratory. The Division's programs include operation of ATLAS as a national user facility, nuclear structure and reaction research, nuclear theory, medium energy nuclear research and accelerator research and development. The intellectual challenges of this research represent some of the most fundamental challenges in modern science, shaping our understanding of both tiny objects at the center of the atom and some of the largest structures in the universe. A great strength of these efforts is the critical interplay of theory and experiment. Notable results in research at ATLAS include a measurement of the charge radius of He-6 in an atom trap and its explanation in ab-initio calculations of nuclear structure. Precise mass measurements on critical waiting point nuclei in the rapid-proton-capture process set the time scale for this important path in nucleosynthesis. An abrupt fall-off was identified in the subbarrier fusion of several heavy-ion systems. ATLAS operated for 5559 hours of research in FY2004 while achieving 96% efficiency of beam delivery for experiments. In Medium Energy Physics, substantial progress was made on a long-term experiment to search for the violation of time-reversal invariance using trapped Ra atoms. New results from HERMES reveal the influence of quark angular momentum. Experiments at JLAB search for evidence of color transparency in rho-meson production and study the EMC effect in helium isotopes. New theoretical results include a Poincare covariant description of baryons as composites of confined quarks and non-point-like diquarks. Green's function Monte Carlo techniques give accurate descriptions of the excited states of light nuclei and these techniques been extended to scattering states for astrophysics studies. A theoretical description of the phenomena of proton radioactivity has been extended to triaxial nuclei. Argonne continues to lead in the development and exploitation of the new technical concepts that will truly make RIA, in the words of NSAC, ''the world-leading facility for research in nuclear structure and nuclear astrophysics''. The performance standards for new classes of superconducting cavities continue to increase. Driver linac transients and faults have been analyzed to understand reliability issues and failure modes. Liquid-lithium targets were shown to successfully survive the full-power deposition of a RIA beam. Our science and our technology continue to point the way to this major advance. It is a tremendously exciting time in science for RIA holds the keys to unlocking important secrets of nature. The work described here shows how far we have come and makes it clear we know the path to meet these intellectual challenges. The great progress that has been made in meeting the exciting intellectual challenges of modern nuclear physics reflects the talents and dedication of the Physics Division staff and the visitors, guests and students who bring so much to the research.

  7. Safeguards and security concept for the Secure Automated Fabrication (SAF) and Liquid Metal Reactor (LMR) fuel cycle, SAF line technical support

    SciTech Connect (OSTI)

    Schaubert, V.J.; Remley, M.E.; Grantham, L.F.

    1986-02-21T23:59:59.000Z

    This report is a safeguards and security concept system review for the secure automated fabrication (SAF) and national liquid metal reactor (LMR) fuel programs.

  8. Fissile Flow and Enrichment Monitor for GCEP Advanced Safeguards Application

    SciTech Connect (OSTI)

    March-Leuba, Jose A [ORNL] [ORNL; Uckan, Taner [ORNL] [ORNL

    2010-01-01T23:59:59.000Z

    This paper presents experimental data that demonstrate a concept for a {sup 235}U flow and enrichment monitor (FEMO) based on passive measurements of process equipment in gaseous centrifuge enrichment plants (GCEPs). The primary goal of the FEMO is to prevent, without using pipe penetrations or active interrogation with external sources, the production and diversion of undeclared nuclear material. This FEMO concept utilizes: (1) calibrated measurements of {sup 235}U density in cascade headers, and (2) measurements of pump inlet pressure and volumetric flow rate, which are correlated to the electrical power consumed by the GCEP pumps that transport UF{sub 6} from the cascade to the condensation cylinders. The {sup 235}U density is measured by counting 186 keV emissions using a NaI gamma detector located upstream of the pump. The pump inlet pressure and volumetric flow rate are determined using a correlation that is a function of the measured pump operational parameters (e.g., electric power consumption and rotational frequency) and the pumping configuration. The concept has been demonstrated in a low-pressure flow loop at Oak Ridge National Laboratory.

  9. Chemistry-nuclear chemistry division. Progress report, October 1979-September 1980

    SciTech Connect (OSTI)

    Ryan, R.R. (comp.)

    1981-05-01T23:59:59.000Z

    This report presents the research and development programs pursued by the Chemistry-Nuclear Chemistry Division of the Los Alamos National Laboratory. Topics covered include advanced analytical methods, atmospheric chemistry and transport, biochemistry, biomedical research, element migration and fixation, inorganic chemistry, isotope separation and analysis, atomic and molecular collisions, molecular spectroscopy, muonic x rays, nuclear cosmochemistry, nuclear structure and reactions, radiochemical separations, theoretical chemistry, and unclassified weapons research.

  10. Physics division annual report 1999

    SciTech Connect (OSTI)

