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Sample records for design basis threat

  1. design basis threat | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    design basis threat Design Basis Threat NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special nuclear material, or ...

  2. Design Basis Threat | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Design Basis Threat NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special nuclear material, or SNM) and nuclear weapons in its custody. NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special nuclear material, or SNM) and nuclear weapons in its custody. NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special

  3. design basis threat

    National Nuclear Security Administration (NNSA)

    training courses, and additional full-time instructors.

    • The shift to an "Elite Forces," or Tactical Response Force (TRF) model, to transform NNSA's protective forces...

    • Design Basis Threat Policy (U)

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

      2004-10-01

      This Order is classified and will not be available on the Directives Portal. For distribution, NA employees should contact Jon Todd, 202-586-2579; all other DOE employees should contact Ron Francis, 301-903-6874. Does not cancel other directives.

    • Design Basis Threat Policy (U)

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

      2005-11-29

      This Order is classified and will not be available on the Directives Portal. For distribution, contact John Fitzgibbons, 301-903-1361, john.fitzgibbons@hq.doe.gov. Cancels: DOE O 470.3

    • Beyond Design Basis Events | Department of Energy

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

      Beyond Design Basis Events Beyond Design Basis Events Beyond Design Basis Events Following the March 2011 Fukushima Daiichi nuclear plant accident in Japan, DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to beyond design basis events (BDBEs). These initiatives included issuing Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis, and conducting two DOE nuclear safety workshops. DOE also issued two reports documenting the

    • Beyond Design Basis Event Pilot Evaluations

      Office of Energy Efficiency and Renewable Energy (EERE)

      This document provides Results and Recommendations for Improvements to Enhance Nuclear Safety at Department of Energy Nuclear Facilities based upon Beyond Design Basis Event Pilot Evaluations

    • Office of Nuclear Safety Basis and Facility Design

      Broader source: Energy.gov [DOE]

      The Office of Nuclear Safety Basis & Facility Design establishes safety basis and facility design requirements and expectations related to analysis and design of nuclear facilities to ensure protection of workers and the public from the hazards associated with nuclear operations.

    • Assessing Beyond Design Basis Seismic Events and Implications...

      Office of Environmental Management (EM)

      Defense Nuclear Facilities Safety Board Topics Covered: Department of Energy Approach to Natural Phenomena Hazards Analysis and Design (Seismic) Design Basis and Beyond Design...

    • CRAD, Integrated Safety Basis and Engineering Design Review ...

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

      Integrated Safety Basis and Engineering Design Review - August 20, 2014 (EA CRAD 31-4, Rev. 0) CRAD, Integrated Safety Basis and Engineering Design Review - August 20, 2014 (EA...

    • CRAD, Engineering Design and Safety Basis- December 22, 2009

      Broader source: Energy.gov [DOE]

      Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0)

    • Protocol for Enhanced Evaluations of Beyond Design Basis Events...

      Energy Savers [EERE]

      Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 Protocol for Enhanced Evaluations of Beyond Design ...

    • Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents

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

      2014-12-19

      This Standard describes a framework and the criteria to be used for approval of (1) safety basis documents, as required by 10 Code of Federal Regulation (C.F.R.) 830, Nuclear Safety Management, and (2) safety design basis documents, as required by Department of Energy (DOE) Standard (STD)-1189-2008, Integration of Safety into the Design Process.

    • Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting

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

      Implementation of Operating Experience Report 2013-01 | Department of Energy Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 April, 2013 Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 To support the

    • Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents

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

      SENSITIVE DOE-STD-1104-2014 December 2014 Superseding DOE-STD-1104-2009 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1104-2014 i FOREWORD 1. This Standard describes a framework and the criteria to be used for approval of (1) safety basis documents, as required by 10 Code of Federal Regulation

    • Advanced Test Reactor Design Basis Reconstitution Project Issue Resolution Process

      SciTech Connect (OSTI)

      Steven D. Winter; Gregg L. Sharp; William E. Kohn; Richard T. McCracken

      2007-05-01

      The Advanced Test Reactor (ATR) Design Basis Reconstitution Program (DBRP) is a structured assessment and reconstitution of the design basis for the ATR. The DBRP is designed to establish and document the ties between the Document Safety Analysis (DSA), design basis, and actual system configurations. Where the DBRP assessment team cannot establish a link between these three major elements, a gap is identified. Resolutions to identified gaps represent configuration management and design basis recovery actions. The proposed paper discusses the process being applied to define, evaluate, report, and address gaps that are identified through the ATR DBRP. Design basis verification may be performed or required for a nuclear facility safety basis on various levels. The process is applicable to large-scale design basis reconstitution efforts, such as the ATR DBRP, or may be scaled for application on smaller projects. The concepts are applicable to long-term maintenance of a nuclear facility safety basis and recovery of degraded safety basis components. The ATR DBRP assessment team has observed numerous examples where a clear and accurate link between the DSA, design basis, and actual system configuration was not immediately identifiable in supporting documentation. As a result, a systematic approach to effectively document, prioritize, and evaluate each observation is required. The DBRP issue resolution process provides direction for consistent identification, documentation, categorization, and evaluation, and where applicable, entry into the determination process for a potential inadequacy in the safety analysis (PISA). The issue resolution process is a key element for execution of the DBRP. Application of the process facilitates collection, assessment, and reporting of issues identified by the DBRP team. Application of the process results in an organized database of safety basis gaps and prioritized corrective action planning and resolution. The DBRP team follows the ATR

    • Development of design basis capacity for SNF project systems

      SciTech Connect (OSTI)

      Pajunen, A.L.

      1996-02-27

      An estimate of the design capacity for Spent Nuclear Fuel Project systems producing Multi-Canister Overpacks is developed based on completing fuel processing in a two year period. The design basis capacity for systems relates the desired annual processing rate to potential operating inefficiencies which may be actually experienced to project a design capacity for systems. The basis for estimating operating efficiency factors is described. Estimates of the design basis capacity were limited to systems actually producing the Multi-Canister Overpack. These systems include Fuel Retrieval, K Basin SNF Vacuum Drying, Canister Storage Building support for Staging and Storage, and Hot Vacuum conditioning. The capacity of other systems are assumed to be derived from these system capacities such that systems producing a Multi-Canister Overpack are not constrained.

    • Solar Power Tower Design Basis Document, Revision 0

      SciTech Connect (OSTI)

      ZAVOICO,ALEXIS B.

      2001-07-01

      This report contains the design basis for a generic molten-salt solar power tower. A solar power tower uses a field of tracking mirrors (heliostats) that redirect sunlight on to a centrally located receiver mounted on top a tower, which absorbs the concentrated sunlight. Molten nitrate salt, pumped from a tank at ground level, absorbs the sunlight, heating it up to 565 C. The heated salt flows back to ground level into another tank where it is stored, then pumped through a steam generator to produce steam and make electricity. This report establishes a set of criteria upon which the next generation of solar power towers will be designed. The report contains detailed criteria for each of the major systems: Collector System, Receiver System, Thermal Storage System, Steam Generator System, Master Control System, and Electric Heat Tracing System. The Electric Power Generation System and Balance of Plant discussions are limited to interface requirements. This design basis builds on the extensive experience gained from the Solar Two project and includes potential design innovations that will improve reliability and lower technical risk. This design basis document is a living document and contains several areas that require trade-studies and design analysis to fully complete the design basis. Project- and site-specific conditions and requirements will also resolve open To Be Determined issues.

    • Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents

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

      SENSITIVE DOE-STD-1104-2009 May 2009 Superseding DOE-STD-1104-96 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1104-2009 ii Available on the Department of Energy Technical Standards web page at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1104-2009 iii CONTENTS FOREWORD

    • Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

      SciTech Connect (OSTI)

      CROWE, R.D.

      1999-09-09

      This document provides the detailed accident analysis to support ''HNF-3553, Spent Nuclear Fuel Project Final Safety, Analysis Report, Annex A,'' ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  1. Cold Vacuum Drying (CVD) Facility Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    PIEPHO, M.G.

    1999-10-20

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR.

  2. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.; PIEPHO, M.G.

    2000-03-23

    This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  3. Canister storage building design basis accident analysis documentation

    SciTech Connect (OSTI)

    KOPELIC, S.D.

    1999-02-25

    This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  4. Basis for NGNP Reactor Design Down-Selection

    SciTech Connect (OSTI)

    L.E. Demick

    2011-11-01

    The purpose of this paper is to identify the extent of technology development, design and licensing maturity anticipated to be required to credibly identify differences that could make a technical choice practical between the prismatic and pebble bed reactor designs. This paper does not address a business decision based on the economics, business model and resulting business case since these will vary based on the reactor application. The selection of the type of reactor, the module ratings, the number of modules, the configuration of the balance of plant and other design selections will be made on the basis of optimizing the Business Case for the application. These are not decisions that can be made on a generic basis.

  5. Design-Load Basis for LANL Structures, Systems, and Components

    SciTech Connect (OSTI)

    I. Cuesta

    2004-09-01

    This document supports the recommendations in the Los Alamos National Laboratory (LANL) Engineering Standard Manual (ESM), Chapter 5--Structural providing the basis for the loads, analysis procedures, and codes to be used in the ESM. It also provides the justification for eliminating the loads to be considered in design, and evidence that the design basis loads are appropriate and consistent with the graded approach required by the Department of Energy (DOE) Code of Federal Regulation Nuclear Safety Management, 10, Part 830. This document focuses on (1) the primary and secondary natural phenomena hazards listed in DOE-G-420.1-2, Appendix C, (2) additional loads not related to natural phenomena hazards, and (3) the design loads on structures during construction.

  6. Cold Vacuum Drying facility design basis accident analysis documentation

    SciTech Connect (OSTI)

    CROWE, R.D.

    2000-08-08

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

  7. Theoretical Basis for the Design of a DWPF Evacuated Canister

    SciTech Connect (OSTI)

    Routt, K.R.

    2001-09-17

    This report provides the theoretical bases for use of an evacuated canister for draining a glass melter. Design recommendations are also presented to ensure satisfactory performance in future tests of the concept.

  8. Report to the Secretary of Energy on Beyond Design Basis Event...

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

    BDBEReportfinal.pdf More Documents & Publications Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements...

  9. A BASIS FOR MODIFYING THE TANK 12 COMPOSITE SAMPLING DESIGN

    SciTech Connect (OSTI)

    Shine, G.

    2014-11-25

    The SRR sampling campaign to obtain residual solids material from the Savannah River Site (SRS) Tank Farm Tank 12 primary vessel resulted in obtaining appreciable material in all 6 planned source samples from the mound strata but only in 5 of the 6 planned source samples from the floor stratum. Consequently, the design of the compositing scheme presented in the Tank 12 Sampling and Analysis Plan, Pavletich (2014a), must be revised. Analytical Development of SRNL statistically evaluated the sampling uncertainty associated with using various compositing arrays and splitting one or more samples for compositing. The variance of the simple mean of composite sample concentrations is a reasonable standard to investigate the impact of the following sampling options. Composite Sample Design Option (a). Assign only 1 source sample from the floor stratum and 1 source sample from each of the mound strata to each of the composite samples. Each source sample contributes material to only 1 composite sample. Two source samples from the floor stratum would not be used. Composite Sample Design Option (b). Assign 2 source samples from the floor stratum and 1 source sample from each of the mound strata to each composite sample. This infers that one source sample from the floor must be used twice, with 2 composite samples sharing material from this particular source sample. All five source samples from the floor would be used. Composite Sample Design Option (c). Assign 3 source samples from the floor stratum and 1 source sample from each of the mound strata to each composite sample. This infers that several of the source samples from the floor stratum must be assigned to more than one composite sample. All 5 source samples from the floor would be used. Using fewer than 12 source samples will increase the sampling variability over that of the Basic Composite Sample Design, Pavletich (2013). Considering the impact to the variance of the simple mean of the composite sample concentrations

  10. Laser design basis for the National Ignition Facility

    SciTech Connect (OSTI)

    Hunt, J.T.; Manes, K.R.; Murray, J.R.; Renard, P.A.; Sawicki, R.; Trenholme, J.B.; Williams, W.

    1994-06-01

    Controlled nuclear fusion initiated by highly intense laser beams has been the subject of experiment for many years. The National Ignition Facility (NIF) represents the culmination of design efforts to provide a laser facility that will successfully demonstrate fusion ignition in the laboratory. In this so-called inertial confinement approach, energetic driver beams (laser, X-ray, or charged particle) heat the outer surface of a spherical capsule containing deuterium and tritium (DT) fuel. As the capsule surface explosively evaporates, reaction pressure compresses the DT fuel causing the central core of the fuel to reach extreme density and temperature. When the central temperature is high enough, DT fusion reactions occur. The energy released from these reactions further heats the compressed fuel, and fusion burn propagates outward through the colder regions of the capsule much more rapidly than the inertially confined capsule can expand. The resulting fusion reactions yield many times more energy than was absorbed from the driver beams.

  11. Breckinridge Project, initial effort. Report II. Breckinridge Project design basis

    SciTech Connect (OSTI)

    1982-01-01

    The Breckinridge Project is a pioneer endeavor involving the engineering, construction, and operation of a commercial facility that will convert 23,000 tons per day of run-of-mine, high-sulfur coal into 50,000 barrels per day of liquid hydrocarbons equivalent to those produced from crude oil. The Initial Effort, now complete, was executed under Cooperative Agreement No. DE-FC05-80OR20717 between the Department of Energy and the Participants, Ashland Synthetic Fuels, Inc., and Airco Energy Company, Inc. The Initial Effort produced a preliminary design, capital estimate, and economic analysis of the commercial plant, as well as a plan for the design, construction, and operation of that plant. The extensive and rigorous attention given to environmental, socioeconomic, safety, and health considerations is indicative of the high priority these issues will continue to receive throughout the life of the project. The Breckinridge Energy Company, a partnership of several major corporations, is being formed to finance, own, and manage the Breckinridge Project. Report II is intended for the reader who is primarily interested in less detailed discussion of the coal liquefaction process and Breckinridge facility than presented in the eleven volumes of Reports IV and V. The overview section describes the project goals and briefly introduces the coal liquefaction process. The report continues with a discussion of the history of the project and the H-COAL process from its concept to the proposed commercialization technology. The report describes the site, the Breckinridge Facility, and concludes with a summary of the eleven reports that contain the deliverable documentation of the Initial Effort or Development Phase of the project.

  12. Reducing Uncertainty in the Seismic Design Basis for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, Thomas M.; Rohay, Alan C.; Reidel, Steve; Gardner, Martin G.

    2007-02-27

    The seismic design basis for the Waste Treatment Plant (WTP) at the Department of Energy’s (DOE) Hanford Site near Richland was re-evaluated in 2005, resulting in an increase by up to 40% in the seismic design basis. The original seismic design basis for the WTP was established in 1999 based on a probabilistic seismic hazard analysis completed in 1996. The 2005 analysis was performed to address questions raised by the Defense Nuclear Facilities Safety Board (DNFSB) about the assumptions used in developing the original seismic criteria and adequacy of the site geotechnical surveys. The updated seismic response analysis used existing and newly acquired seismic velocity data, statistical analysis, expert elicitation, and ground motion simulation to develop interim design ground motion response spectra which enveloped the remaining uncertainties. The uncertainties in these response spectra were enveloped at approximately the 84th percentile to produce conservative design spectra, which contributed significantly to the increase in the seismic design basis.

  13. Drain Tank Information for Developing Design Basis of the Preliminary Design

    SciTech Connect (OSTI)

    Ferrada, Juan J

    2012-02-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of coolant accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)]; Neutral Beam Injector (NBI) components; and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004-design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by US ITER and AREVA Federal Services, the US ITER A and E Company. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design basis accident: a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassette lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA

  14. Drain Tank Information for Developing Design Basis of the Preliminary Design - R00

    SciTech Connect (OSTI)

    Ferrada, Juan J

    2011-01-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of cooling accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)], Neutral Beam Injector (NBI) components, and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004 design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by U.S. ITER. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design-basis accident:1 a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassettes lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout anddimensions, including design

  15. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis

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

    Analysis, March 2011 | Department of Energy DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011 DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011 PURPOSE This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. BACKGROUND On March 11, 2011, the Fukushima Daiichi nuclear power station in

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

    SciTech Connect (OSTI)

    Demuth, Scott F; Mullen, Mark

    2011-10-05

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

  17. The power of simplification: Operator interface with the AP1000{sup R} during design-basis and beyond design-basis events

    SciTech Connect (OSTI)

    Williams, M. G.; Mouser, M. R.; Simon, J. B.

    2012-07-01

    The AP1000{sup R} plant is an 1100-MWe pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and cost. The passive safety features are designed to function without safety-grade support systems such as component cooling water, service water, compressed air or HVAC. The AP1000 passive safety features achieve and maintain safe shutdown in case of a design-basis accident for 72 hours without need for operator action, meeting the expectations provided in the European Utility Requirements and the Utility Requirement Document for passive plants. Limited operator actions may be required to maintain safe conditions in the spent fuel pool (SFP) via passive means. This safety approach therefore minimizes the reliance on operator action for accident mitigation, and this paper examines the operator interaction with the Human-System Interface (HSI) as the severity of an accident increases from an anticipated transient to a design basis accident and finally, to a beyond-design-basis event. The AP1000 Control Room design provides an extremely effective environment for addressing the first 72 hours of design-basis events and transients, providing ease of information dissemination and minimal reliance upon operator actions. Symptom-based procedures including Emergency Operating Procedures (EOPs), Abnormal Operating Procedures (AOPs) and Alarm Response Procedures (ARPs) are used to mitigate design basis transients and accidents. Use of the Computerized Procedure System (CPS) aids the operators during mitigation of the event. The CPS provides cues and direction to the operators as the event progresses. If the event becomes progressively worse or lasts longer than 72 hours, and depending upon the nature of failures that may have occurred, minimal operator actions may be required outside of the control room in areas that have been designed to be accessible using components that have been

  18. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    SciTech Connect (OSTI)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-11-01

    The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

  19. Comparison of CRBR design-basis events with those of foreign LMFBR plants

    SciTech Connect (OSTI)

    Agrawal, A.K.

    1983-04-01

    As part of the Construction Permit (CP) review of the Clinch River Breeder Reactor Plant (CRBR), the Brookhaven National Laboratory was asked to compare the Design Basis Accidents that are considered in CRBR Preliminary Safety Analysis Report with those of the foreign contemporary plants (PHENIX, SUPER-PHENIX, SNR-300, PFR, and MONJU). A brief introductory review of any special or unusual characteristics of these plants is given. This is followed by discussions of the design basis accidents and their acceptance criteria. In spite of some discrepancies due either to semantics or to licensing decisions, there appears to be a considerable degree of unanimity in the selection (definition) of DBAs in all of these plants.