    Thayer, K., ed.; Physics

    2000-12-06T23:59:59.000Z

    This report summarizes the research performed in the past year in the Argonne Physics Division. The Division's programs include operation of ATLAS as a national heavy-ion user facility, nuclear structure and reaction research with beams of heavy ions, accelerator research and development especially in superconducting radio frequency technology, nuclear theory and medium energy nuclear physics. The Division took significant strides forward in its science and its initiatives for the future in the past year. Major progress was made in developing the concept and the technology for the future advanced facility of beams of short-lived nuclei, the Rare Isotope Accelerator. The scientific program capitalized on important instrumentation initiatives with key advances in nuclear science. In 1999, the nuclear science community adopted the Argonne concept for a multi-beam superconducting linear accelerator driver as the design of choice for the next major facility in the field a Rare Isotope Accelerator (WA) as recommended by the Nuclear Science Advisory Committee's 1996 Long Range Plan. Argonne has made significant R&D progress on almost all aspects of the design concept including the fast gas catcher (to allow fast fragmentation beams to be stopped and reaccelerated) that in large part defined the RIA concept the superconducting rf technology for the driver accelerator, the multiple-charge-state concept (to permit the facility to meet the design intensity goals with existing ion-source technology), and designs and tests of high-power target concepts to effectively deal with the full beam power of the driver linac. An NSAC subcommittee recommended the Argonne concept and set as tie design goal Uranium beams of 100-kwatt power at 400 MeV/u. Argonne demonstrated that this goal can be met with an innovative, but technically in-hand, design. The heavy-ion research program focused on GammaSphere, the premier facility for nuclear structure gamma-ray studies. One example of the ground-breaking research with Garnmasphere was the first study of the limits of stability with angular momentum in the shell stabilized nobelium isotopes. It was found that these heaviest nuclei could be formed at surprisingly high angular momentum, providing important new insight into the production mechanisms for super-heavy elements. Another focus continues to be experiments with short-lived beams for critical nuclear astrophysics applications. Measurements revealed that {sup 44}Ti is more readily destroyed in supernovae than was expected. Major progress was made in collecting and storing unstable ions in the Canadian Penning Trap. The technique of stopping and rapidly extracting ions from a helium gas cell led directly to the new paradigm in the production of rare isotope beams that became RIA. ATLAS provided a record 6046 hours of beam use for experiments in FY99. The facility pressed hard to support the heavy demands of the GammaSphere Research program but maintained an operational reliability of 93%. Of the 29 different isotopes provided as beams in FY99, radioactive beams of {sup 44}Ti and {sup 17}F comprised 6% of the beam time. The theoretical efforts in the Division made dramatic new strides in such topics as quantum Monte Carlo calculations of light nuclei to understand microscopic many-body forces in nuclei; QCD calculations based on the Dyson-Schwinger approach which were extended to baryon systems and finite temperatures and densities; the structure of heavy nuclei; and proton decay modes of nuclei far from stability. The medium-energy program continues to focus on new techniques to understand how the quark-gluon structure of matter impacts the structure of nuclei. The HERMES experiment began making measurements of the fraction of the spin of the nucleon carried by the glue. Drell-Yan experiments study the flavor composition of the sea of the proton. Experiments at Jefferson lab search for clues of QCD dynamics at the hadronic level. A major advance in trace isotope analysis was realized with pioneering work on Atom Trap Trace Analysis, exploitin

  11. Financial Services Division of Administration & Finance

    E-Print Network [OSTI]

    de Lijser, Peter

    Financial Services Division of Administration & Finance (657) 278-2512 / Fax (714) 278: May Wong / Financial Services (CP-300). Instructions are at Questions? Email Directive11@fullerton.eduwww.finance

  12. Export Controls Compliance Division of Research

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    Export Controls Compliance Division of Research of this document is to provide overall guidance on export control regulations and internal procedures information contained in their Export Control Compliance programs in the development of this document. #12

  13. EARTH SCIENCES DIVISION ANNUAL REPORT 1978

    E-Print Network [OSTI]

    Authors, Various

    2012-01-01T23:59:59.000Z

    of electrolytes: IX, rare earth chlorides, nitrates, andU E OF AQUIFER RESPONSE TO EARTH TIDES AS A MEANS O F SLawrence Berkeley Laboratory, Earth Sciences Division, 1977.

  14. EARTH SCIENCES DIVISION ANNUAL REPORT 1978

    E-Print Network [OSTI]

    Authors, Various

    2012-01-01T23:59:59.000Z

    of Energy's Division of Geothermal Energy has undertaken aand Ghormley, E. L. , 1976. Geothermal energy conversion andi a , Mexico, i n Geothermal energy: a n o v e l t y becomes

  15. Community Development Department Building & Safety Division

    E-Print Network [OSTI]

    BUILDING, RESIDENTIAL AND GREEN BUILDING CODES, AMENDING FREMONT MUNICIPAL CODE TITLE vn (BUILDING TO ENERGY REGULATIONS THE 2010 CALIFORNIA,GREEN BUILDING CODE The City of Fremont proposed to adopt local................ Community Development Department Building & Safety Division 39550 Liberty Street

  16. Energy Research and Development Division STAFF REPORT

    E-Print Network [OSTI]

    Energy Research and Development Division STAFF REPORT NATURAL GAS RESEARCH AND DEVELOPMENT 2013 Annual Report CALIFORNIA ENERGY COMMISSION Edmund G. Brown Jr., Governor OCTOBER 2013 CEC5002013111 #12; CALIFORNIA ENERGY COMMISSION Linda Schrupp Primary Authors Prepared for: California

  17. Argonne National Decision and Information Sciences Division

    E-Print Network [OSTI]

    Argonne National Laboratory Decision and Information Sciences Division Introducing EMTools conforms to expecta- tions. Argonne National Laboratory, developer of the successful Synchronization Matrix and exercise tool: EMTools. EMTools integrates the func- tionality of Argonne's previous-generation emergency

  18. Acquisition Notice Posting Headquarters Acquisition Division

    E-Print Network [OSTI]

    Christian, Eric

    the technology readiness of the selected systems, provide tangible, innovative technology products, are cost CROSSCUTTING CAPABILITY DEMONSTRATIONS DIVISION TECHNOLOGY DEMONSTRATION MISSIONS PROGRAM General Information, NASA plans to begin the Technology Demonstrations Missions Program. One of the greatest challenges

  19. Materials Sciences Division Integrated Safety Management Plan

    E-Print Network [OSTI]

    Materials Sciences Division Integrated Safety Management Plan Revised: February 9, 2012 Prepared by: signed Feb. 9, 2012 Rick Kelly, Facility/EH&S Manager Submitted by: signed Feb. 9, 2012 Miquel Salmeron.1 RESPONSIBILITY AND AUTHORITY THROUGH LINE MANAGEMENT............................................................5

  20. UNIVERSITY OF CALIFORNIA, SANTA CRUZ DIVISION OF GRADUATE STUDIES

    E-Print Network [OSTI]

    California at Santa Cruz, University of

    and Graduate Division coordination of efforts to increase graduate support and postdoctoral placement through

  1. NO. REV. NO. Systems Division DATE

    E-Print Network [OSTI]

    Rathbun, Julie A.

    -~ NO. REV. NO. EATM-15 PAGE OF ~ Systems Division DATE EASEP /PSEP Solar Panel Development Design+"'--.:L'_;;;J....;::::::..··-=·~::!!:!!!e::...._ K. Hsi #12;NO. REV. NO. EATM-15 EASEP/PSEP Solar Panel Development ~ Systems Division Design of the EASE-PSEP Solar Panel Array~PA::G:,:E:..::=l=~o:F~=2=7= DATE 20 Nov. 1968 1. 0 SUMMARY Electrical power

  2. Earth Sciences Division annual report 1989

    SciTech Connect (OSTI)

    Not Available

    1990-06-01T23:59:59.000Z

    This Annual Report presents summaries of selected representative research activities from Lawrence Berkeley Laboratory grouped according to the principal disciplines of the Earth Sciences Division: Reservoir Engineering and Hydrology, Geology and Geochemistry, and Geophysics and Geomechanics. We are proud to be able to bring you this report, which we hope will convey not only a description of the Division's scientific activities but also a sense of the enthusiasm and excitement present today in the Earth Sciences.

  3. Weapons Experiments Division Explosives Operations Overview

    SciTech Connect (OSTI)

    Laintz, Kenneth E. [Los Alamos National Laboratory

    2012-06-19T23:59:59.000Z

    Presentation covers WX Division programmatic operations with a focus on JOWOG-9 interests. A brief look at DARHT is followed by a high level overview of explosives research activities currently being conducted within in the experimental groups of WX-Division. Presentation covers more emphasis of activities and facilities at TA-9 as these efforts have been more traditionally aligned with ongoing collaborative explosive exchanges covered under JOWOG-9.

  4. Earth Sciences Division collected abstracts: 1980

    SciTech Connect (OSTI)

    Henry, A.L.; Hornady, B.F. (eds.)

    1981-10-15T23:59:59.000Z

    This report is a compilation of abstracts of papers, reports, and talks presented during 1980 at national and international meetings by members of the Earth Sciences Division, Lawrence Livermore National Laboratory. The arrangement is alphabetical (by author). For a given report, a bibliographic reference appears under the name of each coauthor, but the abstract itself is given only under the name of the first author (indicated in capital letters) or the first Earth Sciences Division author.

  5. Biology Division progress report, October 1, 1991--September 30, 1993

    SciTech Connect (OSTI)

    Hartman, F.C.; Cook, J.S.

    1993-10-01T23:59:59.000Z

    This Progress Report summarizes the research endeavors of the Biology Division of the Oak Ridge National Laboratory during the period October 1, 1991, through September 30, 1993. The report is structured to provide descriptions of current activities and accomplishments in each of the Division`s major organizational units. Lists of information to convey the entire scope of the Division`s activities are compiled at the end of the report.

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

    SciTech Connect (OSTI)

    Not Available

    1981-05-01T23:59:59.000Z

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

  7. ENERGY & ENVIRONMENT DIVISION. ANNUAL REPORT FY 1980

    E-Print Network [OSTI]

    Authors, Various

    2010-01-01T23:59:59.000Z

    consumption capita industrial capita transportation capita coal capita petroleum capita natural gas capita electricity Government

  8. The History of Metals and Ceramics Division

    SciTech Connect (OSTI)

    Craig, D.F.

    1999-01-01T23:59:59.000Z

    The division was formed in 1946 at the suggestion of Dr. Eugene P. Wigner to attack the problem of the distortion of graphite in the early reactors due to exposure to reactor neutrons, and the consequent radiation damage. It was called the Metallurgy Division and assembled the metallurgical and solid state physics activities of the time which were not directly related to nuclear weapons production. William A. Johnson, a Westinghouse employee, was named Division Director in 1946. In 1949 he was replaced by John H Frye Jr. when the Division consisted of 45 people. He was director during most of what is called the Reactor Project Years until 1973 and his retirement. During this period the Division evolved into three organizational areas: basic research, applied research in nuclear reactor materials, and reactor programs directly related to a specific reactor(s) being designed or built. The Division (Metals and Ceramics) consisted of 204 staff members in 1973 when James R. Weir, Jr., became Director. This was the period of the oil embargo, the formation of the Energy Research and Development Administration (ERDA) by combining the Atomic Energy Commission (AEC) with the Office of Coal Research, and subsequent formation of the Department of Energy (DOE). The diversification process continued when James O. Stiegler became Director in 1984, partially as a result of the pressure of legislation encouraging the national laboratories to work with U.S. industries on their problems. During that time the Division staff grew from 265 to 330. Douglas F. Craig became Director in 1992.

  9. North Atlantic DivisionNorth Atlantic Division SuperstormSuperstorm SandySandy

    E-Print Network [OSTI]

    US Army Corps of Engineers

    North Atlantic DivisionNorth Atlantic Division SuperstormSuperstorm SandySandy Dredging Industry BriefDredging Industry BriefDredging Industry BriefDredging Industry Brief 3 April 20133 April 2013 #12;NAD Sandy Dredging BriefNAD Sandy Dredging Brief · Purposep · Goals · Sandy Program Overview

  10. SHR Service Team: Academic Divisions -Contact Matrix Primary Contact by Unit/Division

    E-Print Network [OSTI]

    California at Santa Cruz, University of

    SHR Service Team: Academic Divisions - Contact Matrix Primary Contact by Unit/Division Astronomy Consultation Dawn Harker Teresa Roffe Barbara Lorimer Last Revised: 07/07/2010 Mail Stop: SHR-Service Teams Fax: 831-459-2661 1 of 2 #12;SHR Operations Services Team One SHR Partner Services Senior Manager, SHR

  11. Division of Student Life 20122013 ANNUAL REPORT Division of Student Life

    E-Print Network [OSTI]

    1 Division of Student Life 2012­2013 ANNUAL REPORT Division of Student Life #12;2 The Power to Transform: Expectations of Our Students At UW­Madison, we know that the Wisconsin Experience has learning inside and outside the classroom to make the world a better place?" In the eight departments

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

    SciTech Connect (OSTI)

    Santi, Peter A [Los Alamos National Laboratory; Demuth, Scott F [Los Alamos National Laboratory; Klasky, Kristen L [Los Alamos National Laboratory; Lee, Haeok [Los Alamos National Laboratory; Miller, Michael C [Los Alamos National Laboratory; Sprinkle, James K [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Williams, Bradley [DOE, NE

    2009-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Humberto Garcia; Wen-Chiao Lin; Reed Carlson

    2014-07-01T23:59:59.000Z

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

  14. High-resolution microcalorimeter detectors as a tool in the future of nuclear safeguards

    SciTech Connect (OSTI)