  20. AP1000 Design Basis Event Simulation at the APEX-1000 Test Facility

    SciTech Connect (OSTI)

    Wright, Richard F.; Groome, John

    2004-07-01

    The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. Several design basis events are being simulated at APEX-1000 including a double-ended direct vessel injection (DEDVI) line break and a 2-inch cold leg break. These tests show that the core remains covered with ample margin until gravity injection is established regardless of the initiating event. The tests also show that liquid entrainment from the upper plenum which is proportional to the reactor power does not impact the ability of the passive core cooling system to keep the core covered. (authors)

  1. Current plans to characterize the design basis ground motion at the Yucca Mountain, Nevada Site

    SciTech Connect (OSTI)

    Simecka, W.B.; Grant, T.A.; Voegele, M.D.; Cline, K.M.

    1992-12-31

    A site at Yucca Mountain Nevada is currently being studied to assess its suitability as a potential host site for the nation`s first commercial high level waste repository. The DOE has proposed a new methodology for determining design-basis ground motions that uses both deterministic and probabilistic methods. The role of the deterministic approach is primary. It provides the level of detail needed by design engineers in the characterization of ground motions. The probabilistic approach provides a logical structured procedure for integrating the range of possible earthquakes that contribute to the ground motion hazard at the site. In addition, probabilistic methods will be used as needed to provide input for the assessment of long-term repository performance. This paper discusses the local tectonic environment, potential seismic sources and their associated displacements and ground motions. It also discusses the approach to assessing the design basis earthquake for the surface and underground facilities, as well as selected examples of the use of this type of information in design activities.

  2. Demonstrating Structural Adequacy of Nuclear Power Plant Containment Structures for Beyond Design-Basis Pressure Loadings

    SciTech Connect (OSTI)

    Braverman, J.I.; Morante, R.

    2010-07-18

    ABSTRACT Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment structures, for beyond design-basis internal pressure loadings, is necessary to satisfy Nuclear Regulatory Commission (NRC) requirements and performance goals. This paper discusses methods for demonstrating the structural adequacy of the containment for beyond design-basis pressure loadings. Three distinct evaluations are addressed: (1) estimating the ultimate pressure capacity of the containment structure (10 CFR 50 and US NRC Standard Review Plan, Section 3.8) ; (2) demonstrating the structural adequacy of the containment subjected to pressure loadings associated with combustible gas generation (10 CFR 52 and 10 CFR 50); and (3) demonstrating the containment structural integrity for severe accidents (10 CFR 52 as well as SECY 90-016, SECY 93-087, and related NRC staff requirements memoranda (SRMs)). The paper describes the technical basis for specific aspects of the methods presented. It also presents examples of past issues identified in licensing activities related to these evaluations.

  3. Licensing topical report: application of probabilistic risk assessment in the selection of design basis accidents. [HTGR

    SciTech Connect (OSTI)

    Houghton, W.J.

    1980-06-01

    A probabilistic risk assessment (PRA) approach is proposed to be used to scrutinize selection of accident sequences. A technique is described in this Licensing Topical Report to identify candidates for Design Basis Accidents (DBAs) utilizing the risk assessment results. As a part of this technique, it is proposed that events with frequencies below a specified limit would not be candidates. The use of the methodology described is supplementary to the traditional, deterministic approach and may result, in some cases, in the selection of multiple failure sequences as DBAs; it may also provide a basis for not considering some traditionally postulated events as being DBAs. A process is then described for selecting a list of DBAs based on the candidates from PRA as supplementary to knowledge and judgments from past licensing practice. These DBAs would be the events considered in Chapter 15 of Safety Analysis Reports of high-temperature gas-cooled reactors (HTGRs).

  4. Breckinridge Project, initial effort. Report XI, Volume V. Critical review of the design basis. [Critical review

    SciTech Connect (OSTI)

    1982-01-01

    Report XI, Technical Audit, is a compendium of research material used during the Initial Effort in making engineering comparisons and decisions. Volumes 4 and 5 of Report XI present those studies which provide a Critical Review of the Design Basis. The Critical Review Report, prepared by Intercontinental Econergy Associates, Inc., summarizes findings from an extensive review of the data base for the H-Coal process design. Volume 4 presents this review and assessment, and includes supporting material; specifically, Design Data Tabulation (Appendix A), Process Flow Sheets (Appendix B), and References (Appendix C). Volume 5 is a continuation of the references of Appendix C. Studies of a proprietary nature are noted and referenced, but are not included in these volumes. They are included in the Limited Access versions of these reports and may be reviewed by properly cleared personnel in the offices of Ashland Synthetic Fuels, Inc.

  5. Technical Basis for Certification of Seismic Design Criteria for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, T.M.; Rohay, A.C. [Pacific Northwest National Laboratory, Richland, WA (United States); Youngs, R.R. [Geomatrix Consultants, Inc., Oakland, CA (United States); Costantino, C.J. [C.J. Costantino and Associates, Valley, NY (United States); Miller, L.F. [U.S. Department of Energy, Office of River Protection, Richland, WA (United States)

    2008-07-01

    In August 2007, Secretary of Energy Samuel W. Bodman approved the final seismic and ground motion criteria for the Waste Treatment and Immobilization Plant (WTP) at the Department of Energy's (DOE) Hanford Site. Construction of the WTP began in 2002 based on seismic design criteria established in 1999 and a probabilistic seismic hazard analysis completed in 1996. The design criteria were reevaluated in 2005 to address questions from the Defense Nuclear Facilities Safety Board (DNFSB), resulting in an increase by up to 40% in the seismic design basis. DOE announced in 2006 the suspension of construction on the pretreatment and high-level waste vitrification facilities within the WTP to validate the design with more stringent seismic criteria. In 2007, the U.S. Congress mandated that the Secretary of Energy certify the final seismic and ground motion criteria prior to expenditure of funds on construction of these two facilities. With the Secretary's approval of the final seismic criteria in the summer of 2007, DOE authorized restart of construction of the pretreatment and high-level waste vitrification facilities. The technical basis for the certification of seismic design criteria resulted from a two-year Seismic Boreholes Project that planned, collected, and analyzed geological data from four new boreholes drilled to depths of approximately 1400 feet below ground surface on the WTP site. A key uncertainty identified in the 2005 analyses was the velocity contrasts between the basalt flows and sedimentary interbeds below the WTP. The absence of directly-measured seismic shear wave velocities in the sedimentary interbeds resulted in the use of a wider and more conservative range of velocities in the 2005 analyses. The Seismic Boreholes Project was designed to directly measure the velocities and velocity contrasts in the basalts and sediments below the WTP, reanalyze the ground motion response, and assess the level of conservatism in the 2005 seismic design criteria

  6. Development of Probabilistic Design Basis Earthquake (DBE) Parameters for Moderate and High Hazard Facilities at INEEL

    SciTech Connect (OSTI)

    S. M. Payne; V. W. Gorman; S. A. Jensen; M. E. Nitzel; M. J. Russell; R. P. Smith

    2000-03-01

    Design Basis Earthquake (DBE) horizontal and vertical response spectra are developed for moderate and high hazard facilities or Performance Categories (PC) 3 and 4, respectively, at the Idaho National Engineering and Environmental Laboratory (INEEL). The probabilistic DBE response spectra will replace the deterministic DBE response spectra currently in the U.S. Department of Energy Idaho Operations Office (DOE-ID) Architectural Engineering Standards that govern seismic design criteria for several facility areas at the INEEL. Probabilistic DBE response spectra are recommended to DOE Naval Reactors for use at the Naval Reactor Facility at INEEL. The site-specific Uniform Hazard Spectra (UHS) developed by URS Greiner Woodward Clyde Federal Services are used as the basis for developing the DBE response spectra. In 1999, the UHS for all INEEL facility areas were recomputed using more appropriate attenuation relationships for the Basin and Range province. The revised UHS have lower ground motions than those produced in the 1996 INEEL site-wide probabilistic ground motion study. The DBE response spectra were developed by incorporating smoothed broadened regions of the peak accelerations, velocities, and displacements defined by the site-specific UHS. Portions of the DBE response spectra were adjusted to ensure conservatism for the structural design process.

  7. Technical Basis for Certification of Seismic Design Criteria for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, Thomas M.; Rohay, Alan C.; Youngs, Robert R.; Costantino, Carl J.; Miller, Lewis F.

    2008-02-28

    In August 2007, Secretary of Energy Samuel W. Bodman approved the final seismic and ground motion criteria for the Waste Treatment and Immobilization Plant (WTP) at the Department of Energy’s (DOE) Hanford Site. Construction of the WTP began in 2002 based on seismic design criteria established in 1999 and a probabilistic seismic hazard analysis completed in 1996. The design criteria were re-evaluated in 2005 to address questions from the Defense Nuclear Facilities Safety Board (DNFSB), resulting in an increase by up to 40% in the seismic design basis. DOE announced in 2006 the suspension of construction on the pretreatment and high-level waste vitrification facilities within the WTP to validate the design with more stringent seismic criteria. In 2007, the U.S. Congress mandated that the Secretary of Energy certify the final seismic and ground motion criteria prior to expenditure of funds on construction of these two facilities. With the Secretary’s approval of the final seismic criteria this past summer, DOE authorized restart of construction of the pretreatment and high-level waste vitrification facilities.

  8. Beyond-Design-Basis-Accidents Passive Containment-Cooling Spray System

    SciTech Connect (OSTI)

    Karameldin, Aly; Temraz, Hassan M. Elsawy; Ibrahim, Nady Attia [Atomic Energy Authority (Egypt)

    2001-10-15

    The proposed safety feature considered in this study aims to increase the safety margins of nuclear power plants by proposed water tanks located inside or outside the upper zone of the containment to be utilized for (a) residual heat removal of the reactor in case of station blackout or in case of normal reactor shutdown and (b) beyond-design-basis accidents, in which core melt and debris-concrete interaction take place, associated with accumulative containment pressure increase and partial loss of the active systems. The proposed passive containment system can be implemented by a special mechanism, which can allow the pressurization of the water in the tanks and therefore can enable an additional spray system to start in case of increasing the containment pressure over a certain value just below the design pressure. A conservative case study is that of a Westinghouse 3411-MW(thermal) power station, where the proposed passive containment cooling spray system (PCCSS) will start at a pressure of 6 bars and terminate at a pressure of 3 bars. A one-dimensional lumped model is postulated to describe the thermal and hydraulic process behavior inside the containment after a beyond-design-basis accident. The considered parameters are the spray mass flow rate, the initial droplet diameters, fuel-cooling time, and the ultimate containment pressure. The overall heat and mass balance inside the containment are carried out, during both the containment depressurization (by the spraying system) and pressurization (by the residual energies). The results show that the design of the PCCSS is viable and has a capability to maintain the containment below the design pressure passively for the required grace period of 72 h. Design curves of the proposed PCCSS indicate the effect of the spray flow rate and cooling time on the total sprayed volume during the grace period of 72 h. From these curves it can be concluded that for the grace period of 72 h, the required tank volumes are 3800

  9. Criteria for calculating the efficiency of HEPA filters during and after design basis accidents

    SciTech Connect (OSTI)

    Bergman, W.; First, M.W.; Anderson, W.L.; Gilbert, H.; Jacox, J.W.

    1994-12-01

    We have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data.

  10. Emerging Threats and Opportunities

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

    Emergency Response NNSA's Office of Emergency Operations is the United States government's primary capability for radiological and nuclear emergency response and for providing security to the nation from the threat of nuclear terrorism. The Office of Emergency Operations maintains a high level of readiness for protecting and serving the U.S. and its allies through the development, implementation and coordination of programs and systems designed to serve as a last line of defense in the event of

  11. Maximal design basis accident of fusion neutron source DEMO-TIN

    SciTech Connect (OSTI)

    Kolbasov, B. N.

    2015-12-15

    When analyzing the safety of nuclear (including fusion) facilities, the maximal design basis accident at which the largest release of activity is expected must certainly be considered. Such an accident is usually the failure of cooling systems of the most thermally stressed components of a reactor (for a fusion facility, it is the divertor or the first wall). The analysis of safety of the ITER reactor and fusion power facilities (including hybrid fission–fusion facilities) shows that the initial event of such a design basis accident is a large-scale break of a pipe in the cooling system of divertor or the first wall outside the vacuum vessel of the facility. The greatest concern is caused by the possibility of hydrogen formation and the inrush of air into the vacuum chamber (VC) with the formation of a detonating mixture and a subsequent detonation explosion. To prevent such an explosion, the emergency forced termination of the fusion reaction, the mounting of shutoff valves in the cooling systems of the divertor and the first wall or blanket for reducing to a minimum the amount of water and air rushing into the VC, the injection of nitrogen or inert gas into the VC for decreasing the hydrogen and oxygen concentration, and other measures are recommended. Owing to a continuous feed-out of the molten-salt fuel mixture from the DEMO-TIN blanket with the removal period of 10 days, the radioactivity release at the accident will mainly be determined by tritium (up to 360 PBq). The activity of fission products in the facility will be up to 50 PBq.

  12. Application of the MELCOR code to design basis PWR large dry containment analysis.

    SciTech Connect (OSTI)

    Phillips, Jesse; Notafrancesco, Allen (USNRC, Office of Nuclear Regulatory Research, Rockville, MD); Tills, Jack Lee (Jack Tills & Associates, Inc., Sandia Park, NM)

    2009-05-01

    The MELCOR computer code has been developed by Sandia National Laboratories under USNRC sponsorship to provide capability for independently auditing analyses submitted by reactor manufactures and utilities. MELCOR is a fully integrated code (encompassing the reactor coolant system and the containment building) that models the progression of postulated accidents in light water reactor power plants. To assess the adequacy of containment thermal-hydraulic modeling incorporated in the MELCOR code for application to PWR large dry containments, several selected demonstration designs were analyzed. This report documents MELCOR code demonstration calculations performed for postulated design basis accident (DBA) analysis (LOCA and MSLB) inside containment, which are compared to other code results. The key processes when analyzing the containment loads inside PWR large dry containments are (1) expansion and transport of high mass/energy releases, (2) heat and mass transfer to structural passive heat sinks, and (3) containment pressure reduction due to engineered safety features. A code-to-code benchmarking for DBA events showed that MELCOR predictions of maximum containment loads were equivalent to similar predictions using a qualified containment code known as CONTAIN. This equivalency was found to apply for both single- and multi-cell containment models.

  13. Simulation of a beyond design-basis-accident with RELAP5/MOD3.1

    SciTech Connect (OSTI)

    Banati, J.

    1995-09-01

    This paper summarizes the results of analyses, parametric and sensitivity studies, performed using the RELAP5/MOD3.1 computer code for the 4th IAEA Standard Problem Exercise (SPE-4). The test, conducted on the PMK-2 facility in Budapest, involved simulation of a Small Break Loss Of Coolant Accident (SBLOCA) with a 7.4% break in the cold leg of a VVER-440 type pressurized water reactor. According to the scenario, the unavailability of the high pressure injection system led to a beyond design basis accident. For prevention of core damage, secondary side bleed-and-feed accident management measures were applied. A brief description of the PMK-2 integral type test facility is presented, together with the profile and some key phenomenological aspects of this particular experiment. Emphasis is placed on the ability of the code to predict the main trends observed in the test and thus, an assessment is given for the code capabilities to represent the system transient.

  14. Cyber threat metrics.

    SciTech Connect (OSTI)

    Frye, Jason Neal; Veitch, Cynthia K.; Mateski, Mark Elliot; Michalski, John T.; Harris, James Mark; Trevino, Cassandra M.; Maruoka, Scott

    2012-03-01

    Threats are generally much easier to list than to describe, and much easier to describe than to measure. As a result, many organizations list threats. Fewer describe them in useful terms, and still fewer measure them in meaningful ways. This is particularly true in the dynamic and nebulous domain of cyber threats - a domain that tends to resist easy measurement and, in some cases, appears to defy any measurement. We believe the problem is tractable. In this report we describe threat metrics and models for characterizing threats consistently and unambiguously. The purpose of this report is to support the Operational Threat Assessment (OTA) phase of risk and vulnerability assessment. To this end, we focus on the task of characterizing cyber threats using consistent threat metrics and models. In particular, we address threat metrics and models for describing malicious cyber threats to US FCEB agencies and systems.

  15. Independent Oversight Review of the Los Alamos National Laboratory Transuranic Waste Facility Safety Basis and Design Development, July 2014

    Office of Environmental Management (EM)

    Los Alamos National Laboratory Transuranic Waste Facility Safety Basis and Design Development July 2014 Office of Nuclear Safety and Environmental Assessments Office of Environment, Safety and Health Assessments Office of Independent Enterprise Assessments U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................ 1 2.0 Scope ...

  16. Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development, August 2013

    Office of Environmental Management (EM)

    Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development May 2011 August 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background

  17. Insider Threat Program

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

    2014-06-02

    To establish responsibilities and requirements for the Department of Energy (DOE) Insider Threat Program (ITP) to deter, detect, and mitigate insider threat actions by Federal and contractor employees in accordance with the requirements of Executive Order 13587, the National Insider Threat Policy and Minimum Standards for Executive Branch Insider Threat Programs and other government-wide and DOE requirements. Does not cancel/supersede other directives.

  18. 105-K Basin material design basis feed description for spent nuclear fuel project facilities

    SciTech Connect (OSTI)

    Praga, A.N.

    1998-01-08

    Revisions 0 and 0A of this document provided estimated chemical and radionuclide inventories of spent nuclear fuel and sludge currently stored within the Hanford Site`s 105-K Basins. This Revision (Rev. 1) incorporates the following changes into Revision 0A: (1) updates the tables to reflect: improved cross section data, a decision to use accountability data as the basis for total Pu, a corrected methodology for selection of the heat generation basis fee, and a revised decay date; (2) adds section 3.3.3.1 to expand the description of the approach used to calculate the inventory values and explain why that approach yields conservative results; (3) changes the pre-irradiation braze beryllium value.