    Hoteling, Nathan J [Los Alamos National Laboratory; Hoover, Andrew S [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    New measurements are presented from the LANL-NIST microcalorimeter array for two standard plutonium sources. The results demonstrate substantially smaller error bars obtained from the spectral analysis program FRAM. Some areas of improvement to the analysis technique have been identified, indicating that the micro calorimeter results can be improved upon. These results support the viability of a device for performing real nuclear safeguards measurements in the near future. The challenge of providing reliably accurate and precise data is a critical component of any safeguards initiative. In the realm of nuclear safeguards, this is an especially daunting task since inaccurate and/or imprecise data could have very serious international consequences. As such, there is a constant drive within the community to establish better measurement and analysis techniques in order to further reduce the associated errors and uncertainties. Even with todays state of the art equipment, measurement uncertainties can extend to several significant quantities worth of material over a relatively modest period of time. Furthermore, there is a strong desire for improved nondestructive analysis techniques in order to reduce both the cost, turnover rate, and inconvenience of destructive analyses. One promising new technology that may help to realize these goals is that of gamma-ray microcalorimeter detectors. The hallmark quality of this new technique is the ability to achieve energy resolution nearly an order of magnitude better than typical planar high-purity germanium (HPGe) detectors. Such an improvement may help reduce uncertainties associated with, for instance, plutonium isotopics or uranium enrichment measurements. This may, in turn, help to reduce uncertainties in total plutonium and/or uranium content in a given sample without the need for destructive analysis. In this paper, we will describe this new detector technology as well as some recent measurements carried out with the LANL-NIST gamma-ray microcalorimeter ({micro}cal) array. Discussion will focus on the capabilities of this technology as well as the progress toward a practical measurement device.

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

    SciTech Connect (OSTI)

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

    2012-10-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Ivan R. Thomas

    2010-07-01T23:59:59.000Z

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

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

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron4(SC) Mapping the ImpactSC Correspondence Control CenterSafeguards

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysis and Feedback onWorkingIAEA Safeguards

  19. Computational Transportation

    E-Print Network [OSTI]

    Illinois at Chicago, University of

    ), in-vehicle computers, and computers in the transportation infrastructure are integrated ride- sharing, real-time multi-modal routing and navigation, to autonomous/assisted driving

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

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

    1998-06-12T23:59:59.000Z

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

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

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

    1998-06-12T23:59:59.000Z

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

  2. Energy Division annual progress report for period ending September 30, 1988: Volume 2

    SciTech Connect (OSTI)

    Not Available

    1989-06-01T23:59:59.000Z

    The goals and accomplishments of the Energy Division of Oak Ridge National Laboratory are described in this annual progress report for Fiscal Year (FY) 1988. The Energy Division is a multidisciplinary research organization committed to (1) increasing the knowledge and understanding of the way society makes choices in energy use and energy-using technologies, (2) improving society's understanding of the environmental implications of changes in energy technology, and (3) improving and developing new energy-efficient technologies. The Energy Division's programmatic activities focus on four major areas: (1) analysis and assessment, (2) transportation and decision systems research, (3) technology research and development for improving the efficiency of energy and end-use technologies, and (4) electric power systems. The Division's total expenditures in FY 1988 were $44.3 million. The work is supported by the US Department of Energy, US Department of Defense, many other federal agencies, and some private organizations. Disciplines of the 139 staff members include engineering, social sciences, physical and life sciences, and mathematics and statistics.

  3. Life Sciences Division annual report, 1988

    SciTech Connect (OSTI)

    Marrone, B.L.; Cram, L.S. (comps.)

    1989-04-01T23:59:59.000Z

    This report summarizes the research and development activities of Los Alamos National Laboratory's Life Sciences Division for the calendar year 1988. Technical reports related to the current status of projects are presented in sufficient detail to permit the informed reader to assess their scope and significance. Summaries useful to the casual reader desiring general information have been prepared by the Group Leaders and appear in each group overview. Investigators on the staff of the Life Sciences Division will be pleased to provide further information.

  4. Demonstration of safeguards technology at the Russian Institute of Experimental Physics (VNIIEF), Arzamas-16

    SciTech Connect (OSTI)

    Yuferev, V.; Skripka, G.; Augustson, R.H. [and others

    1995-09-01T23:59:59.000Z

    As part of the US-Russian Lab-to-Lab program for strengthening nuclear material protection, control, and accounting (MPC&A), a testbed facility has been established in a laboratory of the VNIIEF to demonstrate safeguards technology to nuclear facility operators. The design of the testbed MPC&A system provides the functions of nondestructive measurements for plutonium and highly enriched uranium, item control, personnel access control, radiation portal monitoring, search equipment, and computerized on-line accounting. The system controls, monitors, and accounts for nuclear material and people as the material moves through three MBAs. It also assists with physical inventory taking. A total of 39 instruments and control systems are being demonstrated in the present version of the testbed. Of these, about half are of Russian design and fabrication, including the software for the item monitoring and the accounting systems. These two computer systems are on an ethernet network and connected in a client-server local area architecture. The item monitoring system is integrated with the accounting system, providing alarm and status information to a central dispatcher terminal. The operation of the MPC&A testbed has been demonstrated under routine and alarm conditions in collaboration with safeguards staff from the six participating US national labs. Workshops and training for Russian nuclear facility operators are in progress. As needs for additional MPC&A technology at specific plants are identified, these are incorporated into the testbed and used to certify the hardware and software for implementation at the plant.

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

    SciTech Connect (OSTI)

    Diaz,R.A.

    2008-06-13T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2013-08-12T23:59:59.000Z

    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.

  7. Implementation of safeguards and security for fissile materials disposition reactor alternative facilities

    SciTech Connect (OSTI)

    Jaeger, C.D.; Duggan, R.A.; Tolk, K.M.

    1995-10-01T23:59:59.000Z

    A number of different disposition alternatives are being considered and include facilities which provide for long-ten-n and interim storage, convert and stabilize fissile materials for other disposition alternatives, immobilize fissile material in glass and/or ceramic material, fabricate fissile material into mixed oxide (MOX) fuel for reactors, use reactor based technologies to convert material into spent fuel, and dispose of fissile material using a number of geologic alternatives. Particular attention will be given to the reactor alternatives which include existing, partially completed, advanced or evolutionary LWRs and CANDU reactors. The various reactor alternatives are all very similar and include processing which converts Pu to a usable form for fuel fabrication, a MOX fuel fab facility located in either the US or in Europe, US LWRs or the CANDU reactors and ultimate disposal of spent fuel in a geologic repository. This paper focuses on how the objectives of reducing security risks and strengthening arms reduction and nonproliferation will be accomplished and the possible impacts of meeting these objectives on facility operations and design. Some of the areas in this paper include: (1) domestic and international safeguards requirements, (2) non-proliferation criteria and measures, (3) the threat, and (4) potential proliferation risks, the impacts on the facilities, and safeguards and security issues unique to the presence of Category 1 or strategic special nuclear material.