  19. Evaluation of the Scaling of the APEX-1000 Test Facility to AP1000 for Design Basis Events

    SciTech Connect (OSTI)

    Wright, Richard F.; Gagnon, Andre; Skinner, Jesse; Groome, John

    2004-07-01

    The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. Several design basis events have been simulated at APEX-1000 including double-ended direct vessel injection (DEDVI) line break, 2-inch cold leg break, and inadvertent actuation of the automatic depressurization system. These events were analyzed as part of the AP1000 safety analysis using the NOTRUMP computer code. Applying the scaling factors that were used to size the APEX-1000 facility, the test results can be compared to the NOTRUMP plant simulations. These comparisons indicate the similarity between the design basis events in AP1000 and APEX-1000, the adequacy of the scaling of APEX-1000, and the applicability of the NOTRUMP code. (authors)

  20. nuclear threat science

    National Nuclear Security Administration (NNSA)

    2011 National Strategy for Counterterrorism states that the danger of nuclear terrorism is the greatest threat to global security, and affirms preventing terrorist...

  1. Categorizing Threat Building and Using a Generic Threat Matrix | Department

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

    of Energy Categorizing Threat Building and Using a Generic Threat Matrix Categorizing Threat Building and Using a Generic Threat Matrix The key piece of knowledge necessary for building defenses capable of withstanding or surviving cyber and kinetic attacks is an understanding of the capabilities posed by threats to a government, function, or system. With the number of threats continuing to increase, it is no longer feasible to enumerate the capabilities of all known threats and then build

  2. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1993-03-18

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz.

  3. Modeling of the Reactor Core Isolation Cooling Response to Beyond Design Basis Operations - Interim Report

    SciTech Connect (OSTI)

    Ross, Kyle; Cardoni, Jeffrey N.; Wilson, Chisom Shawn; Morrow, Charles; Osborn, Douglas; Gauntt, Randall O.

    2015-12-01

    Efforts are being pursued to develop and qualify a system-level model of a reactor core isolation (RCIC) steam-turbine-driven pump. The model is being developed with the intent of employing it to inform the design of experimental configurations for full-scale RCIC testing. The model is expected to be especially valuable in sizing equipment needed in the testing. An additional intent is to use the model in understanding more fully how RCIC apparently managed to operate far removed from its design envelope in the Fukushima Daiichi Unit 2 accident. RCIC modeling is proceeding along two avenues that are expected to complement each other well. The first avenue is the continued development of the system-level RCIC model that will serve in simulating a full reactor system or full experimental configuration of which a RCIC system is part. The model reasonably represents a RCIC system today, especially given design operating conditions, but lacks specifics that are likely important in representing the off-design conditions a RCIC system might experience in an emergency situation such as a loss of all electrical power. A known specific lacking in the system model, for example, is the efficiency at which a flashing slug of water (as opposed to a concentrated jet of steam) could propel the rotating drive wheel of a RCIC turbine. To address this specific, the second avenue is being pursued wherein computational fluid dynamics (CFD) analyses of such a jet are being carried out. The results of the CFD analyses will thus complement and inform the system modeling. The system modeling will, in turn, complement the CFD analysis by providing the system information needed to impose appropriate boundary conditions on the CFD simulations. The system model will be used to inform the selection of configurations and equipment best suitable of supporting planned RCIC experimental testing. Preliminary investigations with the RCIC model indicate that liquid water ingestion by the turbine

  4. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 2, Appendices

    SciTech Connect (OSTI)

    Not Available

    1993-03-18

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical & Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties.

  5. Open literature review of threats including sabotage and theft of fissile material transport in Japan.

    SciTech Connect (OSTI)

    Cochran, John Russell; Furaus, James Phillip; Marincel, Michelle K.

    2005-06-01

    This report is a review of open literature concerning threats including sabotage and theft related to fissile material transport in Japan. It is intended to aid Japanese officials in the development of a design basis threat. This threat includes the external threats of the terrorist, criminal, and extremist, and the insider threats of the disgruntled employee, the employee forced into cooperation via coercion, the psychotic employee, and the criminal employee. Examination of the external terrorist threat considers Japanese demographics, known terrorist groups in Japan, and the international relations of Japan. Demographically, Japan has a relatively homogenous population, both ethnically and religiously. Japan is a relatively peaceful nation, but its history illustrates that it is not immune to terrorism. It has a history of domestic terrorism and the open literature points to the Red Army, Aum Shinrikyo, Chukaku-Ha, and Seikijuku. Japan supports the United States in its war on terrorism and in Iraq, which may make Japan a target for both international and domestic terrorists. Crime appears to remain low in Japan; however sources note that the foreign crime rate is increasing as the number of foreign nationals in the country increases. Antinuclear groups' recent foci have been nuclear reprocessing technology, transportation of MOX fuel, and possible related nuclear proliferation issues. The insider threat is first defined by the threat of the disgruntled employee. This threat can be determined by studying the history of Japan's employment system, where Keiretsu have provided company stability and lifetime employment. Recent economic difficulties and an increase of corporate crime, due to sole reliability on the honor code, have begun to erode employee loyalty.

  6. Protecting Against Nuclear Threats

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

    Protecting Against Nuclear Threats Protecting Against Nuclear Threats Los Alamos' mission is to solve national security challenges through scientific excellence. April 12, 2012 Los Alamos researchers use a magnetic field detector to screen carry-on liquids at airports Los Alamos researchers use a magnetic field detector to screen carry-on liquids at airports: MagViz project leader Michelle Espy demonstrates the MagViz liquid detection and analysis system in the Albuquerque International Sunport.

  7. THREAT OF MALICIOUS CODE

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

    THREAT OF MALICIOUS CODE The Department of Energy (DOE) is strongly committed to the protection of all DOE assets from cyber attack and malicious exploitation. This includes information, networks, hardware, software, and mobile devices. DOE's continued diligence in this arena is critical in today's constantly-evolving cyber threat landscape. A recently cited incident involved senior officials receiving unsolicited free phone chargers. Luckily, the source was legitimate and did not result in a

  8. Refining and end use study of coal liquids. Topical report: Petroleum Refinery; Linear Programming Model; and Design Basis

    SciTech Connect (OSTI)

    1995-03-01

    A model was developed for use in the Bechtel PIMS (Process Industry Modeling System) linear programming software to simulate a generic Midwest (PADD II) petroleum refinery of the future. This ``petroleum-only`` version of the model establishes the size and complexity of the refinery after the year 2000 and prior to the introduction of coal liquids. It should be noted that no assumption has been made on when a plant can be built to produce coal liquids except that it will be after the year 2000. The year 2000 was chosen because it is the latest year where fuel property and emission standards have been set by the Environmental Protection Agency. It assumes the refinery has been modified to accept crudes that are heavier in gravity and higher in sulfur than today`s average crude mix. In addition, the refinery has also been modified to produce a product slate of transportation fuels of the future (i.e. 40% reformulated gasolines). This model will be used as a basis for determining the optimum scheme for processing coal liquids in a petroleum refinery. This report summarizes the design basis for this ``petroleum only`` LP refinery model. A report detailing the refinery configuration when coal liquids are processed will be provided at a later date.

  9. Development of Site-Specific Soil Design Basis Earthquake (DBE) Parameters for the Integrated Waste Treatment Unit (IWTU)

    SciTech Connect (OSTI)

    Payne, Suzette

    2008-08-01

    Horizontal and vertical PC 3 (2,500 yr) Soil Design Basis Earthquake (DBE) 5% damped spectra, corresponding time histories, and strain-compatible soil properties were developed for the Integrated Waste Treatment Unit (IWTU). The IWTU is located at the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Laboratory (INL). Mean and 84th percentile horizontal DBE spectra derived from site-specific site response analyses were evaluated for the IWTU. The horizontal and vertical PC 3 (2,500 yr) Soil DBE 5% damped spectra at the 84th percentile were selected for Soil Structure Interaction (SSI) analyses at IWTU. The site response analyses were performed consistent with applicable Department of Energy (DOE) Standards, recommended guidance of the Nuclear Regulatory Commission (NRC), American Society of Civil Engineers (ASCE) Standards, and recommendations of the Blue Ribbon Panel (BRP) and Defense Nuclear Facilities Safety Board (DNFSB).

  10. After Action Report:Idaho National Laboratory (INL) 2014 Multiple Facility Beyond Design Basis (BDBE) Evaluated Drill October 21, 2014

    SciTech Connect (OSTI)

    V. Scott Barnes

    2014-12-01

    On October 21, 2014, Idaho National Laboratory (INL), in coordination with local jurisdictions, and Department of Energy (DOE) Idaho Operations Office (DOE ID) conducted an evaluated drill to demonstrate the ability to implement the requirements of DOE O 151.1C, “Comprehensive Emergency Management System” when responding to a beyond design basis event (BDBE) scenario as outlined in the Office of Health, Safety, and Security Operating Experience Level 1 letter (OE-1: 2013-01). The INL contractor, Battelle Energy Alliance, LLC (BEA), in coordination with CH2M-WG Idaho, LLC (CWI), and Idaho Treatment Group LLC (ITG), successfully demonstrated appropriate response measures to mitigate a BDBE event that would impact multiple facilities across the INL while protecting the health and safety of personnel, the environment, and property. Offsite response organizations participated to demonstrate appropriate response measures.

  11. 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

    SciTech Connect (OSTI)

    PACKER, M.J.

    1999-11-04

    Metallic uranium Spent Nuclear Fuel (SNF) is currently stored within two water filled pools, 105-KE Basin (KE Basin) and 105-KW Basin (KW Basin), at the United States Department of Energy (U.S. DOE) Hanford Site, in southeastern Washington State. The Spent Nuclear Fuel Project (SNF Project) is responsible to DOE for operation of these fuel storage pools and for the 2100 metric tons of SNF materials that they contain. The SNF Project mission includes safe removal and transportation of all SNF from these storage basins to a new storage facility in the 200 East Area. To accomplish this mission, the SNF Project modifies the existing KE Basin and KW Basin facilities and constructs two new facilities: the 100 K Area Cold Vacuum Drying Facility (CVDF), which drains and dries the SNF; and the 200 East Area Canister Storage Building (CSB), which stores the SNF. The purpose of this document is to describe the design basis feed compositions for materials stored or processed by SNF Project facilities and activities. This document is not intended to replace the Hanford Spent Fuel Inventory Baseline (WHC 1994b), but only to supplement it by providing more detail on the chemical and radiological inventories in the fuel (this volume) and sludge. A variety of feed definitions is required to support evaluation of specific facility and process considerations during the development of these new facilities. Six separate feed types have been identified for development of new storage or processing facilities. The approach for using each feed during design evaluations is to calculate the proposed facility flowsheet assuming each feed. The process flowsheet would then provide a basis for material compositions and quantities which are used in follow-on calculations.

  12. Possible Methods to Estimate Core Location in a Beyond-Design-Basis Accident at a GE BWR with a Mark I Containment Stucture

    SciTech Connect (OSTI)

    Walston, S; Rowland, M; Campbell, K

    2011-07-27

    It is difficult to track to the location of a melted core in a GE BWR with Mark I containment during a beyond-design-basis accident. The Cooper Nuclear Station provided a baseline of normal material distributions and shielding configurations for the GE BWR with Mark I containment. Starting with source terms for a design-basis accident, methods and remote observation points were investigated to allow tracking of a melted core during a beyond-design-basis accident. The design of the GE BWR with Mark-I containment highlights an amazing poverty of expectations regarding a common mode failure of all reactor core cooling systems resulting in a beyond-design-basis accident from the simple loss of electric power. This design is shown in Figure 1. The station blackout accident scenario has been consistently identified as the leading contributor to calculated probabilities for core damage. While NRC-approved models and calculations provide guidance for indirect methods to assess core damage during a beyond-design-basis loss-of-coolant accident (LOCA), there appears to be no established method to track the location of the core directly should the LOCA include a degree of fuel melt. We came to the conclusion that - starting with detailed calculations which estimate the release and movement of gaseous and soluble fission products from the fuel - selected dose readings in specific rooms of the reactor building should allow the location of the core to be verified.

  13. Criteria for calculating the efficiency of deep-pleated HEPA filters with aluminum separators during and after design basis accidents

    SciTech Connect (OSTI)

    Bergman, W.; First, M.W.; Anderson, W.L.; Gilbert, H.; Jacox, J.W.

    1995-02-01

    The authors have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). This study is only applicable to the standard deep-pleated HEPA filter with aluminum separators as specified in ASME N509. The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data.

  14. ThreatView

    Energy Science and Technology Software Center (OSTI)

    2007-09-25

    The ThreatView project is based on our prior work with the existing ParaView open-source scientific visualization application. Where ParaView provides a grapical client optimized scientific visualization over the VTK parallel client server architecture, ThreatView provides a client optimized for more generic visual analytics over the same architecture. Because ThreatView is based on the VTK parallel client-server architecture, data sources can reside on remote hosts, and processing and rendering can be performed in parallel. As seenmore » in Fig. 1, ThreatView provides four main methods for visualizing data: Landscape View, which displays a graph using a landscape metaphor where clusters of graph nodes produce "hills" in the landscape; Graph View, which displays a graph using a traditional "ball-and-stick" style; Table View, which displays tabular data in a standard spreadsheet; and Attribute View, which displays a tabular "histogram" of input data - for a selected table column, the Attribute View displays each unique value within the column, and the number of times that value appears in the data. There are two supplemental view types: Text View, which displays tabular data one-record-at-a-time; and the Statistics View, which displays input metadata, such as the number of vertices and edges in a graph, the number of rows in a table, etc.« less

  15. Analysis of main steam isolation valve leakage in design basis accidents using MELCOR 1.8.6 and RADTRAD.

    SciTech Connect (OSTI)

    Salay, Michael; Kalinich, Donald A.; Gauntt, Randall O.; Radel, Tracy E.

    2008-10-01

    Analyses were performed using MELCOR and RADTRAD to investigate main steam isolation valve (MSIV) leakage behavior under design basis accident (DBA) loss-of-coolant (LOCA) conditions that are presumed to have led to a significant core melt accident. Dose to the control room, site boundary and LPZ are examined using both approaches described in current regulatory guidelines as well as analyses based on best estimate source term and system response. At issue is the current practice of using containment airborne aerosol concentrations as a surrogate for the in-vessel aerosol concentration that exists in the near vicinity of the MSIVs. This study finds current practice using the AST-based containment aerosol concentrations for assessing MSIV leakage is non-conservative and conceptually in error. A methodology is proposed that scales the containment aerosol concentration to the expected vessel concentration in order to preserve the simplified use of the AST in assessing containment performance under assumed DBA conditions. This correction is required during the first two hours of the accident while the gap and early in-vessel source terms are present. It is general practice to assume that at {approx}2hrs, recovery actions to reflood the core will have been successful and that further core damage can be avoided. The analyses performed in this study determine that, after two hours, assuming vessel reflooding has taken place, the containment aerosol concentration can then conservatively be used as the effective source to the leaking MSIV's. Recommendations are provided concerning typical aerosol removal coefficients that can be used in the RADTRAD code to predict source attenuation in the steam lines, and on robust methods of predicting MSIV leakage flows based on measured MSIV leakage performance.

  16. Proliferation: Threat and response

    SciTech Connect (OSTI)

    1996-04-01

    During the height of the Cold War, the Russian physicist Andre Sakharov said, `Reducing the risk of annihilating humanity in a nuclear war carries an absolute priority over all other considerations.` The end of the Cold War has reduced the threat of global nuclear war, but today a new threat is rising from the global spread of nuclear, biological, and chemical weapons. Hostile groups and nations have tried - or have been able - to obtain these weapons, the technology, and homegrown ability to make them or ballistic missiles that can deliver the massive annihilation, poison, and death of these weapons hundreds of miles away. For rogue nations, these weapons are a ticket to power, stature, and confidence in regional war.

  17. Structural and Functional Basis for Broad-spectrum Neutralization...

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

    Structural and Functional Basis for Broad-spectrum Neutralization of Avian and Human ... globally that have little or no immunity, represents a grave threat to human health. ...

  18. Appraisal of the Uranium Processing Facility Safety Basis Preliminary Safety Design Report Process at the Y-12 National Security Complex, May 2013

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

    Independent Oversight Appraisal of the Uranium Processing Facility Safety Basis Preliminary Safety Design Report Process at the Y-12 National Security Complex May 2011 May 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose

  19. Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities, January 2013

    Office of Energy Efficiency and Renewable Energy (EERE)

    In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made. These actions and recommendations were addressed in an August 2011 report to the Secretary of Energy, Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events.

  20. Bio-threat microparticle simulants

    DOE Patents [OSTI]

    Farquar, George Roy; Leif, Roald N

    2012-10-23

    A bio-threat simulant that includes a carrier and DNA encapsulated in the carrier. Also a method of making a simulant including the steps of providing a carrier and encapsulating DNA in the carrier to produce the bio-threat simulant.

  1. Bio-threat microparticle simulants

    DOE Patents [OSTI]

    Farquar, George Roy; Leif, Roald

    2014-09-16

    A bio-threat simulant that includes a carrier and DNA encapsulated in the carrier. Also a method of making a simulant including the steps of providing a carrier and encapsulating DNA in the carrier to produce the bio-threat simulant.

  2. Insider Threat - Material Control and Accountability Mitigation

    SciTech Connect (OSTI)

    Powell, Danny H; Elwood Jr, Robert H; Roche, Charles T

    2011-01-01

    The technical objectives of nuclear safeguards are (1) the timely detection of diversion of significant quantities of nuclear material from peaceful uses to the manufacture of nuclear weapons or other nuclear explosive devices or for purposes unknown and (2) the deterrence of such diversion by the risk of early detection. The safeguards and security program must address both outsider threats and insider threats. Outsider threats are primarily addressed by the physical protection system. Insider threats can be any level of personnel at the site including passive or active insiders that could attempt protracted or abrupt diversion. This could occur by an individual acting alone or by collusion between an individual with material control and accountability (MC&A) responsibilities and another individual who has responsibility or control within both the physical protection and the MC&A systems. The insider threat is one that must be understood and incorporated into the safeguards posture. There have been more than 18 documented cases of theft or loss of plutonium or highly enriched uranium. The insider has access, authority, and knowledge, as well as a set of attributes, that make him/her difficult to detect. An integrated safeguards program is designed as a defense-in-depth system that seeks to prevent the unauthorized removal of nuclear material, to provide early detection of any unauthorized attempt to remove nuclear material, and to rapidly respond to any attempted removal of nuclear material. The program is also designed to support protection against sabotage, espionage, unauthorized access, compromise, and other hostile acts that may cause unacceptable adverse impacts on national security, program continuity, the health and safety of employees, the public, or the environment. Nuclear MC&A play an essential role in the capabilities of an integrated safeguards system to deter and detect theft or diversion of nuclear material. An integrated safeguards system with

  3. Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    O'Hara, J.M.

    2009-11-30

    Human performance models (HPMs) are simulations of human behavior with which we can predict human performance. Designers use them to support their human factors engineering (HFE) programs for a wide range of complex systems, including commercial nuclear power plants. Applicants to U.S. Nuclear Regulatory Commission (NRC) can use HPMs for design certifications, operating licenses, and license amendments. In the context of nuclear-plant safety, it is important to assure that HPMs are verified and validated, and their usage is consistent with their intended purpose. Using HPMs improperly may generate misleading or incorrect information, entailing safety concerns. The objective of this research was to develop guidance to support the NRC staff's reviews of an applicant's use of HPMs in an HFE program. The guidance is divided into three topical areas: (1) HPM Verification, (2) HPM Validation, and (3) User Interface Verification. Following this guidance will help ensure the benefits of HPMs are achieved in a technically sound, defensible manner. During the course of developing this guidance, I identified several issues that could not be addressed; they also are discussed.

  4. Threat Analysis Framework | Department of Energy

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

    Threat Analysis Framework Threat Analysis Framework The need to protect national critical infrastructure has led to the development of a threat analysis framework. The threat analysis framework can be used to identify the elements required to quantify threats against critical infrastructure assets and provide a means of distributing actionable threat information to critical infrastructure entities for the protection of infrastructure assets. This document identifies and describes five key

  5. Threat Analysis Framework | Department of Energy

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

    Threat Analysis Framework Threat Analysis Framework The need to protect national critical infrastructure has led to the development of a threat analysis framework. The threat analysis framework can be used to identify the elements required to quantify threats against critical infrastructure assets and provide a means of distributing actionable threat information to critical infrastructure entities for the protection of infrastructure assets. This document identifies and describes five key

  6. Material Performance of Fully-Ceramic Micro-Encapsulated Fuel under Selected LWR Design Basis Scenarios: Final Report

    SciTech Connect (OSTI)

    B. Boer; R. S. Sen; M. A. Pope; A. M. Ougouag

    2011-09-01

    The extension to LWRs of the use of Deep-Burn coated particle fuel envisaged for HTRs has been investigated. TRISO coated fuel particles are used in Fully-Ceramic Microencapsulated (FCM) fuel within a SiC matrix rather than the graphite of HTRs. TRISO particles are well characterized for uranium-fueled HTRs. However, operating conditions of LWRs are different from those of HTRs (temperature, neutron energy spectrum, fast fluence levels, power density). Furthermore, the time scales of transient core behavior during accidents are usually much shorter and thus more severe in LWRs. The PASTA code was updated for analysis of stresses in coated particle FCM fuel. The code extensions enable the automatic use of neutronic data (burnup, fast fluence as a function of irradiation time) obtained using the DRAGON neutronics code. An input option for automatic evaluation of temperature rise during anticipated transients was also added. A new thermal model for FCM was incorporated into the code; so-were updated correlations (for pyrocarbon coating layers) suitable to estimating dimensional changes at the high fluence levels attained in LWR DB fuel. Analyses of the FCM fuel using the updated PASTA code under nominal and accident conditions show: (1) Stress levels in SiC-coatings are low for low fission gas release (FGR) fractions of several percent, as based on data of fission gas diffusion in UO{sub 2} kernels. However, the high burnup level of LWR-DB fuel implies that the FGR fraction is more likely to be in the range of 50-100%, similar to Inert Matrix Fuels (IMFs). For this range the predicted stresses and failure fractions of the SiC coating are high for the reference particle design (500 {micro}mm kernel diameter, 100 {micro}mm buffer, 35 {micro}mm IPyC, 35 {micro}mm SiC, 40 {micro}mm OPyC). A conservative case, assuming 100% FGR, 900K fuel temperature and 705 MWd/kg (77% FIMA) fuel burnup, results in a 8.0 x 10{sup -2} failure probability. For a 'best-estimate' FGR fraction

  7. Nuclear Radiological Threat Task Force Established | National...

    National Nuclear Security Administration (NNSA)

    Nuclear Radiological Threat Task Force Established Washington, DC NNSA's Administrator Linton Brooks announces the establishment of the Nuclear Radiological Threat Reduction Task ...

  8. Global Threat Reduction Initiative | Department of Energy

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

    An overview of the Global Threat Reduction Initiative, U.S.-Origin Nuclear Fuel Removals. Global Threat Reduction Initiative (1.45

  9. Insider Threat Awareness | Department of Energy

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

    Threat Program https:www.directives.doe.govdirectives-documents400-series0470.5-BOrder Insider Threat Program Powerpedia Webpage https:powerpedia.energy.govwiki...

  10. Office of Nuclear Threat Science | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    | (NNSA) Nuclear Threat Science The Office of Nuclear Threat Science is responsible for overseeing the Nuclear Counterterrorism Program, an NNSA program that sustains specialized expertise and integrates and executes key activities to advise and enable technical aspects of U.S. Government nuclear counterterrorism and counterproliferation missions. Nuclear Counterterrorism The Nuclear Counterterrorism Program operates in partnership with weapons design-, stockpile science-, weapons surety-,

  11. Safety Basis Report

    SciTech Connect (OSTI)

    R.J. Garrett

    2002-01-14

    As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

  12. Cyber Threats to Nuclear Infrastructures

    SciTech Connect (OSTI)

    Robert S. Anderson; Paul Moskowitz; Mark Schanfein; Trond Bjornard; Curtis St. Michel

    2010-07-01

    Nuclear facility personnel expend considerable efforts to ensure that their facilities can maintain continuity of operations against both natural and man-made threats. Historically, most attention has been placed on physical security. Recently however, the threat of cyber-related attacks has become a recognized and growing world-wide concern. Much attention has focused on the vulnerability of the electric grid and chemical industries to cyber attacks, in part, because of their use of Supervisory Control and Data Acquisition (SCADA) systems. Lessons learned from work in these sectors indicate that the cyber threat may extend to other critical infrastructures including sites where nuclear and radiological materials are now stored. In this context, this white paper presents a hypothetical scenario by which a determined adversary launches a cyber attack that compromises the physical protection system and results in a reduced security posture at such a site. The compromised security posture might then be malevolently exploited in a variety of ways. The authors conclude that the cyber threat should be carefully considered for all nuclear infrastructures.

  13. Flashback: Rapid scanning for radiological threats

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

    Flashback: Rapid scanning for radiological threats Flashback: Rapid scanning for radiological threats The ability to identify distinct material density enables the Multi-Mode Passive Detection System (MMPDS)to quickly detect unshielded to heavily shielded nuclear threats, as well as gamma rays, with near-zero false alarms. November 1, 2015 Decision Science Decision Science Decision Sciences' Multi-Mode Passive Detection System: Rapid scanning forradiological threats Click on headline to go to

  14. nuclear threat science | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    threat science Counterterrorism Counterterrorism Policy and Cooperation Nuclear Threat Science Office of Nuclear Threat Science The Office of Nuclear Threat Science is responsible for overseeing the Nuclear Counterterrorism Program, an NNSA program that sustains specialized expertise and integrates and executes key activities to advise and enable technical aspects of U.S. Government nuclear counterterrorism and... Office of Counterterrorism Policy and Cooperation The 2011 National Strategy for

  15. Novel Threat-risk Index Using Probabilistic Risk Assessment and Human Reliability Analysis - Final Report

    SciTech Connect (OSTI)

    George A. Beitel

    2004-02-01

    In support of a national need to improve the current state-of-the-art in alerting decision makers to the risk of terrorist attack, a quantitative approach employing scientific and engineering concepts to develop a threat-risk index was undertaken at the Idaho National Engineering and Environmental Laboratory (INEEL). As a result of this effort, a set of models has been successfully integrated into a single comprehensive model known as Quantitative Threat-Risk Index Model (QTRIM), with the capability of computing a quantitative threat-risk index on a system level, as well as for the major components of the system. Such a threat-risk index could provide a quantitative variant or basis for either prioritizing security upgrades or updating the current qualitative national color-coded terrorist threat alert.

  16. Security by Design in the United States: Fact Sheet | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Security by Design in the United States: Fact Sheet March 23, 2012 Since the events of September 11, 2001, security requirements for nuclear facilities have increased primarily due to changes in the Design Basis Threat against which planned facilities are designed and existing physical security systems are tested. As a result, security costs and operational impacts have increased significantly because facilities originally were not designed with intrinsic

  17. Sensor-guided threat countermeasure system

    DOE Patents [OSTI]

    Stuart, Brent C.; Hackel, Lloyd A.; Hermann, Mark R.; Armstrong, James P.

    2012-12-25

    A countermeasure system for use by a target to protect against an incoming sensor-guided threat. The system includes a laser system for producing a broadband beam and means for directing the broadband beam from the target to the threat. The countermeasure system comprises the steps of producing a broadband beam and directing the broad band beam from the target to blind or confuse the incoming sensor-guided threat.

  18. Global Threat Reduction Initiative | Department of Energy

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

    The Current Status of Gap and U.S.-Origin Nuclear Fuel Removals 2011. Global Threat Reduction Initiative (2.96

  19. Autonomous Realtime Threat-Hunting Robot (ARTHR

    ScienceCinema (OSTI)

    INL

    2009-09-01

    Idaho National Laboratory researchers developed an intelligent plug-and-play robot payload that transforms commercial robots into effective first responders for deadly chemical, radiological and explosive threats.

  20. The Nature of the Bioterrorism Threat

    SciTech Connect (OSTI)

    Regens, J. L.

    2003-02-25

    This analysis provides an overview of the nature of the bioterrorism threat. It identifies potential CDC Class A biological agents that are likely candidates for use in a terrorist incident and describes the known sources of vulnerability. The paper also summarizes S&T resources/needs and assesses response options for achieving effective biodefense against terrorist threats.

  1. Autonomous Realtime Threat-Hunting Robot (ARTHR)

    ScienceCinema (OSTI)

    Idaho National Laboratory - David Bruemmer, Curtis Nielsen

    2010-01-08

    Idaho National Laboratory researchers developed an intelligent plug-and-play robot payload that transforms commercial robots into effective first responders for deadly chemical, radiological and explosive threats. To learn more, visit

  2. Manager, International Chemical Threat Reduction Department, Sandia

    National Nuclear Security Administration (NNSA)

    National Laboratories | National Nuclear Security Administration | (NNSA) Manager, International Chemical Threat Reduction Department, Sandia National Laboratories Nancy B. Jackson Nancy Jackson Nancy B. Jackson, manager of the International Chemical Threat Reduction Department at Sandia National Laboratories, will be the American Chemical Society president in 2011 and will serve on the ACS Board of Directors during her presidential succession, which will run from 2010 to 2012. Jackson holds

  3. Why is Zika now a threat?

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

    is Zika now a threat? Why is Zika now a threat? Population growth, rising temperatures, embryonic immune systems says Lab scientist February 25, 2016 Human-gorilla divergence may have occurred two million years earlier than thought (Photo : Flickr: Rod Waddington) Human-gorilla divergence may have occurred two million years earlier than thought (Photo : Flickr: Rod Waddington) "The distribution, transmission, and abundance of vectors that bear and transmit diseases are being enhanced by

  4. Bio-Terrorism Threat and Casualty Prevention

    SciTech Connect (OSTI)

    NOEL,WILLIAM P.

    2000-01-01

    The bio-terrorism threat has become the ''poor man's'' nuclear weapon. The ease of manufacture and dissemination has allowed an organization with only rudimentary skills and equipment to pose a significant threat with high consequences. This report will analyze some of the most likely agents that would be used, the ease of manufacture, the ease of dissemination and what characteristics of the public health response that are particularly important to the successful characterization of a high consequence event to prevent excessive causalities.

  5. V-220: Juniper Security Threat Response Manager Lets Remote Authentica...

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

    Threat Response Manager Lets Remote Authenticated Users Execute Arbitrary Commands V-220: Juniper Security Threat Response Manager Lets Remote Authenticated Users Execute...

  6. The space weather threat... and how we protect ourselves

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

    space weather threat... and how we protect ourselves The space weather threat... and how we protect ourselves The Sun continually ejects high-energy electrons, protons, and other ...

  7. Before the House Subcommittee on Emerging Threats, Cyber Security...

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

    Subcommittee on Emerging Threats, Cyber Security and Science and Technology Committee on Homeland Security Before the House Subcommittee on Emerging Threats, Cyber Security and ...

  8. The space weather threat... and how we protect ourselves

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

    The space weather threat... and how we protect ourselves The space weather threat... and how we protect ourselves The Sun continually ejects high-energy electrons, protons, and ...

  9. Rapid Threat Organism Recognition Pipeline

    Energy Science and Technology Software Center (OSTI)

    2013-05-07

    The RAPTOR computational pipeline identifies microbial nucleic acid sequences present in sequence data from clinical samples. It takes as input raw short-read genomic sequence data (in particular, the type generated by the Illumina sequencing platforms) and outputs taxonomic evaluation of detected microbes in various human-readable formats. This software was designed to assist in the diagnosis or characterization of infectious disease, by detecting pathogen sequences in nucleic acid sequence data from clinical samples. It has alsomore » been applied in the detection of algal pathogens, when algal biofuel ponds became unproductive. RAPTOR first trims and filters genomic sequence reads based on quality and related considerations, then performs a quick alignment to the human (or other host) genome to filter out host sequences, then performs a deeper search against microbial genomes. Alignment to a protein sequence database is optional. Alignment results are summarized and placed in a taxonomic framework using the Lowest Common Ancestor algorithm.« less

  10. Nuclear Radiological Threat Task Force Established | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Radiological Threat Task Force Established Nuclear Radiological Threat Task Force Established Washington, DC NNSA's Administrator Linton Brooks announces the establishment of the Nuclear Radiological Threat Reduction Task Force (NRTRTF) to combat the threats posed by radiological dispersion devices or "dirty bombs."

  11. Left-Wing Extremism: The Current Threat

    SciTech Connect (OSTI)

    Karl A. Seger

    2001-04-30

    Left-wing extremism is ''alive and well'' both in the US and internationally. Although the current domestic terrorist threat within the U. S. is focused on right-wing extremists, left-wing extremists are also active and have several objectives. Leftist extremists also pose an espionage threat to U.S. interests. While the threat to the U.S. government from leftist extremists has decreased in the past decade, it has not disappeared. There are individuals and organizations within the U.S. who maintain the same ideology that resulted in the growth of left-wing terrorism in this country in the 1970s and 1980s. Some of the leaders from that era are still communicating from Cuba with their followers in the U.S., and new leaders and groups are emerging.

  12. A threat-based definition of IA- and IA-enabled products.

    SciTech Connect (OSTI)

    Shakamuri, Mayuri; Schaefer, Mark A.; Campbell, Philip LaRoche

    2010-07-01

    This paper proposes a definition of 'IA and IA-enabled products' based on threat, as opposed to 'security services' (i.e., 'confidentiality, authentication, integrity, access control or non-repudiation of data'), as provided by Department of Defense (DoD) Instruction 8500.2, 'Information Assurance (IA) Implementation.' The DoDI 8500.2 definition is too broad, making it difficult to distinguish products that need higher protection from those that do not. As a consequence the products that need higher protection do not receive it, increasing risk. The threat-based definition proposed in this paper solves those problems by focusing attention on threats, thereby moving beyond compliance to risk management. (DoDI 8500.2 provides the definitions and controls that form the basis for IA across the DoD.) Familiarity with 8500.2 is assumed.

  13. A threat-based definition of IA and IA-enabled products.

    SciTech Connect (OSTI)

    Shakamuri, Mayuri; Schaefer, Mark A.; Campbell, Philip LaRoche

    2010-09-01

    This paper proposes a definition of 'IA and IA-enabled products' based on threat, as opposed to 'security services' (i.e., 'confidentiality, authentication, integrity, access control or non-repudiation of data'), as provided by Department of Defense (DoD) Instruction 8500.2, 'Information Assurance (IA) Implementation.' The DoDI 8500.2 definition is too broad, making it difficult to distinguish products that need higher protection from those that do not. As a consequence the products that need higher protection do not receive it, increasing risk. The threat-based definition proposed in this paper solves those problems by focusing attention on threats, thereby moving beyond compliance to risk management. (DoDI 8500.2 provides the definitions and controls that form the basis for IA across the DoD.) Familiarity with 8500.2 is assumed.

  14. Results from Beyond Design Basis Event Pilots

    Broader source: Energy.gov [DOE]

    Presenter: Mike Hillman, Program Manager, Office of Health, Safety and Security, US Department of Energy

  15. Events Beyond Design Safety Basis Analysis

    Broader source: Energy.gov [DOE]

    This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. [Safety Bulletin 2011-01

  16. Technical Planning Basis

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

    2007-07-11

    The Guide assists DOE/NNSA field elements and operating contractors in identifying and analyzing hazards at facilities and sites to provide the technical planning basis for emergency management programs. Supersedes DOE G 151.1-1, Volume 2.

  17. Securing Infrastructure from High Explosive Threats

    SciTech Connect (OSTI)

    Glascoe, L; Noble, C; Reynolds, J; Kuhl, A; Morris, J

    2009-03-20

    Lawrence Livermore National Laboratory (LLNL) is working with the Department of Homeland Security's Science and Technology Directorate, the Transportation Security Administration, and several infrastructure partners to characterize and help mitigate principal structural vulnerabilities to explosive threats. Given the importance of infrastructure to the nation's security and economy, there is a clear need for applied research and analyses (1) to improve understanding of the vulnerabilities of these systems to explosive threats and (2) to provide decision makers with time-critical technical assistance concerning countermeasure and mitigation options. Fully-coupled high performance calculations of structural response to ideal and non-ideal explosives help bound and quantify specific critical vulnerabilities, and help identify possible corrective schemes. Experimental validation of modeling approaches and methodologies builds confidence in the prediction, while advanced stochastic techniques allow for optimal use of scarce computational resources to efficiently provide infrastructure owners and decision makers with timely analyses.

  18. Nonproliferation, Nuclear Security, and the Insider Threat

    SciTech Connect (OSTI)

    Balatsky, Galya I.; Duggan, Ruth

    2012-07-12

    Insider threat concept is evolving and getting more attention: (1) Domestically, internationally and in foreign countries, (2) At the government, academia, and industry levels, and (3) Public awareness and concerns are also growing. Negligence can be an insider's action. Technology advancements provide more opportunities, new tools for the insider. Our understanding of the insider is shaped by our cultural, social and ethnic perceptions and traditions. They also can limit our recognition of the issues and response actions.