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

    SciTech Connect (OSTI)

    Goodman, David I [Univ. of Michigan, Ann Arbor, MI (United States); Rowland, Kelly L [Univ. of California, Berkeley, CA (United States); Smith, Sheriden [Colorado State Univ., Fort Collins, CO (United States); Miller, Karen A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Flynn, Eric B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-10T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2009-01-01T23:59:59.000Z

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

  10. Transportation Market Distortions

    E-Print Network [OSTI]

    Litman, Todd

    2006-01-01T23:59:59.000Z

    of Highways, Volpe National Transportation Systems Center (Evaluating Criticism of Transportation Costing, VictoriaFrom Here: Evaluating Transportation Diversity, Victoria

  11. Transportation Energy Data Book: Edition 32, from the Center for Transportation Analysis (CTA)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Davis, Stacy C.; Diegel, Susan W.; Boundy, Robert G. [Roltek, Inc.

    The Transportation Energy Data Book: Edition 32 is a statistical compendium designed for use as a reference. The data book represents an assembly and display of statistics and information that characterize transportation activity, and presents data on other factors that influence transportation energy use. This edition of the Data Book has 12 chapters which focus on various aspects of the transportation industry. Chapter 1 focuses on petroleum; Chapter 2 on energy; Chapter 3 0n highway vehicles; Chapter 4 on light vehicles; Chapter 5 on heavy vehicles; Chapter 6 on alternative fuel vehicles; Chapter 7on fleet vehicles; Chapter 8 on household vehicles; and Chapter 9 on nonhighway modes; Chapter 10 on transportation and the economy; Chapter 11 on greenhouse gas emissions; and Chapter 12 on criteria pollutant emissions. The sources used represent the latest available data. There are also appendices which include detailed source information for various tables, measures of conversion, and the definition of Census divisions and regions.

  12. Highway and interline transportation routing models

    SciTech Connect (OSTI)

    Joy, D.S.; Johnson, P.E.

    1994-06-01T23:59:59.000Z

    The potential impacts associated with the transportation of hazardous materials are important issues to shippers, carriers, and the general public. Since transportation routes are a central characteristic in most of these issues, the prediction of likely routes is the first step toward the resolution of these issues. In addition, US Department of Transportation requirements (HM-164) mandate specific routes for shipments of highway controlled quantities of radioactive materials. In response to these needs, two routing models have been developed at Oak Ridge National Laboratory under the sponsorship of the U.S. Department of Energy (DOE). These models have been designated by DOE`s Office of Environmental Restoration and Waste Management, Transportation Management Division (DOE/EM) as the official DOE routing models. Both models, HIGHWAY and INTERLINE, are described.

  13. Department of Natural Resources and Water Divisions (Nebraska)

    Broader source: Energy.gov [DOE]

    This chapter describes the duties of the Department of Natural Resources and divides the state into two water divisions for administrative purposes. Water Division 1 consists of all the lands of...

  14. Nuclear Science Division Annual Report 1995-1996

    E-Print Network [OSTI]

    Authors, Various

    2010-01-01T23:59:59.000Z

    Saladin5, and C.H. Yu6 Nuclear Science Division, LawrenceMoretto, G.J. Wozniak, Nuclear Science Division, LawrenceComment on “Probing the Nuclear Liquid-Gas Phase Transition”

  15. Engineering Research Division publication report, calendar year 1980

    SciTech Connect (OSTI)

    Miller, E.K.; Livingston, P.L.; Rae, D.C. (eds.)

    1980-06-01T23:59:59.000Z

    Each year the Engineering Research Division of the Electronics Engineering Department at Lawrence Livermore Laboratory has issued an internal report listing all formal publications produced by the Division during the calendar year. Abstracts of 1980 reports are presented.

  16. Linking Sulfur Metabolism to the Cell Division Machinery in Yeast

    E-Print Network [OSTI]

    Blank, Heidi M.

    2010-07-14T23:59:59.000Z

    The longstanding view has been that metabolism allows for cell division to take place, but that metabolic processes do not actively promote cell division. I have recently challenged this notion by identifying a unique gain-of-function metabolic...

  17. Mesoscale & Microscale Meteorological Division / NCAR WRF Nature Run

    E-Print Network [OSTI]

    Michalakes, John

    Mesoscale & Microscale Meteorological Division / NCAR WRF Nature Run John Michalakes Josh Hacker overview and petascale issues Nature run methodology Results and conclusion #12;Mesoscale & Microscale's atmosphere #12;Mesoscale & Microscale Meteorological Division / NCAR Description of Science · Kinetic energy

  18. The mechanism of chloroplast division in higher plants

    E-Print Network [OSTI]

    Proctor, John Michael

    2013-02-22T23:59:59.000Z

    of chloroplasts found in a normal mesophyll cell. The process of chloroplast biogenesis has been well characterized at the cellular level, but the molecular basis of chloroplast division and the role of nuclear genes in the control of plastid division...

  19. Distributing the Cost of Securing a Transportation Infrastructure

    E-Print Network [OSTI]

    Chawathe, Sudarshan S.

    on such division of costs has been the topic of much political controversy and threatens to derail initiatives new regulations. However, there are also indirect costs such as noise, pollution, and dangerDistributing the Cost of Securing a Transportation Infrastructure Sudarshan S. Chawathe Computer

  20. ENVIRONMENT, SAFETY & HEALTH DIVISION Chapter 24: Training

    E-Print Network [OSTI]

    Wechsler, Risa H.

    ENVIRONMENT, SAFETY & HEALTH DIVISION Chapter 24: Training Quick Start Summary Product ID: 520-group.slac.stanford.edu/esh/eshmanual/references/trainingQuickstart.pdf 1 Who needs to know about these requirements The requirements of Training apply to all persons on-site, employees and non-employees, their SLAC

  1. West Virginia University Division of Human Resources

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    Resources Web page hr.wvu.edu. In the event of a conflict between the current posted version and this printed copy, the posted version on the Web page is controlling. Page 1 of 9 Family Medical Leave Act Division of Human Resources Web page hr.wvu.edu. In the event of a conflict between the current posted

  2. Building an R package Division of Biostatistics

    E-Print Network [OSTI]

    Carlin, Bradley P.

    Building an R package Yen-Yi Ho Division of Biostatistics School of Public Health, University of Minnesota Yen-Yi Ho Building an R package #12;Steps Prepare your functions, example data sets Build package in man subdirectory) Write a package vignette Build and install the R package (R CMD build) Check the R

  3. Mentor Program Information Division of Biology

    E-Print Network [OSTI]

    Kaufman, Glennis A.

    Mentor Program Information Division of Biology 116 Ackert Hall Manhattan, KS 66506 Kansas State will never be released for public information unless requested by the mentor. It is used only if a current K-State student requests to speak with a specific mentor and is kept private until that time. However, it may

  4. Physics Division activities report, 1986--1987

    SciTech Connect (OSTI)

    Not Available

    1987-01-01T23:59:59.000Z

    This report summarizes the research activities of the Physics Division for the years 1986 and 1987. Areas of research discussed in this paper are: research on e/sup +/e/sup /minus// interactions; research on p/bar p/ interactions; experiment at TRIUMF; double beta decay; high energy astrophysics; interdisciplinary research; and advanced technology development and the SSC.

  5. University of Massachusetts Physical Plant Division

    E-Print Network [OSTI]

    Mountziaris, T. J.

    with all applicable rules and regulations. As of the date of this policy, the University of Massachusetts1 University of Massachusetts Amherst Physical Plant Division March 26, 2007 From: Pat Daly. To this end, the Property Office of the University of Massachusetts Amherst shall provide the Physical Plant

  6. DANE TECHNICAL NOTE INFN -LNF, Accelerator Division

    E-Print Network [OSTI]

    Istituto Nazionale di Fisica Nucleare (INFN)

    (Chairman) F. Willeke, DESY 1. Follow up of previous Meeting The first report by the DANE Machine AdvisoryK K DANE TECHNICAL NOTE INFN - LNF, Accelerator Division Frascati, May 11, 2000 Note: G-55 Report by DANE Machine Advisory Panel on 2nd Meeting held on 4-5 May 2000 J. M. Jowett, CERN S. Myers, CERN

  7. Materials Sciences Division 1990 annual report

    SciTech Connect (OSTI)

    Not Available

    1990-01-01T23:59:59.000Z

    This report is the Materials Sciences Division's annual report. It contains abstracts describing materials research at the National Center for Electron Microscopy, and for research groups in metallurgy, solid-state physics, materials chemistry, electrochemical energy storage, electronic materials, surface science and catalysis, ceramic science, high tc superconductivity, polymers, composites, and high performance metals.

  8. Lectures on Linear Algebra over Division Ring

    E-Print Network [OSTI]

    Aleks Kleyn

    2014-10-11T23:59:59.000Z

    In this book i treat linear algebra over division ring. A system of linear equations over a division ring has properties similar to properties of a system of linear equations over a field. However, noncommutativity of a product creates a new picture. Matrices allow two products linked by transpose. Biring is algebra which defines on the set two correlated structures of the ring. As in the commutative case, solutions of a system of linear equations build up right or left vector space depending on type of system. We study vector spaces together with the system of linear equations because their properties have a close relationship. As in a commutative case, the group of automorphisms of a vector space has a single transitive representation on a frame manifold. This gives us an opportunity to introduce passive and active representations. Studying a vector space over a division ring uncovers new details in the relationship between passive and active transformations, makes this picture clearer. Considering of twin representations of division ring in Abelian group leads to the concept of D vector space and their linear map. Based on polyadditive map I considered definition of tensor product of rings and tensor product of D vector spaces.

  9. Student Regulations and Procedures Academic Division

    E-Print Network [OSTI]

    Student Regulations and Procedures Academic Division 2007/2008 11 Students Union Code information regarding their course, tuition fees, award ceremonies and other matters www.mmu.ac.uk/academic's Articles of Government (Article 1.1). As prescribed in the Articles of Government (Article 12

  10. Student Regulations and Procedures Academic Division

    E-Print Network [OSTI]

    Student Regulations and Procedures Academic Division 2007/2008 3 RULES FOR STUDENT CONDUCT fees, award ceremonies and other matters www.mmu.ac.uk/academic/student_regulations.php #12;RULES of Governors in accordance with the following Articles of Government: 7.1.6 Subject to the responsibilities

  11. Division of Human Resources Termination Of

    E-Print Network [OSTI]

    Meyers, Steven D.

    Division of Human Resources Termination Of Domestic Partnership Health Stipend Questions (813) 974 Insurance Stipend will terminate as of the Effective Date on this Termination of Domestic Partnership Health. ______ The Domestic Partnership Declaration attested to and filed by me with USF shall be and is terminated

  12. Division of Student Affairs 107 Conklin North

    E-Print Network [OSTI]

    Moore, Paul A.

    A. Herman graduated from Bowling Green State University's College Student Personnel program in 1990, August 31st to the Office of the Division of Student Affairs, Bowling Green State University, Attn: Beth Bowling Green State University Shelli A. Herman graduated from Bowling Green State University's College

  13. DIVISION S-6--SOIL & WATER MANAGEMENT & CONSERVATION

    E-Print Network [OSTI]

    DIVISION S-6--SOIL & WATER MANAGEMENT & CONSERVATION Soil Organic Carbon Sequestration Rates soil column within 20 yr following culti- Carbon sequestration rates, with a change from CT to NT, can in approximately 40 to and returning to the original land cover or other peren- 60 yr. Carbon sequestration rates

  14. Ruiying Wu PhD Biosciences Division

    E-Print Network [OSTI]

    Kemner, Ken

    1 Ruiying Wu PhD Biosciences Division BIO-202 Argonne National Laboratory E-mail: rwu@anl.gov 9700 to millimeter wave National Natural Science Foundation of PR China (NSFC) #12;2 Grant # - 39970189 1998 ­ 2000 National Natural Science Foundation of PR China (NSFC) Grant # - 39770633 SELECTIVE HONORS AND AWARDS 1

  15. DANE TECHNICAL NOTE INFN -LNF, Accelerator Division

    E-Print Network [OSTI]

    Istituto Nazionale di Fisica Nucleare (INFN)

    K K DANE TECHNICAL NOTE INFN - LNF, Accelerator Division Frascati, 28 November, 2002 IR-12 together with the total losses around the rings. Results seem encouraging, as calculated loss rates at IR2 in details and compared to calculated losses for the KLOE and the DEAR cases. 1 Introduction Background rates

  16. DANE TECHNICAL NOTE INFN -LNF, Accelerator Division

    E-Print Network [OSTI]

    Istituto Nazionale di Fisica Nucleare (INFN)

    K K DANE TECHNICAL NOTE INFN - LNF, Accelerator Division Frascati, March 10, 1997 Note: BM-1 BUNCH current. This measurement allows to calculate energy losses due to parasitic beam-vacuum chamber losses. In this Note we present results of the measurements and their analysis, comparing the results

  17. DANE TECHNICAL NOTE INFN -LNF, Accelerator Division

    E-Print Network [OSTI]

    Istituto Nazionale di Fisica Nucleare (INFN)

    KKKK KKKK DANE TECHNICAL NOTE INFN - LNF, Accelerator Division Frascati, January 13, 1993 Note: IR to see how much heat has to be removed. The two main sources of heat are: 1) Resistive losses due. Technol. 5(6) 3446 (1987). #12;IR-1 pg. 6 APPENDIX IA Losses in the I.R. 1) Resistive losses in Be: dp dz

  18. DANE TECHNICAL NOTE INFN -LNF, Accelerator Division

    E-Print Network [OSTI]

    Istituto Nazionale di Fisica Nucleare (INFN)

    KKKK KKKK DANE TECHNICAL NOTE INFN - LNF, Accelerator Division Frascati, October 26, 1994 Note: RF enough (i.e. if the parasitic losses are low with respect to the energy left by each passing bunch-zero longitudinal electric field on the cavity axis. Being azimuthally symmetric, it is possible to calculate them

  19. DANE TECHNICAL NOTE INFN -LNF, Accelerator Division

    E-Print Network [OSTI]

    Istituto Nazionale di Fisica Nucleare (INFN)

    K K DANE TECHNICAL NOTE INFN - LNF, Accelerator Division Frascati, July 16, 1996 Note: RF-19 losses and prevents to reach the operating voltage range. The RF cavity of the DANE -Factory Accumulator and electrical conductivities. Multipactoring (MP) is a phenomenon of resonant electron discharge which can occur

  20. DANE TECHNICAL NOTE INFN -LNF, Accelerator Division

    E-Print Network [OSTI]

    Istituto Nazionale di Fisica Nucleare (INFN)

    K K DANE TECHNICAL NOTE INFN - LNF, Accelerator Division Frascati, December 14, 1995 Note: CD-5, are also needed in order to minimise the losses. In order to use this device as a transverse kicker, two) excitation. #12;CD-5 pg. 3 The combined magnetic and electric field gives a net deflecting Lorentz force

  1. DANE TECHNICAL NOTE INFN -LNF, Accelerator Division

    E-Print Network [OSTI]

    Istituto Nazionale di Fisica Nucleare (INFN)

    KKKK KKKK DANE TECHNICAL NOTE INFN - LNF, Accelerator Division Frascati, Sept. 26, 1991 Note: RF-4 and vacuum simpler and less expensive. The cavity will be made of copper which has better electrical and thermal conductivity to reduce the RF losses and keep the cooling easier. #12;RF-4 pg. 2 Multipacting (MP

  2. Division of Human Resources Payroll Certification Process

    E-Print Network [OSTI]

    Meyers, Steven D.

    Division of Human Resources Payroll Certification Process Questions (813) 974-7955 Payroll/Payroll Processing Rev. 04/2010 Payroll Certification is the process by which departments submit to Payroll the hours to be paid for each employee within each department. This process utilizes the online Certification System

  3. INTRAMURAL GOLF TOURAMENT ALL DIVISIONS Fall 2011 Division Sunday Sept. 18

    E-Print Network [OSTI]

    Omiecinski, Curtis

    INTRAMURAL GOLF TOURAMENT ALL DIVISIONS Fall 2011 Division Sunday Sept. 18 GOLF M W Team Member ?? EMAIL Tee-Time FIRST NAME LAST NAME or F TEAM NAME @psu.edu 9:00 AM Matt McTague M last round mim5187 Frankie Kehs M last round fjk5012 Chase Roman M Tiger Wood cer197 Dustin Hartzel M Tiger Wood dnh124 9

  4. TO: HR and Business Contacts FROM: Division of Human Resources

    E-Print Network [OSTI]

    Almor, Amit

    MEMORANDUM TO: HR and Business Contacts FROM: Division of Human Resources DATE: October 25, 2013 RE: Human Resources Fall 2013 Forum The Division of Human Resources will sponsor an HR Forum from 1 to the Division of Human Resources' Organizational and Professional Development Office at hrtrain

  5. TO: HR and Business Contacts FROM: Division of Human Resources

    E-Print Network [OSTI]

    Almor, Amit

    TO: HR and Business Contacts FROM: Division of Human Resources DATE: September 6, 2012 RE: Human Resources Fall 2012 Forum The Division of Human Resources will sponsor an HR Forum from 1-4 p in person or by webinar. Any questions about the forum may be e-mailed to the Division of Human Resources

  6. MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division

    E-Print Network [OSTI]

    Fusion Technology & Engineering Division 1. Costing of 4 "Reference" Options 2. Equalization of TF;MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division Total Cost (M$) vs. A; MMIT Plasma Science and Fusion Center Fusion Technology & Engineering Division J.H. Schultz M

  7. DIVISION OF DRUG ABUSE CONTROL A Project Evaluation

    E-Print Network [OSTI]

    Touretzky, David S.

    L,: . -'" -- . : NARCONON 1/1 DIVISION OF DRUG ABUSE CONTROL FA-48-72 74-007 75-009 A Project. In Relation to the Stated Objectives of the Division of Drug Abuse Control's Application .......... II ........·..··.· Appendix C - NARCONON - Division of Drug Abuse Control Contract ..·.............·..... Appendix D - Job

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

    SciTech Connect (OSTI)

    Middleton, Bobby D.; Mendez, Carmen Margarita [Sociotecnia Solutions] [Sociotecnia Solutions

    2013-10-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Humberto E. Garcia

    2014-07-01T23:59:59.000Z

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

  10. electrifyingthefuture transportation

    E-Print Network [OSTI]

    Birmingham, University of

    electrifyingthefuture transportation The UK Government's carbon reduction strategy vehicles and the new Birmingham Science City Energy Systems Integration Laboratory (ESIL) will further enhance this work. The laboratory - unique within the UK and world leading - brings together cutting edge

  11. Biology Division progress report, October 1, 1993--September 30, 1995

    SciTech Connect (OSTI)

    NONE

    1995-10-01T23:59:59.000Z

    This Progress Report summarizes the research endeavors of the Biology Division of the Oak Ridge National Laboratory during the period October 1, 1993, through September 30, 1995. The report is structured to provide descriptions of current activities and accomplishments in each of the Division`s major organizational units. Lists of information to convey the entire scope of the Division`s activities are compiled at the end of the report. Attention is focused on the following research activities: molecular, cellular, and cancer biology; mammalian genetics and development; genome mapping program; and educational activities.

  12. Strategic analysis for safeguards systems: a feasibility study. Volume 2. Appendix

    SciTech Connect (OSTI)

    Goldman, A J

    1984-12-01T23:59:59.000Z

    This appendix provides detailed information regarding game theory (strategic analysis) and its potential role in safeguards to supplement the main body of this report. In particualr, it includes an extensive, though not comprehensive review of literature on game theory and on other topics that relate to the formulation of a game-theoretic model (e.g. the payoff functions). The appendix describes the basic form and components of game theory models, and the solvability of various models. It then discusses three basic issues related to the use of strategic analysis in material accounting: (1) its understandability; (2) its viability in regulatory settings; and (3) difficulties in the use of mixed strategies. Each of the components of a game theoretic model are then discussed and related to the present context.

  13. Ultra-high-resolution alpha spectrometry for nuclear forensics and safeguards applications

    SciTech Connect (OSTI)

    Bacrania, Minesh K [Los Alamos National Laboratory; Croce, Mark [Los Alamos National Laboratory; Bond, Evelyn [Los Alamos National Laboratory; Dry, Donald [Los Alamos National Laboratory; Moody, W. Allen [Los Alamos National Laboratory; Lamont, Stephen [Los Alamos National Laboratory; Rabin, Michael [Los Alamos National Laboratory; Rim, Jung [Los Alamos National Laboratory; Smith, Audrey [Los Alamos National Laboratory; Beall, James [NIST-BOULDER; Bennett, Douglas [NIST-BOULDER; Kotsubo, Vincent [NIST-BOULDER; Horansky, Robert [NIST-BOULDER; Hilton, Gene [NIST-BOULDER; Schmidt, Daniel [NIST-BOULDER; Ullom, Joel [NIST-BOULDER; Cantor, Robin [STAR CRYOELECTRONICS

    2010-01-01T23:59:59.000Z

    We will present our work on the development of ultra-high-resolution detectors for alpha particle spectrometry. These detectors, based on superconducting transition-edge sensors, offer energy resolution that is five to ten times better than conventional silicon detectors. Using these microcalorimeter detectors, the isotopic composition of mixed-actinide samples can be determined rapidly without the need for actinide separation chemistry to isolate each element, or mass spectrometry to separate isotopic signatures that can not be resolved using traditional alpha spectrometry (e.g. Pu-239/Pu-240, or Pu-238/Am-241). This paper will cover the detector and measurement system, actinide source preparation, and the quantitative isotopic analysis of a number of forensics- and safeguards-relevant radioactive sources.

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

    SciTech Connect (OSTI)

    Suzuki, Mitsutoshi; Mochiji, Toshiro [Department of Science and Technology for Nuclear Material Management, Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1193 (Japan)

    2014-09-30T23:59:59.000Z

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

  15. The ASSESS (Analytic System and Software for Evaluating Safeguards and Security) Outsider module with multiple analyses

    SciTech Connect (OSTI)

    Snell, M.K.; Winblad, A.E. (Sandia National Labs., Albuquerque, NM (USA)); Bingham, B.; Key, B.; Walker, S. (Science and Engineering Associates, Inc., Albuquerque, NM (USA))

    1990-01-01T23:59:59.000Z

    The Analytic System and Software for Evaluating Safeguards and Security (ASSESS) includes modules for analyzing vulnerabilities against outsider and insider adversaries. The ASSESS Outsider Analysis Module has been upgraded to allow for defining, analyzing, and displaying the results of multiple analyses. Once a set of threat definitions have been defined in one Outsider file, they can be readily copied to other Outsider files. This multiple analysis, or batch, mode of operation provides an efficient way of covering the standard DOE outsider threat spectrum. A new approach for coupling the probability of interruption, P(I), values and values calculated by the ASSESS Neutralization module has been implemented in Outsider and is described. An enhanced capability for printing results of these multiple analyses is also included in the upgraded Outside module. 7 refs., 7 figs., 1 tab.

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

    SciTech Connect (OSTI)

    Lee, F.D.

    1995-08-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Gastelum, Zoe N.; Henry, Michael J.

    2013-11-13T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Brian K. Castle; Kelly D. Ellis

    2012-09-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Scherer, Carolynn P [Los Alamos National Laboratory; Long, Jon D [Los Alamos National Laboratory

    2010-09-28T23:59:59.000Z

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

  20. Section III, Division 5 - Development and Future Directions

    SciTech Connect (OSTI)

    D. K. Morton; R I Jetter; James E Nestell; T. D. Burchell; T L (Sam) Sham

    2012-07-01T23:59:59.000Z

    This paper provides commentary on a new division under Section III of the ASME Boiler and Pressure Vessel (BPV) Code. This new Division 5 has an issuance date of November 1, 2011 and is part of the 2011 Addenda to the 2010 Edition of the BPV Code. The new Division covers the rules for the design, fabrication, inspection and testing of components for high temperature nuclear reactors. Information is provided on the scope and need for Division 5, the structure of Division 5, where the rules originated, the various changes made in finalizing Division 5, and the future near-term and long-term expectations for Division 5 development. Portions of this paper were based on Chapter 17 of the Companion Guide to the ASME Boiler & Pressure Vessel Code, Fourth Edition, © ASME, 2012, Reference.