  19. Matrix Characterization in Threat Material Detection Processes

    SciTech Connect (OSTI)

    Obhodas, J.; Sudac, D.; Valkovic, V.

    2009-03-10

    Matrix characterization in the threat material detection is of utmost importance, it generates the background against which the threat material signal has to be identified. Threat materials (explosive, chemical warfare, ...) are usually contained within small volume inside large volumes of variable matrices. We have studied the influence of matrix materials on the capability of neutron systems to identify hidden threat material. Three specific scenarios are considered in some details: case 1--contraband material in the sea containers, case 2 - explosives in soil (landmines), case 3 - explosives and chemical warfare on the sea bottom. Effects of container cargo material on tagged neutron system are seen in the increase of gamma background and the decrease of neutron beam intensity. Detection of landmines is more complex because of variable soil properties. We have studied in detail space and time variations of soil elemental compositions and in particular hydrogen content (humidity). Of special interest are ammunitions and chemical warfare on the sea bottom, damping sites and leftovers from previous conflicts (WW-I, WW-II and local). In this case sea sediment is background source and its role is similar to the role of the soil in the landmine detection. In addition to geochemical cycling of chemical elements in semi-enclosed sea, like the Adriatic Sea, one has to consider also anthropogenic influence, especially when studying small scale variations in concentration levels. Some preliminary experimental results obtained with tagged neutron sensor inside an underwater vehicle are presented as well as data on sediment characterization by X-Ray Fluorescence.

  20. Vision-based threat detection in dynamic environments.

    SciTech Connect (OSTI)

    Carlson, Jeffrey J.

    2007-08-01

    This report addresses the development of automated video-screening technology to assist security forces in protecting our homeland against terrorist threats. A prevailing threat is the covert placement of bombs inside crowded public facilities. Although video-surveillance systems are increasingly common, current systems cannot detect the placement of bombs. It is also unlikely that security personnel could detect a bomb or its placement by observing video from surveillance cameras. The problems lie in the large number of cameras required to monitor large areas, the limited number of security personnel employed to protect these areas, and the intense diligence required to effectively screen live video from even a single camera. Different from existing video-detection systems designed to operate in nearly static environments, we are developing technology to detect changes in the background of dynamic environments: environments where motion and human activities are persistent over long periods. Our goal is to quickly detect background changes, even if the background is visible to the camera less than 5 percent of the time and possibly never free from foreground activity. Our approach employs statistical scene models based on mixture densities. We hypothesized that the background component of the mixture has a small variance compared to foreground components. Experiments demonstrate this hypothesis is true under a wide variety of operating conditions. A major focus involved the development of robust background estimation techniques that exploit this property. We desire estimation algorithms that can rapidly produce accurate background estimates and detection algorithms that can reliably detect background changes with minimal nuisance alarms. Another goal is to recognize unusual activities or foreground conditions that could signal an attack (e.g., large numbers of running people, people falling to the floor, etc.). Detection of background changes and/or unusual

  1. Introduction to Administrative Programs that Mitigate the Insider Threat

    SciTech Connect (OSTI)

    Gerke, Gretchen K.; Rogers, Erin; Landers, John; DeCastro, Kara

    2012-09-01

    This presentation begins with the reality of the insider threat, then elaborates on these tools to mitigate the insider threat: Human Reliability Program (HRP); Nuclear Security Culture (NSC) Program; Employee Assistance Program (EAP).

  2. Review and Approval of Nuclear Facility Safety Basis and Safety...

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

    104-2014, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents by Website Administrator This Standard describes a framework and the criteria to be...

  3. Deterring regional threats from nuclear proliferation

    SciTech Connect (OSTI)

    Spector, L.S.

    1992-03-12

    The most prominent shift in the National Military Strategy is from the global Soviet threat to a new focus on regional contingencies. No threat looms larger in these contingencies than the proliferation of nuclear weapons and ballistic missiles. This study examines proliferation trends and proposes a predominately diplomatic strategy for containing the problem. Dr. Spector identifies three waves of proliferation: the first is the five states with declared weapons and doctrine-the United States, Russia, Great Britain, France, and China; the second includes a less visible group that developed a covert capability, without testing weapons or declaring a doctrine of deterrence-for example, Israel, India, and probably Pakistan; and, a third wave of would-be proliferators includes radical states like Iraq, Iran, Libya, and North Korea. Spector's political approach is based on the common interest of wave one and two states to prevent further proliferation. Political-economic incentives have already worked in the cases of Brazil, Argentina, Taiwan, and South Africa-states which appear to have abandoned their nuclear weapons programs. Spector does not rule out the option of military force. Force, especially under international sanctions, can be a powerful tool to back diplomatic efforts. Use of force, however, remains a last resort.

  4. An Overview of Non-traditional Nuclear Threats

    SciTech Connect (OSTI)

    Geelhood, Bruce D.; Wogman, Ned A.

    2005-01-01

    In view of the terrorist threats to the United States, the country needs to consider new vectors and weapons related to nuclear and radiological threats against our homeland. The traditional threat vectors, missiles and bombers, have expanded to include threats arriving through the flow of commerce. The new commerce-related vectors include: sea cargo, truck cargo, rail cargo, and passenger transport. The types of weapons have also expanded beyond nuclear warheads to include radiation dispersal devices (RDD) or ''dirty'' bombs. The consequences of these nuclear and radiological threats are considered. The defense against undesirable materials entering our borders is considered. The radiation and other signatures or potential nuclear and radiological threats are examined along with potential sensors to discover undesirable items in the flow of commerce. Techniques to improve detection are considered. A strategy of primary and secondary screening is proposed to rapidly clear most cargo and carefully examine suspect cargo.

  5. GTRI: Reducing Nuclear Threats | National Nuclear Security Administration |

    National Nuclear Security Administration (NNSA)

    (NNSA) GTRI: Reducing Nuclear Threats May 29, 2014 Mission In 2004 NNSA established the Global Threat Reduction Initiative (GTRI) in the Office of Defense Nuclear Nonproliferation to, as quickly as possible, identify, secure, remove and/or facilitate the disposition of high risk vulnerable nuclear and radiological materials around the world that pose a threat to the United States and the international community. GTRI's mission is to reduce and protect vulnerable nuclear and radiological

  6. Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration | (NNSA) Insider Threat to Nuclear and Radiological Materials: Fact Sheet March 23, 2012 Almost all known cases of theft of nuclear material involved an insider. The threat of a nuclear facility insider, either individually or in collusion with an outsider, stealing fissile material or committing sabotage at a nuclear facility is a difficult one to accept and prevent. The skills, knowledge, access, and authority held by some insiders make the threat difficult

  7. NNSA's Global Threat Reduction Initiative Removes More Than One...

    National Nuclear Security Administration (NNSA)

    Global Threat Reduction Initiative Removes More Than One Ton of Food | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the...

  8. Mitigating the Insider Threat Using Behavioral Science Workshop

    SciTech Connect (OSTI)

    Landers, John; De Castro, Kara

    2012-11-26

    PowerPoint presentations are included on: the Insider Threat; Detecting the Malicious Insider through Behavioral Science; and Psychological Barriers to Effective Nuclear Security.

  9. ORISE: Securing the Golden State from threats foreign and domestic

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

    ORISE helps California emergency planners with innovative training on state and local levels To protect the state of California from both foreign and domestic threats, ORISE ...

  10. NNSA Launches Global Threat Reduction Initiative | National Nuclear...

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

    Launches Global Threat Reduction Initiative Vienna, Austria Secretary Abraham, in a speech to delegates at the International Energy Agency in Vienna, Austria, launches the...

  11. Cyber-Informed Engineering: The Need for a New Risk Informed and Design Methodology

    SciTech Connect (OSTI)

    Price, Joseph Daniel; Anderson, Robert Stephen

    2015-06-01

    Current engineering and risk management methodologies do not contain the foundational assumptions required to address the intelligent adversary’s capabilities in malevolent cyber attacks. Current methodologies focus on equipment failures or human error as initiating events for a hazard, while cyber attacks use the functionality of a trusted system to perform operations outside of the intended design and without the operator’s knowledge. These threats can by-pass or manipulate traditionally engineered safety barriers and present false information, invalidating the fundamental basis of a safety analysis. Cyber threats must be fundamentally analyzed from a completely new perspective where neither equipment nor human operation can be fully trusted. A new risk analysis and design methodology needs to be developed to address this rapidly evolving threatscape.

  12. Tank characterization technical sampling basis

    SciTech Connect (OSTI)

    Brown, T.M.

    1998-04-28

    Tank Characterization Technical Sampling Basis (this document) is the first step of an in place working process to plan characterization activities in an optimal manner. This document will be used to develop the revision of the Waste Information Requirements Document (WIRD) (Winkelman et al. 1997) and ultimately, to create sampling schedules. The revised WIRD will define all Characterization Project activities over the course of subsequent fiscal years 1999 through 2002. This document establishes priorities for sampling and characterization activities conducted under the Tank Waste Remediation System (TWRS) Tank Waste Characterization Project. The Tank Waste Characterization Project is designed to provide all TWRS programs with information describing the physical, chemical, and radiological properties of the contents of waste storage tanks at the Hanford Site. These tanks contain radioactive waste generated from the production of nuclear weapons materials at the Hanford Site. The waste composition varies from tank to tank because of the large number of chemical processes that were used when producing nuclear weapons materials over the years and because the wastes were mixed during efforts to better use tank storage space. The Tank Waste Characterization Project mission is to provide information and waste sample material necessary for TWRS to define and maintain safe interim storage and to process waste fractions into stable forms for ultimate disposal. This document integrates the information needed to address safety issues, regulatory requirements, and retrieval, treatment, and immobilization requirements. Characterization sampling to support tank farm operational needs is also discussed.

  13. NNSA deputy visits PNNL to see radiochemistry and threat detection

    National Nuclear Security Administration (NNSA)

    capabilities | National Nuclear Security Administration | (NNSA) visits PNNL to see radiochemistry and threat detection capabilities Friday, June 24, 2016 - 8:54am NNSA Principal Deputy Administrator Madelyn Creedon visited the Pacific Northwest National Laboratory (PNNL) in Washington this month to see the work it does for the agency, focusing on radiochemistry and threat detection. Creedon heard from Bob Runkle, PNNL's Chief Science and Technology Officer for National Security about the

  14. Protecting the Nation's Electric Grid from Cyber Threats | Department of

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

    Energy Nation's Electric Grid from Cyber Threats Protecting the Nation's Electric Grid from Cyber Threats January 11, 2012 - 11:28am Addthis A smarter, modernized, and more secure grid will be pivotal to the United States’ world leadership in a clean energy future. | Photo courtesy of National Renewable Energy Laboratory. A smarter, modernized, and more secure grid will be pivotal to the United States' world leadership in a clean energy future. | Photo courtesy of National Renewable

  15. EM threat analysis for wireless systems.

    SciTech Connect (OSTI)

    Burkholder, R. J. (Ohio State University Electroscience Laboratory); Mariano, Robert J.; Schniter, P. (Ohio State University Electroscience Laboratory); Gupta, I. J. (Ohio State University Electroscience Laboratory)

    2006-06-01

    Modern digital radio systems are complex and must be carefully designed, especially when expected to operate in harsh propagation environments. The ability to accurately predict the effects of propagation on wireless radio performance could lead to more efficient radio designs as well as the ability to perform vulnerability analyses before and after system deployment. In this report, the authors--experts in electromagnetic (EM) modeling and wireless communication theory--describe the construction of a simulation environment that is capable of quantifying the effects of wireless propagation on the performance of digital communication.

  16. Detecting Nuclear Threats | U.S. DOE Office of Science (SC)

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

    Detecting Nuclear Threats Stories of Discovery & Innovation Detecting Nuclear Threats Enlarge Photo Photo: Denise Applewhite The MINDS device was invented by a team of engineers at ...

  17. Fact Sheet: Detection and Analysis of Threats to the Energy Sector...

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

    event management, and sector-wide threat analysis Detecting cyber attacks against digital control systems quickly ... DATES will create an anonymous global threat database, ...

  18. Resilient Control Systems Practical Metrics Basis for Defining Mission Impact

    SciTech Connect (OSTI)

    Craig G. Rieger

    2014-08-01

    "Resilience” describes how systems operate at an acceptable level of normalcy despite disturbances or threats. In this paper we first consider the cognitive, cyber-physical interdependencies inherent in critical infrastructure systems and how resilience differs from reliability to mitigate these risks. Terminology and metrics basis are provided to integrate the cognitive, cyber-physical aspects that should be considered when defining solutions for resilience. A practical approach is taken to roll this metrics basis up to system integrity and business case metrics that establish “proper operation” and “impact.” A notional chemical processing plant is the use case for demonstrating how the system integrity metrics can be applied to establish performance, and

  19. Basis

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

    This has a number of advantages, such as reduced dataset requirements, ability to ... then solve for these coefficients using statistical correlations in the dataset. ...

  20. Basis

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

    that this equation is a difference- equation representation in the temporal domain of a first- order-in-time nonlinear partial differential equation. The co- efficient L k...

  1. Autonomic Computing: Freedom or a Threat?

    SciTech Connect (OSTI)

    Fink, Glenn A.; Frincke, Deb

    2007-12-01

    No longer is the question whether autonomic computing will gain general acceptance but when. Experts expect autonomic computing to be widely used within 10 years. When it does become mainstream, how will autonomics change system administration and corporations, and will the change be for better or worse? The answer depends on how well we anticipate the limitations of what autonomic systems are suited to do, whether we can collectively address the vulnerabilities of autonomic approaches as we draw upon the advantages, and whether administrators, companies, partners, and users are prepared for the transition. This article presents some design considerations to address the first two issues and some suggested survival techniques for the third.

  2. CRAD, NNSA- Safety Basis (SB)

    Broader source: Energy.gov [DOE]

    CRAD for Safety Basis (SB). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs.

  3. COLLOQUIUM: The Evolving Terrorist Threat | Princeton Plasma Physics Lab

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

    April 6, 2016, 4:15pm to 5:30pm Colloquia MBG Auditorium, 284 cap. COLLOQUIUM: The Evolving Terrorist Threat Mitchell Silber FTI Consulting Evolution of the Terrorist Threat What is behind the genesis of terrorist sanctuaries, foreign fighters and crowdsourced jihad? How and why did they move to the fore in the latter part of 2015 with such events like Paris, Sharm el Sheikh, and San Bernardino? What do we know about the factors underpinning each of these important trends? What is the

  4. The Basis Code Development System

    Energy Science and Technology Software Center (OSTI)

    1994-03-15

    BASIS9.4 is a system for developing interactive computer programs in Fortran, with some support for C and C++ as well. Using BASIS9.4 you can create a program that has a sophisticated programming language as its user interface so that the user can set, calculate with, and plot, all the major variables in the program. The program author writes only the scientific part of the program; BASIS9.4 supplies an environment in which to exercise that scientificmore » programming which includes an interactive language, an interpreter, graphics, terminal logs, error recovery, macros, saving and retrieving variables, formatted I/O, and online documentation.« less

  5. Secretarial Succession, Threat Level Notification and Successor Tracking

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

    2013-01-28

    The Order establishes the Secretarial Order of Succession pursuant to section 202(a) of the Department of Energy Organization Act, 42 U.S.C. 7132(a) and establishes a mechanism for tracking the locations of successors at various threat levels. Cancels DOE O 100.1D.

  6. Secretarial Succession, Threat Level Notification, and Successor Tracking

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

    2007-04-20

    This Order establishes the Secretarial Order of Succession pursuant to section 202(a) of the Department of Energy Organization Act and establishes a mechanism for tracking the locations of successors at various threat levels. Supersedes DOE O 100.1C. Superseded by DOE O 100.1E

  7. Defense Threat Reduction Agency | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Defense Threat Reduction Agency NNSA Administrator honors nonproliferation research leader Last week DOE Under Secretary for Nuclear Security and NNSA Administrator Lt. Gen. Frank G. Klotz (Ret.) presented the agency's Assistant Deputy Administrator for Nonproliferation Research and Development (R&D) Dr. Rhys Williams with the Distinguished Service Gold Medal Award at a

  8. Secretarial Succession, Threat Level Notification, and Successor Tracking

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

    2013-01-28

    This order establishes the Secretarial Order of Succession in the Department of Energy pursuant to section 202(a) of the Department of Energy Organization Act, 42 U.S.C. 7132(a) and establish a mechanism for tracking the locations of successors at the various threat levels. Admin Chg 1, dated 9-13-2013, supersedes DOE O 100.1E.

  9. Authorization basis requirements comparison report

    SciTech Connect (OSTI)

    Brantley, W.M.

    1997-08-18

    The TWRS Authorization Basis (AB) consists of a set of documents identified by TWRS management with the concurrence of DOE-RL. Upon implementation of the TWRS Basis for Interim Operation (BIO) and Technical Safety Requirements (TSRs), the AB list will be revised to include the BIO and TSRs. Some documents that currently form part of the AB will be removed from the list. This SD identifies each - requirement from those documents, and recommends a disposition for each to ensure that necessary requirements are retained when the AB is revised to incorporate the BIO and TSRs. This SD also identifies documents that will remain part of the AB after the BIO and TSRs are implemented. This document does not change the AB, but provides guidance for the preparation of change documentation.

  10. Hanford Generic Interim Safety Basis

    SciTech Connect (OSTI)

    Lavender, J.C.

    1994-09-09

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

  11. Raising consciousness about the nuclear threat through music

    SciTech Connect (OSTI)

    Ungerleider, J.H.

    1987-01-01

    This dissertation examines the use of music, in particular topical collaborative group song writing, as a tool for raising consciousness about the threat of nuclear war. Consciousness raising is one way to overcome the phenomenon of denial and to increase discussion and social action in response to the nuclear threat. This dissertation measures the impact of a group song writing workshop on developing critical problem-solving in adult groups; it reviews how music is applied in psychological research and clinical work, has been used historically as a tool in social-change movements in America, and is used in the contemporary field of peace education. The perspectives of several theorists who discuss the potential of music to contribute to social change are presented. It is concluded that consciousness about the nuclear threat - in terms of naming and analyzing - can be raised by working with music's potential for developing affective, expressive, and collaborative capabilities in individuals and groups. Potential applications of the group song writing workshop are in schools, with peace organizations, music groups, and in relation to other social issues.

  12. Future land use threats to range-restricted fish species in the...

    Office of Scientific and Technical Information (OSTI)

    Future land use threats to range-restricted fish species in the United States Citation ... Title: Future land use threats to range-restricted fish species in the United States Land ...

  13. Notice of Intent to Develop DOE O 470.X, Insider Threat Program

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

    2013-10-17

    The Order establishes top-level responsibilities and requirements for DOE's Insider Threat Program, which is intended to deter, detect, and mitigate insider threat actions by all Federal and contractor employees.

  14. Jefferson Lab to Conduct Active Threat Response Exercise on June 11 |

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

    Jefferson Lab Active Threat Response Exercise on June 11 Jefferson Lab to Conduct Active Threat Response Exercise on June 11 NEWPORT NEWS, VA, June 10, 2014 - On the afternoon of June 11, staff at the Thomas Jefferson National Accelerator Facility will participate in an active threat in the workplace response exercise. The objective of the exercise is to gauge the Jefferson Lab community's response to an active threat incident. The exercise is intended to provide a training opportunity for

  15. OSR encapsulation basis -- 100-KW

    SciTech Connect (OSTI)

    Meichle, R.H.

    1995-01-27

    The purpose of this report is to provide the basis for a change in the Operations Safety Requirement (OSR) encapsulated fuel storage requirements in the 105 KW fuel storage basin which will permit the handling and storing of encapsulated fuel in canisters which no longer have a water-free space in the top of the canister. The scope of this report is limited to providing the change from the perspective of the safety envelope (bases) of the Safety Analysis Report (SAR) and Operations Safety Requirements (OSR). It does not change the encapsulation process itself.

  16. Molecular Design Basis for Hydrogen Storage in Clathrate Hydrates

    SciTech Connect (OSTI)

    John, Vijay T; McPherson, Gary L; Ashbaugh, Hank; Johnes, Camille Y

    2013-06-28

    We attach a final technical report for the project. The report contains the list of all peer reviewed publications that have resulted from the contract. I will be happy to send the pdf files of the papers.

  17. Perspective on Beyond Design Basis Event Analysis and Response

    Broader source: Energy.gov [DOE]

    Presenter: John Schwenker, Nuclear Safety Manager for Liquid Operations, Savannah River Remediation, LLC, Savannah River Site

  18. Development of Guidance for Analysis of Beyond Design Basis Events

    Broader source: Energy.gov [DOE]

    Presenter: Dr. James O'Brien, Director, Office of Nuclear Safety, Office of Health, Safety and Security, US Department of Energy

  19. Beyond Design Basis Events Analysis and Response Information...

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

    Fact Finding Expert Mission of the Fukushima Dai-ichi Accident Following the Great East Japan Earthquake And Tsunami, June 16, 2011 INPO Special Report - Lessons Learned from the...

  20. Internal dosimetry technical basis manual

    SciTech Connect (OSTI)

    Not Available

    1990-12-20

    The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.

  1. Taking Steps to Protect Against the Insider Threat

    SciTech Connect (OSTI)

    Pope, Noah Gale; Williams, Martha; Lewis, Joel; Pham, Thomas

    2015-10-16

    Research reactors are required (in accordance with the Safeguards Agreement between the State and the IAEA) to maintain a system of nuclear material accounting and control for reporting quantities of nuclear material received, shipped, and held on inventory. Enhancements to the existing accounting and control system can be made at little additional cost to the facility, and these enhancements can make nuclear material accounting and control useful for nuclear security. In particular, nuclear material accounting and control measures can be useful in protecting against an insider who is intent on unauthorized removal or misuse of nuclear material or misuse of equipment. An enhanced nuclear material accounting and control system that responds to nuclear security is described in NSS-25G, Use of Nuclear Material Accounting and Control for Nuclear Security Purposes at Facilities, which is scheduled for distribution by the IAEA Department of Nuclear Security later this year. Accounting and control measures that respond to the insider threat are also described in NSS-33, Establishing a System for Control of Nuclear Material for Nuclear Security Purposes at a Facility During Storage, Use and Movement, and in NSS-41, Preventive and Protective Measures against Insider Threats (originally issued as NSS-08), which are available in draft form. This paper describes enhancements to existing material control and accounting systems that are specific to research reactors, and shows how they are important to nuclear security and protecting against an insider.

  2. Social/Ethical Issues in Predictive Insider Threat Monitoring

    SciTech Connect (OSTI)

    Greitzer, Frank L.; Frincke, Deborah A.; Zabriskie, Mariah

    2011-01-01

    Combining traditionally monitored cybersecurity data with other kinds of organizational data is one option for inferring the motivations of individuals, which may in turn allow early prediction and mitigation of insider threats. While unproven, some researchers believe that this combination of data may yield better results than either cybersecurity or organizational data would in isolation. However, this nontraditional approach creates a potential conflict between goals, such as conflicts between organizational security improvements and individual privacy considerations. There are many facets to debate. Should warning signs of a potential malicious insider be addressed before a malicious event has occurred to prevent harm to the organization and discourage the insider from violating the organization’s rules? Would intervention violate employee trust or legal guidelines? What about the possibilities of misuse? Predictive approaches cannot be validated a priori; false accusations can affect the career of the accused; and collection/monitoring of certain types of data may affect employee morale. In this chapter, we explore some of the social and ethical issues stemming from predictive insider threat monitoring and discuss ways that a predictive modeling approach brings to the forefront social and ethical issues that should be considered and resolved by stakeholders and communities of interest.

  3. A Risk Management Approach to the "Insider Threat"

    SciTech Connect (OSTI)

    Bishop, Matt; Engle, Sophie J.; Frincke, Deborah A.; Gates, Carrie; Greitzer, Frank L.; Peisert, Sean; Whalen, Sean

    2010-09-01

    Abstract Recent surveys indicate that the financial impact and operating losses due to insider intrusions are increasing. But these studies often disagree on what constitutes an insider; indeed, many define it only implicitly. In theory, appropriate selection of, and enforcement of, properly specified security policies should prevent legitimate users from abusing their access to computer systems, information, and other resources. However, even if policies could be expressed precisely, the natural mapping between the natural language expression of a security policy, and the expression of that policy in a form that can be implemented on a computer system or network, creates gaps in enforcement. This paper defines insider precisely, in terms of these gaps, and explores an access-based model for analyzing threats that include those usually termed insider threats. This model enables an organization to order its resources based on the business value for that resource and of the information it contains. By identifying those users with access to high-value resources, we obtain an ordered list of users who can cause the greatest amount of damage. Concurrently with this, we examine psychological indicators in order to determine which users are at the greatest risk of acting inappropriately.We conclude by examining how to merge this model with one of forensic logging and auditing.

  4. Neutron Interrogation System For Underwater Threat Detection And Identification

    SciTech Connect (OSTI)

    Barzilov, Alexander P.; Novikov, Ivan S.; Womble, Phil C.

    2009-03-10

    Wartime and terrorist activities, training and munitions testing, dumping and accidents have generated significant munitions contamination in the coastal and inland waters in the United States and abroad. Although current methods provide information about the existence of the anomaly (for instance, metal objects) in the sea bottom, they fail to identify the nature of the found objects. Field experience indicates that often in excess of 90% of objects excavated during the course of munitions clean up are found to be non-hazardous items (false alarm). The technology to detect and identify waterborne or underwater threats is also vital for protection of critical infrastructures (ports, dams, locks, refineries, and LNG/LPG). We are proposing a compact neutron interrogation system, which will be used to confirm possible threats by determining the chemical composition of the suspicious underwater object. The system consists of an electronic d-T 14-MeV neutron generator, a gamma detector to detect the gamma signal from the irradiated object and a data acquisition system. The detected signal then is analyzed to quantify the chemical elements of interest and to identify explosives or chemical warfare agents.

  5. BASIS Set Exchange (BSE): Chemistry Basis Sets from the William R. Wiley Environmental Molecular Sciences Laboratory (EMSL) Basis Set Library

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

    Feller, D; Schuchardt, Karen L.; Didier, Brett T.; Elsethagen, Todd; Sun, Lisong; Gurumoorthi, Vidhya; Chase, Jared; Li, Jun

    The Basis Set Exchange (BSE) provides a web-based user interface for downloading and uploading Gaussian-type (GTO) basis sets, including effective core potentials (ECPs), from the EMSL Basis Set Library. It provides an improved user interface and capabilities over its predecessor, the EMSL Basis Set Order Form, for exploring the contents of the EMSL Basis Set Library. The popular Basis Set Order Form and underlying Basis Set Library were originally developed by Dr. David Feller and have been available from the EMSL webpages since 1994. BSE not only allows downloading of the more than 200 Basis sets in various formats; it allows users to annotate existing sets and to upload new sets. (Specialized Interface)

  6. BASIS Set Exchange (BSE): Chemistry Basis Sets from the William R. Wiley Environmental Molecular Sciences Laboratory (EMSL) Basis Set Library

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

    Feller, D; Schuchardt, Karen L.; Didier, Brett T.; Elsethagen, Todd; Sun, Lisong; Gurumoorthi, Vidhya; Chase, Jared; Li, Jun

    The Basis Set Exchange (BSE) provides a web-based user interface for downloading and uploading Gaussian-type (GTO) basis sets, including effective core potentials (ECPs), from the EMSL Basis Set Library. It provides an improved user interface and capabilities over its predecessor, the EMSL Basis Set Order Form, for exploring the contents of the EMSL Basis Set Library. The popular Basis Set Order Form and underlying Basis Set Library were originally developed by Dr. David Feller and have been available from the EMSL webpages since 1994. BSE not only allows downloading of the more than 500 Basis sets in various formats; it allows users to annotate existing sets and to upload new sets. (Specialized Interface)

  7. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

    2008-03-01

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules—23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

  8. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

    2009-12-01

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules—23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

  9. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert

    2007-04-01

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 26 cost modules—24 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, and high-level waste.

  10. Establishing a Cost Basis for Converting the High Flux Isotope Reactor from High Enriched to Low Enriched Uranium Fuel

    SciTech Connect (OSTI)

    Primm, Trent; Guida, Tracey

    2010-02-01

    Under the auspices of the Global Threat Reduction Initiative Reduced Enrichment for Research and Test Reactors Program, the National Nuclear Security Administration /Department of Energy (NNSA/DOE) has, as a goal, to convert research reactors worldwide from weapons grade to non-weapons grade uranium. The High Flux Isotope Reactor (HFIR) at Oak Ridge National Lab (ORNL) is one of the candidates for conversion of fuel from high enriched uranium (HEU) to low enriched uranium (LEU). A well documented business model, including tasks, costs, and schedules was developed to plan the conversion of HFIR. Using Microsoft Project, a detailed outline of the conversion program was established and consists of LEU fuel design activities, a fresh fuel shipping cask, improvements to the HFIR reactor building, and spent fuel operations. Current-value costs total $76 million dollars, include over 100 subtasks, and will take over 10 years to complete. The model and schedule follows the path of the fuel from receipt from fuel fabricator to delivery to spent fuel storage and illustrates the duration, start, and completion dates of each subtask to be completed. Assumptions that form the basis of the cost estimate have significant impact on cost and schedule.

  11. Safety Basis Information System | Department of Energy

    Energy Savers [EERE]

    Click on the above link to log in to the Safety Basis web interface. "RESTRICTED; access ... Click on the above link to access the form to request access to the Safety Basis web ...

  12. INTERNATIONAL COOPERATION ON RADIOLOGICAL THREAT REDUCTION PROGRAMS IN RUSSIA

    SciTech Connect (OSTI)

    Landers, Christopher C.; Tatyrek, Aaron P.

    2009-10-07

    Since its inception in 2004, the United States Department of Energy’s Global Threat Reduction Initiative (GTRI) has provided the Russian Federation with significant financial and technical assistance to secure its highly vulnerable and dangerous radiological material. The three program areas of this assistance are the removal of radioisotope thermoelectric generators (RTG), the physical protection of vulnerable in-use radiological material of concern, and the recovery of disused or abandoned radiological material of concern. Despite the many successes of the GTRI program in Russia, however, there is still a need for increased international cooperation in these efforts. Furthermore, concerns exist over how the Russian government will ensure that the security of its radiological materials provided through GTRI will be sustained. This paper addresses these issues and highlights the successes of GTRI efforts and ongoing activities.

  13. The Global Threat Reduction Initiative's Molybdenum-99 Program, OAS-L-12-07

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

    Audit Report The Global Threat Reduction Initiative's Molybdenum-99 Program OAS-L-12-07 July 2012 Department of Energy Washington, DC 20585 July 20, 2012 MEMORANDUM FOR THE ASSISTANT DEPUTY ADMINISTRATOR FOR GLOBAL THREAT REDUCTION, NATIONAL NUCLEAR SECURITY ADMINISTRATION FROM: David Sedillo, Director Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Audit Report on "The Global Threat Reduction Initiative's Molybdenum-99 Program" BACKGROUND Molybdenum-99

  14. Future land use threats to range-restricted fish species in the United States

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

    Januchowski-Hartley, Stephanie R.; Holtz, Lauren A.; Martinuzzi, Sebastian; McIntyre, Peter B.; Radeloff, Volker C.; Pracheil, Brenda M.

    2016-03-04

    Land use change is one major threat to freshwater biodiversity, and land use change scenarios can help to assess threats from future land use change, thereby guiding proactive conservation decisions. Furthermore, our goal was to identify which range-restricted freshwater fish species are most likely to be affected by land use change and to determine where threats to these species from future land use change in the conterminous United States are most pronounced.

  15. Working to keep us safe: Sara Brambilla, Postdoc creates threat reduction

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

    tools Inspire » Working to keep us safe: Postdoc creates threat reduction tools Working to keep us safe: Sara Brambilla, Postdoc creates threat reduction tools Chemical engineer postdoc experiences a foreign culture while working on resources that respond to weapons of mass destruction and natural threats. July 18, 2012 image description Brambilla first came to Los Alamos as a visiting student during her PhD program at the Politecnico di Milano, Italy, which required an internship abroad.

  16. Cybersecurity and Emerging Threats Research and Development (CET R&D) |

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

    Department of Energy Mission » Cybersecurity and Emerging Threats Research and Development (CET R&D) Cybersecurity and Emerging Threats Research and Development (CET R&D) cybersecurity r&d resize.jpg The Cybersecurity and Emerging Threats Research and Development (CET R&D) Division advances the research and development of innovative technologies, tools, and techniques to reduce risks to the Nation's critical energy infrastructure posed by cyber and other emerging

  17. How ORISE is Making a Difference: Preparing for the Threat of...

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

    exercise to help agencies prepare for the threat of dirty bombs Radiological dispersion devices (RDDs), also known as dirty bombs, are conventional explosives packed with...

  18. 2014 Annual Planning Summary for the NNSA Global Threat Reduction Initiative Office

    Broader source: Energy.gov [DOE]

    The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2014 and 2015 within the NNSA Global Threat Reduction Initiative Office.

  19. Prevent, Counter, and Respond - A Strategic Plan to Reduce Global Nuclear Threats (FY 2016-FY2020)

    SciTech Connect (OSTI)

    2015-03-01

    NNSA’s second core mission is reducing global nuclear dangers by preventing the acquisition of nuclear weapons or weapons-usable materials, countering efforts to acquire such weapons or materials, and responding to nuclear or radiological incidents. In 2015, NNSA reorganized its nonproliferation activities based on core competencies and realigned its counterterrorism and counterproliferation functions to more efficiently address both current and emerging threats and challenges. The reorganization accompanied the March 2015 release of the first ever Prevent, Counter, and Respond – A Strategic Plan to Reduce Global Nuclear Threats. This report, which NNSA will update annually, highlights key nuclear threat trends and describes NNSA’s integrated threat reduction strategy.

  20. The application of nuclear and national security safeguard strategies to the insider threat in the private sector

    SciTech Connect (OSTI)

    Campbell, G.K. )

    1991-01-01

    This paper reports that the insider threat in commercial enterprises represents multi-billion dollar losses on an annual basis. While much of this experience is in low value, theft-related shrinkage, there are a growing number of organizations where the loss or compromise of critical assets or interruption of vital systems cannot be tolerated. In very real ways, the survival of the organization may turn on the hostile acts of knowledgeable insiders. The nuclear and National security information operations environments represents a baseline of experience from which the corporate world can draw for cost-effective, alternative approaches to this threat. However, it is equally clear that there are a variety of subtle and obvious constraints imposed by the private sector's mission, service delivery, lifestyle and cost-benefit requirements which dictate careful planning and user involvement in safeguards development and application. Where protection of our National security assets are grounded in a consequence-driven set of policies and standards, the private sector is often subject to the lack of a similar (but directly analogous) policy foundation.

  1. Property:ExplorationBasis | Open Energy Information

    Open Energy Info (EERE)

    Text Description Exploration Basis Why was exploration work conducted in this area (e.g., USGS report of a geothermal resource, hot springs with geothemmetry indicating...

  2. Structural basis for Tetrahymena telomerase processivity factor...

    Office of Scientific and Technical Information (OSTI)

    factor Teb1 binding to single-stranded telomeric-repeat DNA Citation Details In-Document Search Title: Structural basis for Tetrahymena telomerase processivity factor Teb1 ...

  3. Insider Threat - Material Control and Accountability Mitigation (Presentation)

    SciTech Connect (OSTI)

    Powell, Danny H; Elwood Jr, Robert H

    2011-01-01

    Why is the insider a concern? There are many documented cases of nuclear material available for sale - there are more insider diversions than outsider attacks and more than 18 documented cases of theft or loss of plutonium or highly enriched uranium. Insider attributes are: have access, has authority, possesses knowledge, works with absence of timeline, can test system, and may act alone or support a team. Material control and accountability (MC&A) is an essential part of an integrated safeguards system. Objectives of MC&A are: (1) Ongoing confirmation of the presence of special nuclear material (SNM) in assigned locations; (2) Prompt investigation of anomalies that may indicate a loss of SNM; (3) Timely and localized detection of loss, diversion, or theft of a goal quantity; (4) Rapid assessment and response to detection alarms; and (5) Timely generation of information to aid in the recovery of SNM in the event of an actual loss, diversion, or theft from the purview of the MC&A system. Control and accountability of material, equipment, and data are essential to minimizing insider threats.

  4. Psychological responses to the threat of nuclear war

    SciTech Connect (OSTI)

    McClenney, J.E.

    1987-01-01

    A series of three studies explored psychological responses to the threat of nuclear war, and the relationship between attitudes and behavior on this issue. The first was a quasi-experimental study of the influence of exposure to a media depiction of nuclear war, The Day After, on attitudes and behavior, and the influence of such attitudinal variables as denial, perception of control, perception of responsibility, survivability, and spiritual orientation, on the decision to view this film. No effects were found for exposure, but those who experienced a greater sense of control over political events were more likely to view the film. The second study was an experiment on the effects of efficacy enhancing, fear arousing or informational communications, in combination with the previously mentioned attitudinal variables, on retention of relevant information, intentions to act, and political activism on the nuclear arms issue. Fear arousal was found to increase activism for women, but to decrease activism for men. The third study employed structural modeling to examine the relationship between attitudes and behavior on the issue of nuclear war, using data from the experiment. The model supported in this study showed that intentions were directly affected by denial and a sense of power over political events.

  5. Summary of Audit Report: OAS-L-09-02 | Department of Energy

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

    Energy (Department) developed the Design Basis Threat policy (DBT), which identified the most credible threats posed by potential adversaries to Departmental assets and operations. ...

  6. Integrating Safeguards and Security with Safety into Design

    SciTech Connect (OSTI)

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

    2009-05-01

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

  7. Engineering basis for operator control of nuclear power stations in abnormal operations - closing the loop

    SciTech Connect (OSTI)

    Womack, E.A.; Kelly, J.J.; Elliott, N.S.

    1980-01-01

    The Abnormal Transient Operating Guidelines (ATOG) Program is intended to ''close the loop'' on a continuing basis between the engineering designers/performance analysts and the operators who control the plant. It will make the technical basis for operation responsive to information from the study of actual plant transients, as well as new developments in engineering.

  8. Global Threat Reduction Initiative Fuel-Thermo-Physical Characterization Project Quality Assurance Plan

    SciTech Connect (OSTI)

    Pereira, Mario M.; Slonecker, Bruce D.

    2012-06-01

    The charter of the Fuel Thermo-Physical Characterization Project is to ready Pacific Northwest National Laboratory (PNNL) facilities and processes for the receipt of unirradiated and irradiated low enriched uranium (LEU) molybdenum (U-Mo) fuel element samples, and to perform analysis to support the Global Threat Reduction Initiative conversion program. PNNL’s support for the program will include the establishment of post-irradiation examination processes, including thermo-physical properties, unique to the U.S. Department of Energy laboratories. These processes will ultimately support the submission of the base fuel qualification (BFQ) to the U.S. Nuclear Regulatory Commission (NRC) and revisions to High Performance Research Reactor Safety Analysis Reports to enable conversion from highly enriched uranium to LEU fuel. This quality assurance plan (QAP) provides the quality assurance requirements and processes that support the NRC BFQ. This QAP is designed to be used by project staff, and prescribes the required management control elements that are to be met and how they are implemented. Additional controls are captured in Fuel Thermo-Physical Characterization Project plans, existing procedures, and procedures to be developed that provide supplemental information on how work is conducted on the project.

  9. Safety Basis Information System | Department of Energy

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

    Request Click on the above link to access the form to request access to the Safety Basis web interface. If you need assistance logging in, please AU UserSupport. Contact Nimi Rao...

  10. Detection and Analysis of Threats to the Energy Sector: DATES

    SciTech Connect (OSTI)

    Alfonso Valdes

    2010-03-31

    This report summarizes Detection and Analysis of Threats to the Energy Sector (DATES), a project sponsored by the United States Department of Energy and performed by a team led by SRI International, with collaboration from Sandia National Laboratories, ArcSight, Inc., and Invensys Process Systems. DATES sought to advance the state of the practice in intrusion detection and situational awareness with respect to cyber attacks in energy systems. This was achieved through adaptation of detection algorithms for process systems as well as development of novel anomaly detection techniques suited for such systems into a detection suite. These detection components, together with third-party commercial security systems, were interfaced with the commercial Security Information Event Management (SIEM) solution from ArcSight. The efficacy of the integrated solution was demonstrated on two testbeds, one based on a Distributed Control System (DCS) from Invensys, and the other based on the Virtual Control System Environment (VCSE) from Sandia. These achievements advance the DOE Cybersecurity Roadmap [DOE2006] goals in the area of security monitoring. The project ran from October 2007 until March 2010, with the final six months focused on experimentation. In the validation phase, team members from SRI and Sandia coupled the two test environments and carried out a number of distributed and cross-site attacks against various points in one or both testbeds. Alert messages from the distributed, heterogeneous detection components were correlated using the ArcSight SIEM platform, providing within-site and cross-site views of the attacks. In particular, the team demonstrated detection and visualization of network zone traversal and denial-of-service attacks. These capabilities were presented to the DistribuTech Conference and Exhibition in March 2010. The project was hampered by interruption of funding due to continuing resolution issues and agreement on cost share for four months in 2008

  11. Basis for UCNI | Department of Energy

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

    UCNI Basis for UCNI What documents contain the legal and policy foundations for the UCNI program? Section 148 of the Atomic Energy Act of 1954, as amended (42 U.S.C. 2011 et seq.), is the statutory basis for the UCNI program. 10 CFR Part 1017, Identification and Protection of Unclassified Controlled Nuclear Information specifies many detailed policies and requirements concerning the UCNI program. DOE O 471.1B, Identification and Protection of Unclassified Controlled Nuclear Information,

  12. Open PCS Security Architecture For Interoperable Design (OPSAID...

    Office of Environmental Management (EM)

    Open PCS Security Architecture For Interoperable Design (OPSAID) Open PCS Security Architecture For Interoperable Design (OPSAID) The OPSAID program provides a design basis for ...

  13. Nanoplasmonics simulations at the basis set limit through completeness-optimized, local numerical basis sets

    SciTech Connect (OSTI)

    Rossi, Tuomas P. Sakko, Arto; Puska, Martti J.; Lehtola, Susi; Nieminen, Risto M.

    2015-03-07

    We present an approach for generating local numerical basis sets of improving accuracy for first-principles nanoplasmonics simulations within time-dependent density functional theory. The method is demonstrated for copper, silver, and gold nanoparticles that are of experimental interest but computationally demanding due to the semi-core d-electrons that affect their plasmonic response. The basis sets are constructed by augmenting numerical atomic orbital basis sets by truncated Gaussian-type orbitals generated by the completeness-optimization scheme, which is applied to the photoabsorption spectra of homoatomic metal atom dimers. We obtain basis sets of improving accuracy up to the complete basis set limit and demonstrate that the performance of the basis sets transfers to simulations of larger nanoparticles and nanoalloys as well as to calculations with various exchange-correlation functionals. This work promotes the use of the local basis set approach of controllable accuracy in first-principles nanoplasmonics simulations and beyond.

  14. Cutoff walls and cap for lime and M-1 settling basins, Rocky Mountain Arsenal, Colorado. Part 1: Final design analysis. Final report

    SciTech Connect (OSTI)

    1990-10-01

    This document consists of 2 parts, final design analysis and specifications. The purpose of the project was to develop a design for the Interim Response Actions (IRA) at the Lime and M-l Settling Basins at Rocky Mountain Arsenal (RMA), Commerce City, Colorado. The purpose of the IRA at the Lime and M-l Settling Basins is to mitigate the threat of release from the Basins on an interim basis, pending determination of the final remedy in the Onpost Record of Decision (ROD). The IRA for the M-l Basins also includes treatment of the waste materials in the basins with in-situ vitrification (ISV), which is being designed by contract with Woodward-Clyde Consultants.

  15. Sequential Threat Detection for Harbor Defense: An X-ray Physics...

    Office of Scientific and Technical Information (OSTI)

    Sequential Threat Detection for Harbor Defense: An X-ray Physics-Based Bayesian Approach Candy, J V 42 ENGINEERING; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS Abstract not provided...

  16. Anomaly metrics to differentiate threat sources from benign sources in primary vehicle screening.

    SciTech Connect (OSTI)

    Cohen, Israel Dov; Mengesha, Wondwosen

    2011-09-01

    Discrimination of benign sources from threat sources at Port of Entries (POE) is of a great importance in efficient screening of cargo and vehicles using Radiation Portal Monitors (RPM). Currently RPM's ability to distinguish these radiological sources is seriously hampered by the energy resolution of the deployed RPMs. As naturally occurring radioactive materials (NORM) are ubiquitous in commerce, false alarms are problematic as they require additional resources in secondary inspection in addition to impacts on commerce. To increase the sensitivity of such detection systems without increasing false alarm rates, alarm metrics need to incorporate the ability to distinguish benign and threat sources. Principal component analysis (PCA) and clustering technique were implemented in the present study. Such techniques were investigated for their potential to lower false alarm rates and/or increase sensitivity to weaker threat sources without loss of specificity. Results of the investigation demonstrated improved sensitivity and specificity in discriminating benign sources from threat sources.

  17. Sequential Threat Detection for Harbor Defense: An X-ray Physics...

    Office of Scientific and Technical Information (OSTI)

    Defense: An X-ray Physics-Based Bayesian Approach Citation Details In-Document Search Title: Sequential Threat Detection for Harbor Defense: An X-ray Physics-Based Bayesian ...

  18. Tackling the Triple-Threat Genome of Miscanthus x giganteus (2010 JGI User Meeting)

    ScienceCinema (OSTI)

    Moose, Steve

    2011-04-25

    Steve Moose from the University of Illinois at Urbana-Champaign and the Energy Biosciences Institute on "Tackling the Triple-Threat Genome of Miscanthus x giganteus" on March 25, 2010 at the 5th Annual DOE JGI User Meeting

  19. Prototype integration of the joint munitions assessment and planning model with the OSD threat methodology

    SciTech Connect (OSTI)

    Lynn, R.Y.S.; Bolmarcich, J.J.

    1994-06-01

    The purpose of this Memorandum is to propose a prototype procedure which the Office of Munitions might employ to exercise, in a supportive joint fashion, two of its High Level Conventional Munitions Models, namely, the OSD Threat Methodology and the Joint Munitions Assessment and Planning (JMAP) model. The joint application of JMAP and the OSD Threat Methodology provides a tool to optimize munitions stockpiles. The remainder of this Memorandum comprises five parts. The first is a description of the structure and use of the OSD Threat Methodology. The second is a description of JMAP and its use. The third discusses the concept of the joint application of JMAP and OSD Threat Methodology. The fourth displays sample output of the joint application. The fifth is a summary and epilogue. Finally, three appendices contain details of the formulation, data, and computer code.

  20. CRAD, Review of Safety Basis Development - May 6, 2013 | Department of

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

    Energy Review of Safety Basis Development - May 6, 2013 CRAD, Review of Safety Basis Development - May 6, 2013 May 6, 2013 Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility (HSS CRAD 45-59, Rev. 0) The review will consider selected aspects of the development of safety basis for the Transuranic Waste Facility (TWF) to assess the extent to which safety is integrated into the design of the TWF in accordance with DOE directives; in particular,

  1. Emerging threats to global security focus of March 12 talk at Bradbury

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

    Science Museum Emerging threats to global security talk March 12 Emerging threats to global security focus of March 12 talk at Bradbury Science Museum Terry Wallace will focus on how the Lab will address these issues and help the government respond. March 6, 2014 Terry Wallace, principal associate director for Global Security Terry Wallace, principal associate director for Global Security Contact Steve Sandoval Communications Office (505) 665-9206 Email During the next 20 years, as the

  2. Microsoft Word - Threat Analysis Framework Sept07_comments-final.doc

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

    5792 Unlimited Release September 2007 Threat Analysis Framework David P. Duggan and John T. Michalski Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04-94AL85000. Approved for public release; further dissemination unlimited. Threat Analysis

  3. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Structural Basis for Activation of Cholera Toxin Print Wednesday, 30 November 2005 00:00 Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit

  4. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2005-02-25

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database.

  5. TWRS authorization basis configuration control summary

    SciTech Connect (OSTI)

    Mendoza, D.P.

    1997-12-26

    This document was developed to define the Authorization Basis management functional requirements for configuration control, to evaluate the management control systems currently in place, and identify any additional controls that may be required until the TWRS [Tank Waste Remediation System] Configuration Management system is fully in place.

  6. CRAD, Facility Safety- Nuclear Facility Safety Basis

    Office of Energy Efficiency and Renewable Energy (EERE)

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis.

  7. Extended defense systems :I. adversary-defender modeling grammar for vulnerability analysis and threat assessment.

    SciTech Connect (OSTI)

    Merkle, Peter Benedict

    2006-03-01

    Vulnerability analysis and threat assessment require systematic treatments of adversary and defender characteristics. This work addresses the need for a formal grammar for the modeling and analysis of adversary and defender engagements of interest to the National Nuclear Security Administration (NNSA). Analytical methods treating both linguistic and numerical information should ensure that neither aspect has disproportionate influence on assessment outcomes. The adversary-defender modeling (ADM) grammar employs classical set theory and notation. It is designed to incorporate contributions from subject matter experts in all relevant disciplines, without bias. The Attack Scenario Space U{sub S} is the set universe of all scenarios possible under physical laws. An attack scenario is a postulated event consisting of the active engagement of at least one adversary with at least one defended target. Target Information Space I{sub S} is the universe of information about targets and defenders. Adversary and defender groups are described by their respective Character super-sets, (A){sub P} and (D){sub F}. Each super-set contains six elements: Objectives, Knowledge, Veracity, Plans, Resources, and Skills. The Objectives are the desired end-state outcomes. Knowledge is comprised of empirical and theoretical a priori knowledge and emergent knowledge (learned during an attack), while Veracity is the correspondence of Knowledge with fact or outcome. Plans are ordered activity-task sequences (tuples) with logical contingencies. Resources are the a priori and opportunistic physical assets and intangible attributes applied to the execution of associated Plans elements. Skills for both adversary and defender include the assumed general and task competencies for the associated plan set, the realized value of competence in execution or exercise, and the opponent's planning assumption of the task competence.

  8. Auxiliary basis expansions for large-scale electronic structure calculations

    SciTech Connect (OSTI)

    Jung, Yousung; Sodt, Alexander; Gill, Peter W.M.; Head-Gordon, Martin

    2005-04-04

    One way to reduce the computational cost of electronic structure calculations is to employ auxiliary basis expansions to approximate 4 center integrals in terms of 2 and 3-center integrals, usually using the variationally optimum Coulomb metric to determine the expansion coefficients. However the long-range decay behavior of the auxiliary basis expansion coefficients has not been characterized. We find that this decay can be surprisingly slow. Numerical experiments on linear alkanes and a toy model both show that the decay can be as slow as 1/r in the distance between the auxiliary function and the fitted charge distribution. The Coulomb metric fitting equations also involve divergent matrix elements for extended systems treated with periodic boundary conditions. An attenuated Coulomb metric that is short-range can eliminate these oddities without substantially degrading calculated relative energies. The sparsity of the fit coefficients is assessed on simple hydrocarbon molecules, and shows quite early onset of linear growth in the number of significant coefficients with system size using the attenuated Coulomb metric. This means it is possible to design linear scaling auxiliary basis methods without additional approximations to treat large systems.

  9. Microsoft Word - Final Cover.doc

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

    National Nuclear Security Administration's Implementation of the 2003 Design Basis Threat DOE/IG-0705 October 2005 SPECIAL REPORT ON THE NATIONAL NUCLEAR SECURITY ADMINISTRATION'S IMPLEMENTATION OF THE 2003 DESIGN BASIS THREAT TABLE OF CONTENTS Implementation of the Design Basis Threat Details of Finding ...........................................................................................1

  10. TECHNICAL BASIS DOCUMENT FOR NATURAL EVENT HAZARDS

    SciTech Connect (OSTI)

    KRIPPS, L.J.

    2006-07-31

    This technical basis document was developed to support the documented safety analysis (DSA) and describes the risk binning process and the technical basis for assigning risk bins for natural event hazard (NEH)-initiated accidents. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls.

  11. Radioactive Waste Management BasisApril 2006

    SciTech Connect (OSTI)

    Perkins, B K

    2011-08-31

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  12. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2009-08-28

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document.

  13. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  14. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  15. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  16. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  17. Code System to Calculate Brief Adversary Threat Loss Estimate.

    Energy Science and Technology Software Center (OSTI)

    1999-11-23

    Version 00 PC-BATLE is an analytical stochastic model designed to simulate combat engagements between a security force at a nuclear facility and an adversary force attempting to steal nuclear materials or to cause the release of radiological materials through an act of sabotage. The engagement is modeled as a modified continuous-time Markov process in which the state of the process at any time is the number of guards and adversaries currently in the system. Casualtiesmore » to guards and adversaries are determined automatically by the model based on combatant characteristics and site parameters. Combatant characteristics which are specified as input data include force size, type of weapon used, posture, percent of time delaying (an attempt to prolong the engagement), proficiency, defense or assault tactic, and degradation in firing due to an individual's posture. Site parameters include range of the engagement, exposure to the combatants, and degradation in firing due to target illumination. Reinforcements to either or both forces can be specified by the user and will automatically be included at the appropriate time. Output consists of data on engagement duration, combatant survival, and win probabilities.« less

  18. Smaller RFID Sensors Use Less Power to Detect Threats | GE Global Research

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

    New RFID Sensors are Smaller, Use Less Power to Detect Chemical Threats Click to email this to a friend (Opens in new window) Share on Facebook (Opens in new window) Click to share (Opens in new window) Click to share on LinkedIn (Opens in new window) Click to share on Tumblr (Opens in new window) New RFID Sensors are Smaller, Use Less Power to Detect Chemical Threats Radislav Potyrailo 2015.02.17 Hello Earth! We have reached a significant milestone with GE's radio-frequency identification

  19. Before the House Subcommittee on Emerging Threats, Cyber Security and Science and Technology Committee on Homeland Security

    Broader source: Energy.gov [DOE]

    Before the House Subcommittee on Emerging Threats, Cyber Security and Science and Technology Committee on Homeland SecurityBy: Patricia Hoffman, Acting Assistant Secretary for Electricity Delivery...

  20. ORISE: The Medical Basis for Radiation-Accident Preparedness...

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

    The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REACTS Symposium on the Medical Basis for Radiation-Accident ...

  1. Nuclear Safety Basis Program Review Overview and Management Oversight...

    Office of Environmental Management (EM)

    Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review Plan Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review ...

  2. Structural Basis for the Interaction between Pyk2-FAT Domain...

    Office of Scientific and Technical Information (OSTI)

    Structural Basis for the Interaction between Pyk2-FAT Domain and Leupaxin LD Repeats Citation Details In-Document Search Title: Structural Basis for the Interaction between ...

  3. Heavy quarkonium in a holographic basis (Journal Article) | DOE...

    Office of Scientific and Technical Information (OSTI)

    Heavy quarkonium in a holographic basis Title: Heavy quarkonium in a holographic basis Authors: Li, Yang Search DOE PAGES for author "Li, Yang" Search DOE PAGES for ORCID ...

  4. Los Alamos National Laboratory fission basis (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Los Alamos National Laboratory fission basis Citation Details In-Document Search Title: Los Alamos National Laboratory fission basis You are accessing a document from the ...

  5. Structural Basis of Prion Inhibition by Phenothiazine Compounds...

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Search Results Journal Article: Structural Basis of Prion Inhibition by Phenothiazine Compounds Citation Details In-Document Search Title: Structural Basis of Prion ...

  6. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

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

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Polymer ...

  7. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

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

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Life Cycle ...

  8. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

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

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus ...

  9. A molecular basis for advanced materials in water treatment....

    Office of Scientific and Technical Information (OSTI)

    A molecular basis for advanced materials in water treatment. Citation Details In-Document Search Title: A molecular basis for advanced materials in water treatment. Authors: Rempe, ...

  10. NDRPProtocolTechBasisCompiled020705.doc

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

    Basis Document for the Neutron Dose Reconstruction Project NEUTRON DOSE RECONSTRUCTION PROTOCOL Roger B. Falk, Joe M. Aldrich, Jerry Follmer, Nancy M. Daugherty, and Dr. Duane E. Hilmas Oak Ridge Institute of Science and Education and Dr. Phillip L. Chapman Department of Statistics, Colorado State University February 7, 2005 ORISE 05-0199 This document was produced under contract number DE-AC05-00OR22750 between the U.S. Department of Energy and Oak Ridge Associated Universities The authors of

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

    SciTech Connect (OSTI)

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

    2015-02-23

    Small Modular Reactors (SMR) with power levels significantly less than the currently standard 1000 to 1600-MWe reactors have been proposed as a potential game changer for future nuclear power. SMRs may offer a simpler, more standardized, and safer modular design by using factory built and easily transportable components. Additionally, SMRs may be more easily built and operated in isolated locations, and may require smaller initial capital investment and shorter construction times. Because many SMRs designs are still conceptual and consequently not yet fixed, designers have a unique opportunity to incorporate updated design basis threats, emergency preparedness requirements, and then fully integrate safety, physical security, and safeguards/material control and accounting (MC&A) designs. Integrating safety, physical security, and safeguards is often referred to as integrating the 3Ss, and early consideration of safeguards and security in the design is often referred to as safeguards and security by design (SSBD). This paper describes U.S./Russian collaborative efforts toward developing an internationally accepted common approach for implementing SSBD/3Ss for SMRs based upon domestic requirements, and international guidance and requirements. These collaborative efforts originated with the Nuclear Energy and Nuclear Security working group established under the U.S.-Russia Bilateral Presidential Commission during the 2009 Presidential Summit. Initial efforts have focused on review of U.S. and Russian domestic requirements for Security and MC&A, IAEA guidance for security and MC&A, and IAEA requirements for international safeguards. Additionally, example SMR design features that can enhance proliferation resistance and physical security have been collected from past work and reported here. The development of a U.S./Russian common approach for SSBD/3Ss should aid the designer of SMRs located anywhere in the world. More specifically, the application of this approach may

  12. Evaluation in a competitive utility environment: the threat of confidentiality

    SciTech Connect (OSTI)

    Vine, Edward

    1997-06-01

    information needs and sources and revise existing policies. 2. Review process for handling confidentiality claims and revise existing policies. 3. Monitor restructuring activities. 4. Develop framework and specific guidelines. 5. Develop standards of conduct. 6. Hold workshops on confidentiality. 7. Design and implement a pilot project. 8. Establish and support consumer advocates. 9. Support more research on confidentiality. Utilities will be reluctant to support these activities and develop the new rules of the game. Regulators need to be more proactive and conduct the above activities promptly in order to avoid paralysis and inertia and to maintain the regulatory balance. The lack of a regulatory framework and specific policies for information access may only make existing problems more severe. The issue of confidentiality has broad sociopolitical dimensions. In the next few years, commissions will be asked to create information policies that will demonstrate the degree of their support for public access to utility- held information. These policies will be important since they can "profoundly affect the manner in which an individual in a society, indeed a society itself, makes political, economic and social choices." Finally, in all likelihood, evaluators will need to adapt to an environment where utility data will be more difficult to obtain and disseminate. It is premature to see how increased confidentiality will affect the objectivity, usefulness, validity, and reliability of evaluations. If the evaluation community wishes to maintain the high its work, creative solutions will most needed.

  13. Technical Basis for PNNL Beryllium Inventory

    SciTech Connect (OSTI)

    Johnson, Michelle Lynn

    2014-07-09

    The Department of Energy (DOE) issued Title 10 of the Code of Federal Regulations Part 850, “Chronic Beryllium Disease Prevention Program” (the Beryllium Rule) in 1999 and required full compliance by no later than January 7, 2002. The Beryllium Rule requires the development of a baseline beryllium inventory of the locations of beryllium operations and other locations of potential beryllium contamination at DOE facilities. The baseline beryllium inventory is also required to identify workers exposed or potentially exposed to beryllium at those locations. Prior to DOE issuing 10 CFR 850, Pacific Northwest Nuclear Laboratory (PNNL) had documented the beryllium characterization and worker exposure potential for multiple facilities in compliance with DOE’s 1997 Notice 440.1, “Interim Chronic Beryllium Disease.” After DOE’s issuance of 10 CFR 850, PNNL developed an implementation plan to be compliant by 2002. In 2014, an internal self-assessment (ITS #E-00748) of PNNL’s Chronic Beryllium Disease Prevention Program (CBDPP) identified several deficiencies. One deficiency is that the technical basis for establishing the baseline beryllium inventory when the Beryllium Rule was implemented was either not documented or not retrievable. In addition, the beryllium inventory itself had not been adequately documented and maintained since PNNL established its own CBDPP, separate from Hanford Site’s program. This document reconstructs PNNL’s baseline beryllium inventory as it would have existed when it achieved compliance with the Beryllium Rule in 2001 and provides the technical basis for the baseline beryllium inventory.

  14. Modeling threat assessments of water supply systems using markov latent effects methodology.

    SciTech Connect (OSTI)

    Silva, Consuelo Juanita

    2006-12-01

    Recent amendments to the Safe Drinking Water Act emphasize efforts toward safeguarding our nation's water supplies against attack and contamination. Specifically, the Public Health Security and Bioterrorism Preparedness and Response Act of 2002 established requirements for each community water system serving more than 3300 people to conduct an assessment of the vulnerability of its system to a terrorist attack or other intentional acts. Integral to evaluating system vulnerability is the threat assessment, which is the process by which the credibility of a threat is quantified. Unfortunately, full probabilistic assessment is generally not feasible, as there is insufficient experience and/or data to quantify the associated probabilities. For this reason, an alternative approach is proposed based on Markov Latent Effects (MLE) modeling, which provides a framework for quantifying imprecise subjective metrics through possibilistic or fuzzy mathematics. Here, an MLE model for water systems is developed and demonstrated to determine threat assessments for different scenarios identified by the assailant, asset, and means. Scenario assailants include terrorists, insiders, and vandals. Assets include a water treatment plant, water storage tank, node, pipeline, well, and a pump station. Means used in attacks include contamination (onsite chemicals, biological and chemical), explosives and vandalism. Results demonstrated highest threats are vandalism events and least likely events are those performed by a terrorist.

  15. RNEDE: Resilient Network Design Environment

    SciTech Connect (OSTI)

    Venkat Venkatasubramanian, Tanu Malik, Arun Giridh; Craig Rieger; Keith Daum; Miles McQueen

    2010-08-01

    Modern living is more and more dependent on the intricate web of critical infrastructure systems. The failure or damage of such systems can cause huge disruptions. Traditional design of this web of critical infrastructure systems was based on the principles of functionality and reliability. However, it is increasingly being realized that such design objectives are not sufficient. Threats, disruptions and faults often compromise the network, taking away the benefits of an efficient and reliable design. Thus, traditional network design parameters must be combined with self-healing mechanisms to obtain a resilient design of the network. In this paper, we present RNEDEa resilient network design environment that that not only optimizes the network for performance but tolerates fluctuations in its structure that result from external threats and disruptions. The environment evaluates a set of remedial actions to bring a compromised network to an optimal level of functionality. The environment includes a visualizer that enables the network administrator to be aware of the current state of the network and the suggested remedial actions at all times.

  16. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2011-04-04

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision

  17. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2010-04-01

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision

  18. Safety basis academy summary of project implementation from 2007-2009

    SciTech Connect (OSTI)

    Johnston, Julie A

    2009-01-01

    During fiscal years 2007 through 2009, in accordance with Performance Based Incentives with DOE/NNSA Los Alamos Site Office, Los Alamos National Security (LANS) implemented and operated a Safety Basis Academy (SBA) to facilitate uniformity in technical qualifications of safety basis professionals across the nuclear weapons complex. The implementation phase of the Safety Basis Academy required development, delivery, and finalizing a set of 23 courses. The courses developed are capable of supporting qualification efforts for both federal and contractor personnel throughout the DOE/NNSA Complex. The LANS Associate Director for Nuclear and High Hazard Operations (AD-NHHO) delegated project responsibillity to the Safety Basis Division. The project was assigned to the Safety Basis Technical Services (SB-TS) Group at Los Alamos National Laboratory (LANL). The main tasks were project needs analysis, design, development, implementation of instructional delivery, and evaluation of SBA courses. DOE/NNSA responsibility for oversight of the SBA project was assigned to the Chief of Defense for Nuclear Safety, and delegated to the Authorization Basis Senior Advisor, Continuous Learning Chair (CDNS-ABSA/CLC). NNSA developed a memorandum of agreement with LANS AD-NHHO. Through a memorandum of agreement initiated by NNSA, the DOE National Training Center (NTC) will maintain the set of Safety Basis Academy courses and is able to facilitate course delivery throughout the DOE Complex.

  19. Interim Basis for PCB Sampling and Analyses

    SciTech Connect (OSTI)

    BANNING, D.L.

    2001-03-20

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the U.S. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposal approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QA/G4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1A, Vol. IV, Section 4.16 (Banning 1999).

  20. Interim Basis for PCB Sampling and Analyses

    SciTech Connect (OSTI)

    BANNING, D.L.

    2001-01-18

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the US. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposal approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QAlG4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1 A, Vol. IV, Section 4.16 (Banning 1999).

  1. Improving Department of Energy Capabilities for Mitigating Beyond Design

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

    Basis Events | Department of Energy Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events April 2013 OE-1: 2013-01 Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events The purpose of this Operating Experience (OE) document is to: provide results from U.S. Department of Energy (DOE), including the National Nuclear Security Administration,

  2. A radial basis function Galerkin method for inhomogeneous nonlocal diffusion

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

    Lehoucq, Richard B.; Rowe, Stephen T.

    2016-02-01

    We introduce a discretization for a nonlocal diffusion problem using a localized basis of radial basis functions. The stiffness matrix entries are assembled by a special quadrature routine unique to the localized basis. Combining the quadrature method with the localized basis produces a well-conditioned, sparse, symmetric positive definite stiffness matrix. We demonstrate that both the continuum and discrete problems are well-posed and present numerical results for the convergence behavior of the radial basis function method. As a result, we explore approximating the solution to anisotropic differential equations by solving anisotropic nonlocal integral equations using the radial basis function method.

  3. Exposure Levels for Chemical Threat Compounds; Information to Facilitate Chemical Incident Response

    SciTech Connect (OSTI)

    Hauschild, Veronique; Watson, Annetta Paule

    2013-01-01

    Exposure Standards, Limits and Guidelines for Chemical Threat Compunds ABSTRACT Exposure criteria for chemical warfare (CW) agents and certain toxic industrial chemicals (TICs) used as CW agents (such as chlorine fill in an improvised explosive device) have been developed for protection of the civilian general public, civilian employees in chemical agent processing facilities and deployed military populations. In addition, compound-specific concentrations have been developed to serve as how clean is clean enough clearance criteria guiding facility recovery following chemical terrorist or other hazardous release events. Such criteria are also useful to verify compound absence, identify containment boundaries and expedite facility recovery following chemical threat release. There is no single right value or concentration appropriate for all chemical hazard control applications. It is acknowledged that locating and comparing the many sources of CW agent and TIC exposure criteria has not been previously well-defined. This paper summarizes many of these estimates and assembles critical documentation regarding their derivation and use.

  4. Review of July 2013 Nuclear Security Insider Threat Exercise November 2013

    SciTech Connect (OSTI)

    Pederson, Ann C.; Snow, Catherine L.; Townsend, Jeremy; Shannon, Michael

    2013-11-01

    This document is a review of the Nuclear Security Insider Threat Exercise which was hosted at ORNL in July 2013. Nuclear security culture and the insider threat are best learned through experience. Culture is inherently difficult to teach, and as such is best learned through modeled behaviors and learning exercise. This TTX, NSITE, is a tool that strives to aid students in learning what an effective (and ineffective) nuclear security culture might look like by simulating dynamic events that strengthen or weaken the nuclear security regime. The goals of NSITE are to stimulate complex thought and discussion and assist decision makers and management in determining the most effective policies and procedures for their country or facility.

  5. Sensor Data Processing for Tracking Underwater Threats Using Terascale Optical Core Devices

    SciTech Connect (OSTI)

    Barhen, Jacob; Imam, Neena

    2009-01-01

    A critical aspect of littoral surveillance (including port protection) involves the localization and tracking of underwater threats such as manned or unmanned autonomous underwater vehicles. In this article, we present a methodology for locating underwater threat sources from uncertain sensor network data, and illustrate the threat tracking aspects using active sonars in a matched filter framework. The novelty of the latter paradigm lies in its implementation on a tera-scale optical core processor, EnLight , recently introduced by Lenslet Laboratories. This processor is optimized for array operations, which it performs in a fixed point arithmetic architecture at tera-scale throughput. Using the EnLight 64 prototype processor, our results (i) illustrate the ability to reach a robust tracking accuracy, and (ii) demonstrate that a considerable speed-up (a factor of over 13,000) can be achieved when compared to an Intel XeonTM processor in the computation of sets of 80K-sample complex Fourier transforms that are associated with our matched filter techniques.

  6. Beyond Adapting to Climate Change: Embedding Adaptation in Responses to Multiple Threats and Stresses

    SciTech Connect (OSTI)

    Wilbanks, Thomas J; Kates, Dr. Robert W.

    2010-01-01

    Climate change impacts are already being experienced in every region of the United States and every part of the world most severely in Arctic regions and adaptation is needed now. Although climate change adaptation research is still in its infancy, significant adaptation planning in the United States has already begun in a number of localities. This article seeks to broaden the adaptation effort by integrating it with broader frameworks of hazards research, sustainability science, and community and regional resilience. To extend the range of experience, we draw from ongoing case studies in the Southeastern United States and the environmental history of New Orleans to consider the multiple threats and stresses that all communities and regions experience. Embedding climate adaptation in responses to multiple threats and stresses helps us to understand climate change impacts, themselves often products of multiple stresses, to achieve community acceptance of needed adaptations as co-benefits of addressing multiple threats, and to mainstream the process of climate adaptation through the larger envelope of social relationships, communication channels, and broad-based awareness of needs for risk management that accompany community resilience.

  7. Living in the Nuclear Age: Families and the threat of nuclear war

    SciTech Connect (OSTI)

    Demorest, D.M.

    1991-01-01

    The main interest of this research was to add to the body of knowledge about the possible psychological impact of the nuclear threat on the family unit. Data were utilized from the Family Interaction, Stress and Nuclear War study conducted by Jules Riskin, M.D. and Victoria Dickerson, Ph.D. at the Mental Research Institute in Palo Alto, California. The sample consisted of ten families who were recruited for this study. In order to examine family-interaction variables and the impact of the threat of nuclear war, a standardized semi-structured family interview was conducted. Topics ranged from ordinary activities to external, non-nuclear stresses such as landslides or hurricanes, to the topic of nuclear war. A distinction is drawn between a family's level of nuclear concern while they discuss nuclear issues and a family's level of nuclear concern when viewed in the context of their overall pattern of family communication. In terms of family coping, family nuclear concern was found to be significantly related to two family-coping strategies. Families who utilized the coping strategies of seeking spiritual support and mobilizing the family to acquire and accept help were significantly less concerned about the threat of nuclear war.

  8. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2007-03-12

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor

  9. PARFUME Theory and Model basis Report

    SciTech Connect (OSTI)

    Darrell L. Knudson; Gregory K Miller; G.K. Miller; D.A. Petti; J.T. Maki; D.L. Knudson

    2009-09-01

    The success of gas reactors depends upon the safety and quality of the coated particle fuel. The fuel performance modeling code PARFUME simulates the mechanical, thermal and physico-chemical behavior of fuel particles during irradiation. This report documents the theory and material properties behind vari¬ous capabilities of the code, which include: 1) various options for calculating CO production and fission product gas release, 2) an analytical solution for stresses in the coating layers that accounts for irradiation-induced creep and swelling of the pyrocarbon layers, 3) a thermal model that calculates a time-dependent temperature profile through a pebble bed sphere or a prismatic block core, as well as through the layers of each analyzed particle, 4) simulation of multi-dimensional particle behavior associated with cracking in the IPyC layer, partial debonding of the IPyC from the SiC, particle asphericity, and kernel migration (or amoeba effect), 5) two independent methods for determining particle failure probabilities, 6) a model for calculating release-to-birth (R/B) ratios of gaseous fission products that accounts for particle failures and uranium contamination in the fuel matrix, and 7) the evaluation of an accident condition, where a particle experiences a sudden change in temperature following a period of normal irradiation. The accident condi¬tion entails diffusion of fission products through the particle coating layers and through the fuel matrix to the coolant boundary. This document represents the initial version of the PARFUME Theory and Model Basis Report. More detailed descriptions will be provided in future revisions.

  10. Authorization basis status report (miscellaneous TWRS facilities, tanks and components)

    SciTech Connect (OSTI)

    Stickney, R.G.

    1998-04-29

    This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified.