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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 | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the...

  2. Design Basis Threat | National Nuclear Security Administration

    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

      Broader source: Energy.gov [DOE]

      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...

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

      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

      Energy Savers [EERE]

      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

    • 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 DBRP issue resolution process which provides a method for the team to promptly sort and prioritize questions and issues between those that can be addressed as a normal part of the reconstitution project and those that are to be handle as PISAs. Presentation of the DBRP issue resolution process provides an example for similar activities that may be required at other facilities within the Department of Energy complex.

    • 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

      Energy Savers [EERE]

      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

    • 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.

    • 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.

    • 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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...

  7. Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events

    Broader source: Energy.gov [DOE]

    This is a level 1 operating experience document providing direction for Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events. [OE-1: 2013-01

  8. 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, the recommendation is to construct each sample composite using four or five source samples. Although the variance using 5 source samples per composite sample (Composite Sample Design Option (c)) was slightly less than the variance using 4 source samples per composite sample (Composite Sample Design Option (b)), there is no practical difference between those variances. This does not consider that the measurement error variance, which is the same for all composite sample design options considered in this report, will further dilute any differences. Composite Sample Design Option (a) had the largest variance for the mean concentration in the three composite samples and should be avoided. These results are consistent with Pavletich (2014b) which utilizes a low elevation and a high elevation mound source sample and two floor source samples for each composite sample. Utilizing the four source samples per composite design, Pavletich (2014b) utilizes aliquots of Floor Sample 4 for two composite samples.

  9. 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.

  10. 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.

  11. 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); tank layout and dimensions, including design margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

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

    SciTech Connect (OSTI)

    Ferrada, Juan J [ORNL

    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 margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

  13. 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.

  14. 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 designed to be reliable in these conditions. The primary goal of any such actions is to maintain or refill the passive inventory available to cool the core, containment and spent fuel pool in the safety-related and seismically qualified Passive Containment Cooling Water Storage Tank (PCCWST). The seismically-qualified, ground-mounted Passive Containment Cooling Ancillary Water Storage Tank (PCCAWST) is also available for this function as appropriate. The primary effect of these actions would be to increase the coping time for the AP1000 during design basis events, as well as events such as those described above, from 72 hours without operator intervention to 7 days with minimal operator actions. These Operator actions necessary to protect the health and safety of the public are addressed in the Post-72 Hour procedures, as well as some EOPs, AOPs, ARPs and the Severe Accident Management Guidelines (SAMGs). Should the event continue to become more severe and plant conditions degrade further with indications of inadequate core cooling, the SAMGs provide guidance for strategies to address these hypothetical severe accident conditions. The AP1000 SAMG diagnoses and actions are prioritized to first utilize the AP1000 features that are expected to retain a damaged core inside the reactor vessel. Only one strategy is undertaken at any time. This strategy will be followed and its effectiveness evaluated before other strategies are undertaken. This is a key feature of both the symptom-oriented AP1000 EOPs and the AP1000 SAMGs which maximizes the probability of retaining a damaged core inside the reactor vessel and containment while minimizing the chances for confusion and human errors during implementation. The AP1000 SAMGs are simple and straight-forward and have been developed with considerable input from human factors and plant operations experts. Most importantly, and different from severe accident management strategies for other plants, the AP1000 SAMGs do not require diagnosis of the location of the core (i.e., whether reactor vessel failure has occurred). This is a fun

  15. 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.

  16. 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.

  17. 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)

  18. 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.

  19. 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.

  20. 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).

  1. 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.

  2. 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. The characterization and analysis effort included 1) downhole measurements of the velocity properties (including uncertainties) of the basalt/interbed sequences, 2) confirmation of the geometry of the contact between the various basalt and interbedded sediments through examination of retrieved core from the core-hole and data collected through geophysical logging of each borehole, and 3) prediction of ground motion response to an earthquake using newly acquired and historic data. The data and analyses reflect a significant reduction in the uncertainty in shear wave velocities below the WTP and result in a significantly lower spectral acceleration (i.e., ground motion). The updated ground motion response analyses and corresponding design response spectra reflect a 25% lower peak horizontal acceleration than reflected in the 2005 design criteria. These results provide confidence that the WTP seismic design criteria are conservative. (authors)

  3. 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.

  4. 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.

  5. 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 and 4700 m{sup 3}, corresponding to fuel-cooling times (time after shutdown) of two weeks and one week, respectively. This large quantity of water serves as an ultimate heat sink available for the residual heat removal in the case of station blackout. The optimal spraying droplet diameter, travel, and mass flow rate are 3 mm, 30 m, and 100 to 125 kg/s, respectively.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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)

  12. 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...

  13. 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.

  14. 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 decreases the developed turbine torque; the RCIC speed then slows, and thus the pump flow rate to the RPV decreases. Subsequently, RPV water level decreases due to continued boiling and the liquid fraction flowing to the RCIC decreases, thereby accelerating the RCIC and refilling the RPV. The feedback cycle then repeats itself and/or reaches a quasi-steady equilibrium condition. In other words, the water carry-over is limited by cyclic RCIC performance degradation, and hence the system becomes self-regulating. The indications achieved to date with the system model are more qualitative than quantitative. The avenues being pursued to increase the fidelity of the model are expected to add quantitative realism. The end product will be generic in the sense that the RCIC model will be incorporable within the larger reactor coolant system model of any nuclear power plant or experimental configuration.

  15. 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.

  16. Defense Threat Reduction Agency | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Defense Threat Reduction Agency

  17. 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.

  18. THREAT OF MALICIOUS CODE

    Energy Savers [EERE]

    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

  19. Threat Analysis Framework | Department of Energy

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

    Threat Analysis Framework Categorizing Threat Building and Using a Generic Threat Matrix Advanced Metering Infrastructure Security Considerations Careers & Internships Funding...

  20. 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).

  1. 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.

  2. 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.

  3. 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.

  4. 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

  5. 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.

  6. 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.

  7. Categorizing Threat Building and Using a Generic Threat Matrix...

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

    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 ...

  8. 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.

  9. 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.

  10. 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 compensating mitigation can decrease the risk of an insider performing a malicious act without detection.

  11. 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

    Broader source: Energy.gov [DOE]

    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.

  12. 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

  13. 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.

  14. 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 ...

  15. 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...

  16. 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 of 50% and a more modest burnup target level of 500 MWd/kg ,the failure probability drops below 2.0 x 10{sup -5}, the typical performance of TRISO fuel made under the German HTR research program. An optimization study on particle design shows improved performance if the buffer size is increased from 100 to 120 {micro}mm while reducing the OPyC layer. The presence of the latter layer does not provide much benefit at high burnup levels (and fast fluence levels). Normally the shrinkage of the OPyC would result in a beneficial compressive force on the SiC coating. However, at high fluence levels the shrinkage is expected to turn into swelling, resulting in the opposite effect. However, this situation is different when the SiC-matrix, in which the particles are embedded, is also considered: the OPyC swelling can result in a beneficial compressive force on the SiC coating since outward displacement of the OPyC outer surface is inhibited by the presence of the also-swelling SiC matrix. Taking some credit for this effect by adopting a 5 {micro}mm SiC-matrix layer, the optimized particle (100 {micro}mm buffer and 10 {micro}mm OPyC), gives a failure probability of 1.9 x 10{sup -4} for conservative conditions. During a LOCA transient, assuming core re-flood in 30 seconds, the temperature of the coated particle can be expected to be about 200K higher than nominal temperature (900K). For this event the particle failure fraction for a conservative case is 1.0 x 10{sup -2}, for the optimized particle design. For a FGR-fraction of 50% this value reduces to 6.4 x 10{sup -4}.

  17. Global Threat Reduction Initiative | Department of Energy

    Energy Savers [EERE]

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

  18. 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.

  19. 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.

  20. 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

  1. 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

  2. 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.

  3. 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.

  4. Manager, International Chemical Threat Reduction Department,...

    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 ...

  5. 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.

  6. 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.

  7. 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

  8. Why is Zika now a threat?

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

    Why 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

  9. 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.

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

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

    Nuclear Threat Science The Office of Nuclear Threat Science is responsible for overseeing the Nuclear Counterterrorism Program, an NNSA program that sustains specialized expertise ...

  11. 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...

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

    Office of Environmental Management (EM)

    DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS ... Neither a reviewer nor the preparer has veto power over ultimate resolution or ...

  13. 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

  14. Nuclear Radiological Threat Task Force Established | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration 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."

  15. Design Forward and Fast Forward Semi-Annual Review

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

    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

  16. 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.

  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. 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

  1. 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

  2. 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).

  3. 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 other nuclei that bombard the Earth, producing space-weather effects such as the beautiful northern lights but also others that can destroy satellites and disrupt our lives here on Earth. April 24, 2016 The space weather threat... and how we protect ourselves Photo: NASA/GSFC/SDO The space weather threat... and how we

  4. 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.

  5. 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...

  6. 2014 Annual Planning Summary for the NNSA Global Threat Reduction

    Energy Savers [EERE]

    Initiative Office | Department of Energy Global Threat Reduction Initiative Office 2014 Annual Planning Summary for the NNSA Global Threat Reduction Initiative Office The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2014 and 2015 within the NNSA Global Threat Reduction Initiative Office. PDF icon NNSA-GTRI-NEPA-APS-2014.pdf More Documents & Publications 2010 Annual Planning Summary for Stanford Linear Accelerator Center Site Office (SLAC) 2012

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

    National Nuclear Security Administration (NNSA)

    Fact Sheets 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

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

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration 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 to

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

    Energy Savers [EERE]

    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 ...

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

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

    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 ...

  12. 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...

  13. 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...

  14. 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.

  15. COLLOQUIUM: Nuclear Famine: The Threat to Humanity from Nuclear...

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

    June 18, 2014, 4:00pm to 5:30pm Colloquia MBG Auditorium COLLOQUIUM: Nuclear Famine: The Threat to Humanity from Nuclear Weapons Dr. Alan Robock Rutgers University A nuclear war ...

  16. Microsoft Word - Categorizing Threat Oct10-final.doc

    Energy Savers [EERE]

    5791 Unlimited Release Printed September 2007 Categorizing Threat Building and Using a Generic Threat Matrix David P. Duggan, Sherry R. Thomas, Cynthia K. K. Veitch, and Laura Woodard 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

  17. NNSA Works With Australian Agency to Counter Radiological Threats |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration Works With Australian Agency to Counter Radiological Threats March 10, 2006 WASHINGTON, D.C. - - Today, the Department of Energy's National Nuclear Security Administration (NNSA) and the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) agreed to join forces to counter radiological threats - such as a "dirty bomb" - and respond to emergencies. NNSA's Principal Deputy Administrator Jerry Paul and ARPANSA's Chief Executive

  18. 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.

  19. New Perspectives on the NEO Threat and Other Reasons to Consider...

    Office of Scientific and Technical Information (OSTI)

    New Perspectives on the NEO Threat and Other Reasons to Consider Asteroid DeflectionFragmentation. Citation Details In-Document Search Title: New Perspectives on the NEO Threat...

  20. 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.

  1. 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

  2. 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

  3. Basis

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

    operator bispectral analysis D. A. Baver, 1 P. W. Terry, 1 and C. Holland 2 1 Department of Physics, University of Wisconsin, Madison, Wisconsin 53706, USA 2 Center for Energy Research, University of California, San Diego, California 92093, USA ͑Received 11 September 2008; accepted 12 February 2009; published online 30 March 2009͒ A new procedure for calculating model coefficients from fluctuation data for fully developed turbulence is derived. This procedure differs from previous related

  4. 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...

  5. 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.

  6. Enterprise Assessments Targeted Review of the Safety Basis at...

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

    ... in SAR 3.3.2.3.1 does not address the effect of an earthquake followed by a fire. ... Although the accident analysis is generally sound, the analysis of the design basis ...

  7. 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.

  8. 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

  9. Protecting the Nation's Electric Grid from Cyber Threats

    Broader source: Energy.gov [DOE]

    The Electric Sector Cybersecurity Risk Maturity Model Pilot is a new White House initiative led by the Department of Energy to develop a model to help us identify how secure the electric grid is from cyber threats and to test that model with participating utilities.

  10. 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.

  11. 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

  12. 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.

  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. Safety Basis Information System | Department of Energy

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

    Basis Information System Safety Basis Information System Safety Basis Report (Public Access) Click on the above link to see the current Safety Basis report. This report provides a list of all DOE nuclear facilities with the safety basis status, hazard categorization, and safety basis type. Safety Basis Login Click on the above link to log in to the Safety Basis web interface. "RESTRICTED; access only to DOE and DOE contractors" Safety Basis Account Request Click on the above link to

  15. 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

  16. 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.

  17. 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.

  18. 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.

  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. 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

  1. 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

  2. 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.

  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. 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.

  5. 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.

  6. 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.

  7. 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)

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

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

    Energy Savers [EERE]

    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. 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...

  15. 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.

  16. 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.

  17. 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. ...

  18. 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...

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

    Office of Scientific and Technical Information (OSTI)

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

  20. Crystal Structures of mPGES-1 Inhibitor Complexes Form a Basis for the

    Office of Scientific and Technical Information (OSTI)

    Rational Design of Potent Analgesic and Anti-Inflammatory Therapeutics (Journal Article) | SciTech Connect Crystal Structures of mPGES-1 Inhibitor Complexes Form a Basis for the Rational Design of Potent Analgesic and Anti-Inflammatory Therapeutics Citation Details In-Document Search Title: Crystal Structures of mPGES-1 Inhibitor Complexes Form a Basis for the Rational Design of Potent Analgesic and Anti-Inflammatory Therapeutics Authors: Luz, John Gately ; Antonysamy, Stephen ; Kuklish,

  1. 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.

  2. 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. This resulted in delays in finalizing agreements with commercial partners, and in particular the Invensys testbed was not installed until December 2008 (as opposed to the March 2008 plan). The project resulted in a number of conference presentations and publications, and was well received when presented at industry forums. In spite of some interest on the part of the utility sector, we were unfortunately not able to engage a utility for a full-scale pilot deployment.

  3. 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.

  4. 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.

  5. 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

  6. 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...

  7. 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 ...

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

    Office of Scientific and Technical Information (OSTI)

    Bayesian Approach (Conference) | SciTech Connect Sequential Threat Detection for Harbor 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 Approach Authors: Candy, J V Publication Date: 2013-03-14 OSTI Identifier: 1084714 Report Number(s): LLNL-CONF-628912 DOE Contract Number: W-7405-ENG-48 Resource Type: Conference Resource Relation: Conference: Presented at: IEEE

  9. 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

  10. Fact Sheet: Detection and Analysis of Threats to the Energy Sector (DATES)

    Energy Savers [EERE]

    Detection and Analysis of Threats to the Energy Sector (DATES) A groundbreaking integrated capability in intrusion detection, security event management, and sector-wide threat analysis Detecting cyber attacks against digital control systems quickly and accurately is essential to energy sector security. Current intrusion detection systems (IDS) continuously scan control system communication paths and alert operators of suspicious network traffc. But existing IDS, often not tailored to the control

  11. 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...

  12. SRS FTF Section 3116 Basis for Determination

    Broader source: Energy.gov [DOE]

    Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site. In accordance with NDAA Section 3116, certain waste from reprocessing of spent nuclear fuel is not high...

  13. 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,

  14. 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.

  15. 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,

  16. 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.

  17. 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

  18. 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.

  19. 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.

  20. 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.

  1. New Perspectives on the NEO Threat and Other Reasons to Consider Asteroid

    Office of Scientific and Technical Information (OSTI)

    Deflection/Fragmentation. (Conference) | SciTech Connect New Perspectives on the NEO Threat and Other Reasons to Consider Asteroid Deflection/Fragmentation. Citation Details In-Document Search Title: New Perspectives on the NEO Threat and Other Reasons to Consider Asteroid Deflection/Fragmentation. Abstract not provided. Authors: Boslough, Mark Bruce Elrick Publication Date: 2008-11-01 OSTI Identifier: 1142397 Report Number(s): SAND2008-7238C 508981 DOE Contract Number: DE-AC04-94AL85000

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

    Office of Scientific and Technical Information (OSTI)

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

  3. 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

  4. 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...

  5. 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.

  6. 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.

  7. 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.

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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.

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

    SciTech Connect (OSTI)

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

    2015-02-23

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

  14. 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 ...

  15. 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 ...

  16. 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 ...

  17. Structural basis for substrate specificity in the Escherichia...

    Office of Scientific and Technical Information (OSTI)

    Structural basis for substrate specificity in the Escherichia coli maltose transport system Citation Details In-Document Search Title: Structural basis for substrate specificity in ...

  18. 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 ...

  19. 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 ...

  20. 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 ...

  1. 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 ...

  2. 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 ...

  3. 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, ...

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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 numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2.

  9. 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 numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. Radioactive and other environmental threats to the United States and the Arctic resulting from past Soviet activities

    SciTech Connect (OSTI)

    1993-12-31

    Earlier this year the Senate Intelligence Committee began to receive reports from environmental and nuclear scientists in Russia detailing the reckless nuclear waste disposal practices, nuclear accidents and the use of nuclear detonations. We found that information disturbing to say the least. Also troubling is the fact that 15 Chernobyl style RBMK nuclear power reactors continue to operate in the former Soviet Union today. These reactors lack a containment structure and they`re designed in such a way that nuclear reaction can actually increase when the reactor overheats. As scientists here at the University of Alaska have documented, polar air masses and prevailing weather patterns provide a pathway for radioactive contaminants from Eastern Europe and Western Russia, where many of these reactors are located. The threats presented by those potential radioactive risks are just a part of a larger Arctic pollution problem. Every day, industrial activities of the former Soviet Union continue to create pollutants. I think we should face up to the reality that in a country struggling for economic survival, environment protection isn`t necessarily the high priority. And that could be very troubling news for the Arctic in the future.

  15. 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).

  16. 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).

  17. 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 revision. Updated Chapters 5, 6 and 9 to reflect change in default ring calibration factor used in HEDP dose calculation software. Factor changed from 1.5 to 2.0 beginning January 1, 2007. Pages on which changes were made are as follows: 5.23, 5.69, 5.78, 5.80, 5.82, 6.3, 6.5, 6.29, 9.2.

  18. Enterprise Assessments Targeted Review of the Safety Basis at...

    Office of Environmental Management (EM)

    Basis at the Savannah River Site F-Area Central Laboratory Facility - January 2016 Enterprise Assessments Targeted Review of the Safety Basis at the Savannah River Site F-Area ...

  19. 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.

  20. 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 variÂŹous 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 condiÂŹtion 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.

  1. The National Nuclear Security Administration Global Threat Reduction Initiative's Contract Administration, OAS-L-12-01

    Energy Savers [EERE]

    Audit and Inspections Audit Report The National Nuclear Security Administration Global Threat Reduction Initiative's Contract Administration OAS-L-12-01 October 2011 Department of Energy Washington, DC 20585 October 25, 2011 MEMORANDUM FOR THE DEPUTY ADMINISTRATOR FOR DEFENSE NUCLEAR NONPROLIFERATION FROM: David Sedillo Director Western Audits Division SUBJECT: INFORMATION: Audit Report on "The National Nuclear Security Administration Global Threat Reduction Initiative's Contract

  2. The Global Threat Reduction Initiative's Orphan Source Recovery Project in the Russian Federation

    SciTech Connect (OSTI)

    Russell, J. W.; Ahumada, A. D.; Blanchard, T. A.

    2012-06-04

    After 9/11, officials at the United States Department of Energy (DOE), National Nuclear Security Administration (NNSA) grew more concerned about radiological materials that were vulnerable to theft and illicit use around the world. The concern was that terrorists could combine stolen radiological materials with explosives to build and detonate a radiological dispersal device (RDD), more commonly known as a “dirty bomb.” In response to this and other terrorist threats, the DOE/NNSA formed what is now known as the Global Threat Reduction Initiative (GTRI) to consolidate and accelerate efforts to reduce and protect vulnerable nuclear and radiological materials located at civilian sites worldwide. Although a cooperative program was already underway in the Russian Federation to secure nuclear materials at a range of different facilities, thousands of sealed radioactive sources remained vulnerable at medical, research, and industrial sites. In response, GTRI began to focus efforts on addressing these materials. GTRI’s Russia Orphan Source Recovery Project, managed at the Nevada National Security Site’s North Las Vegas facility, was initiated in 2002. Throughout the life of the project, Joint Stock Company “Isotope” has served as the primary Russian subcontractor, and the organization has proven to be a successful partner. Since the first orphan source recovery of an industrial cobalt-60 irradiator with 647 curies (Ci) at an abandoned facility in Moscow in 2003, the GTRI Orphan Source Recovery Project in the Russian Federation has accomplished substantial levels of threat reduction. To date, GTRI has recovered and securely disposed of more than 5,100 sources totaling more that 628,000 Ci. This project serves as an extraordinary example of how international cooperation can be implemented by partners with mutual interests to achieve significant goals.

  3. Student attitudes toward the threat of nuclear war: Friends as influential reference persons

    SciTech Connect (OSTI)

    Marasch, M.J.

    1992-01-01

    A renewed interest in research into the psychology of the threat of nuclear war occurred in the past decade as national attention focused increasingly on the arms race between the US and the USSR. Some of this research began the task of exploring the social influences upon attitudes and responses to the nuclear threat. Research on friends as potential influences upon nuclear attitudes was minimal. The present study investigated the role of college friends as potential reference persons in the formation of nuclear attitudes. A battery of questionnaires addressing various nuclear war and non-nuclear war attitudes was completed by 200 student-friend dyads from introductory psychology and sociology courses at the University of North Dakota. Three hypotheses were presented in this study. One hypothesis was that students would perceive their friends as having similar attitudes toward the threat of nuclear war. A second hypothesis was that the actual attitudes between pairs of students and friends would be similar. The third hypothesis was that the attitudes would have become more similar over the course of the development of the friendship (as measured retrospectively). The first hypothesis was borne out by the data. The second and third hypotheses were not supported. There are several implications of the findings. One implication is that the nuclear issue may not be as salient to college students as other, more immediate, issues. Another implication is that a relative lack of communication between college students on political issues precludes more effective mutual influence upon the development and change of such attitudes. A false consensus bias appeared to be operative when the students perceived that their attitudes were similar. Further discussion is presented in regard to past and future psychological research upon nuclear war attitudes.

  4. GLOBAL THREAT REDUCTION INITIATIVE REACTOR CONVERSION PROGRAM: STATUS AND CURRENT PLANS

    SciTech Connect (OSTI)

    Staples, Parrish A.; Leach, Wayne; Lacey, Jennifer M.

    2009-10-07

    The U.S. Department of Energy’s National Nuclear Security Administration (NNSA) Reactor Conversion Program supports the minimization, and to the extent possible, elimination of the use of high enriched uranium (HEU) in civilian nuclear applications by working to convert research and test reactors and radioisotope production processes to the use of low enriched uranium (LEU). The Reactor Conversion Program is a technical pillar of the NNSA Global Threat Reduction Initiative (GTRI) which is a key organization for implementing U.S. HEU minimization policy and works to reduce and protect vulnerable nuclear and radiological material domestically and abroad.

  5. Propane Market Outlook Key Market Trends, Opportunities, and Threats Facing the Consumer

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Propane Market Outlook Key Market Trends, Opportunities, and Threats Facing the Consumer Propane Industry Through 2025 Prepared for the Propane Education & Research Council (PERC) by: ICF International, Inc. 9300 Lee Highway Fairfax, VA 22031 Tel (703) 218-2758 www.icfi.com Principal Author: Mr. Michael Sloan msloan@icfi.com P R E S E N T E D B Y : Propane Market Outlook at a Glance ÂĄ ICF projects consumer propane sales to grow by about 800 million gallons (9 percent) between 2014 and

  6. Supporting the Global Threat Reduction Initiative through Nuclear Material Recovery: Collaboration between NNSA and AREVA

    SciTech Connect (OSTI)

    Bieniawski, Andrew; Sheely, Ken; Hunter, Ian; Louvet, Thibault

    2007-07-01

    The Global Threat Reduction Initiative (GTRI) was established by the U.S. Department of Energy National Nuclear Security Administration (NNSA) in response to the growing need to comprehensively and internationally address the potential threat posed by vulnerable high-risk nuclear material. GTRI's mission is to foster international support for national programs to identify, secure, remove and/or facilitate the disposition, as quickly and expeditiously as possible, of vulnerable, high-risk nuclear and other radioactive materials around the world that pose a potential threat to the international community. Specifically, GTRI establishes international partnerships to address this global issue. To achieve these objectives, GTRI works with international, regional, and domestic partners to: (1) minimize and, to the extent possible, eliminate the use of highly enriched uranium (HEU) in civil nuclear applications worldwide by converting research reactors to LEU fuels; (2) accelerate the removal or final disposition of vulnerable nuclear material throughout the world; (3) accelerate securing and/or removing vulnerable high-risk radiological materials throughout the world; and (4) address the 'gaps' of other programs by identifying throughout the world, recovering and facilitating permanent disposition of vulnerable high-risk nuclear material not previously addressed by other threat reduction programs. DOE desires to work with more partners, both government and industry, to develop options for the disposal of nuclear material in the most expeditious manner. This paper will present the recent success of the first Plutonium Gap Material recycling contract signed by AREVA thanks to the collaboration developed between NNSA and AREVA. Another item which will be presented and illustrates how GTRI supports government-to-industry partnership, is the willingness to consider the treatment option for Gap Materials used-fuel. This new step represents another broadening of the collaboration that already exists between NNSA and AREVA for achieving the goal of GTRI. Such collaboration was already illustrated in 2006 by the recovery of more than 45 Kg of HEU from facilities within Europe and another 15 Kg of fresh HEU were transported from Europe to the U.S. An additional 40 Kg of fresh HEU will be transported from facilities within Europe to the AREVA-CERCA facility before the end of 2007. (authors)

  7. Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

    Office of Environmental Management (EM)

    Fuel and High-Level Waste | Department of Energy Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered

  8. Basis for Identification of Disposal Options for R and D for Spent Nuclear

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

    Fuel and High-Level Waste | Department of Energy Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered

  9. Technical basis in support of the conversion of the University of Missouri Research Reactor (MURR) core from highly-enriched to low-enriched uranium - core neutron physics

    SciTech Connect (OSTI)

    Stillman, J.; Feldman, E.; Foyto, L; Kutikkad, K; McKibben, J C; Peters, N.; Stevens, J.

    2012-09-01

    This report contains the results of reactor design and performance for conversion of the University of Missouri Research Reactor (MURR) from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL) and the MURR Facility. The core conversion to LEU is being performed with financial support of the U. S. government.

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

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2010-01-01

    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 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 (ERICA) 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 numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Updated Chapters 5, 6 and 9 to reflect change in default ring calibration factor used in HEDP dose calculation software. Factor changed from 1.5 to 2.0 beginning January 1, 2007. Pages on which changes were made are as follows: 5.23, 5.69, 5.78, 5.80, 5.82, 6.3, 6.5, 6.29, and 9.2. Rev 0.2 (8/28/2009) Updated Chapters 3, 5, 6, 8 and 9. Chapters 6 and 8 were significantly expanded. References in the Preface and Chapters 1, 2, 4, and 7 were updated to reflect updates to DOE documents. Approved by HPDAC on 6/2/2009. Rev 1.0 (1/1/2010) Major revision. Updated all chapters to reflect the Hanford site wide implementation on January 1, 2010 of new DOE requirements for occupational radiation protection. The new requirements are given in the June 8, 2007 amendment to 10 CFR 835 Occupational Radiation Protection (Federal Register, June 8, 2007. Title 10 Part 835. U.S., Code of Federal Regulations, Vol. 72, No. 110, 31904-31941). Revision 1.0 to the manual replaces ICRP 26 dosimetry concepts and terminology with ICRP 60 dosimetry concepts and terminology and replaces external dose conversion factors from ICRP 51 with those from ICRP 74 for use in measurement of operational quantities with dosimeters. Descriptions of dose algorithms and dosimeter response characteristics, and field performance were updated to reflect changes in the neutron quality factors used in the measurement of operational quantities.

  11. Technical Basis for Assessing Uranium Bioremediation Performance

    SciTech Connect (OSTI)

    PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL N’Guessan

    2008-04-01

    In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation.

  12. Development of engineering technology basis for industrialization of pyrometallurgical reprocessing

    SciTech Connect (OSTI)

    Koyama, Tadafumi; Hijikata, Takatoshi; Yokoo, Takeshi; Inoue, Tadashi

    2007-07-01

    Development of the engineering technology basis of pyrometallurgical reprocessing is a key issue for industrialization. For development of the transport technologies of molten salt and liquid cadmium at around 500 deg. C, a salt transport test rig and a metal transport test rig were installed in Ar glove box. Function of centrifugal pump and 1/2' declined tubing were confirmed with LiCl- KCl molten salt. The transport behavior of molten salt was found to follow that of water. Function of centrifugal pump, vacuum sucking and 1/2' declined tubing were confirmed with liquid Cd. With employing the transport technologies, industrialization applicable electro-refiner was newly designed and engineering-scale model was fabricated in Ar glove box. The electro-refiner has semi-continuous liquid Cd cathode instead of conventional one used in small-scale tests. With using actinide-simulating elements, demonstration of industrial-scale throughput will be carried out in this electro-refiner for more precise evaluation of industrialization potential of pyrometallurgical reprocessing. (authors)

  13. Designing and Operating Through Compromise: Architectural Analysis of CKMS for the Advanced Metering Infrastructure

    SciTech Connect (OSTI)

    Duren, Mike; Aldridge, Hal; Abercrombie, Robert K; Sheldon, Frederick T

    2013-01-01

    Compromises attributable to the Advanced Persistent Threat (APT) highlight the necessity for constant vigilance. The APT provides a new perspective on security metrics (e.g., statistics based cyber security) and quantitative risk assessments. We consider design principals and models/tools that provide high assurance for energy delivery systems (EDS) operations regardless of the state of compromise. Cryptographic keys must be securely exchanged, then held and protected on either end of a communications link. This is challenging for a utility with numerous substations that must secure the intelligent electronic devices (IEDs) that may comprise complex control system of systems. For example, distribution and management of keys among the millions of intelligent meters within the Advanced Metering Infrastructure (AMI) is being implemented as part of the National Smart Grid initiative. Without a means for a secure cryptographic key management system (CKMS) no cryptographic solution can be widely deployed to protect the EDS infrastructure from cyber-attack. We consider 1) how security modeling is applied to key management and cyber security concerns on a continuous basis from design through operation, 2) how trusted models and key management architectures greatly impact failure scenarios, and 3) how hardware-enabled trust is a critical element to detecting, surviving, and recovering from attack.

  14. Enterprise Assessments Review of the Delegation of Safety Basis Approval

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

    Authority for Hazard Category 1, 2, and 3 Nuclear Facilities - April 2016 | Department of Energy Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear Facilities - April 2016 Enterprise Assessments Review of the Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear Facilities - April 2016 April 2016 Enterprise Assessments Review of the Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear

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

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

    Management (Published by REAC/TS) The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness and the Biodosimetry Workshop As part of its mission to provide continuing education for personnel responsible for treating radiation injuries, REAC/TS hosted the Fifth International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness symposium and

  16. Technical Planning Basis - DOE Directives, Delegations, and Requiremen...

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

    2, Technical Planning Basis by David Freshwater Functional areas: Defense Nuclear Facility Safety and Health Requirement, Safety and Security, The Guide assists DOENNSA field...

  17. CRAD, Review of Safety Basis Development- January 31, 2013

    Broader source: Energy.gov [DOE]

    Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility - Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 45-57, Rev. 0)

  18. 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 ... unsuccessful. figure 2 Fig 2A. Broad spectrum neutralizing antibody F10 in complex ...

  19. Metrics for Developing an Endorsed Set of Radiographic Threat Surrogates for JINII/CAARS

    SciTech Connect (OSTI)

    Wurtz, R; Walston, S; Dietrich, D; Martz, H

    2009-02-11

    CAARS (Cargo Advanced Automated Radiography System) is developing x-ray dual energy and x-ray backscatter methods to automatically detect materials that are greater than Z=72 (hafnium). This works well for simple geometry materials, where most of the radiographic path is through one material. However, this is usually not the case. Instead, the radiographic path includes many materials of different lengths. Single energy can be used to compute {mu}y{sub l} which is related to areal density (mass per unit area) while dual energy yields more information. This report describes a set of metrics suitable and sufficient for characterizing the appearance of assemblies as detected by x-ray radiographic imaging systems, such as those being tested by Joint Integrated Non-Intrusive Inspection (JINII) or developed under CAARS. These metrics will be simulated both for threat assemblies and surrogate threat assemblies (such as are found in Roney et al. 2007) using geometrical and compositional information of the assemblies. The imaging systems are intended to distinguish assemblies containing high-Z material from those containing low-Z material, regardless of thickness, density, or compounds and mixtures. The systems in question operate on the principle of comparing images obtained by using two different x-ray end-point energies--so-called 'dual energy' imaging systems. At the direction of the DHS JINII sponsor, this report does not cover metrics that implement scattering, in the form of either forward-scattered radiation or high-Z detection systems operating on the principle of backscatter detection. Such methods and effects will be covered in a later report. The metrics described here are to be used to compare assemblies and not x-ray radiography systems. We intend to use these metrics to determine whether two assemblies do or do not look the same. We are tasked to develop a set of assemblies whose appearance using this class of detection systems is indistinguishable from the real threats. To check such an indistinguishability, we must define metrics that are broad enough to cover systems of different source spectra and detector spectral response; in other words, the best metrics should capture physical properties of the assemblies and not the source and detectors employed. In fact, one requirement for the metrics is that, as the detection circumstances change, the similarity or difference of the metrics of two assemblies should be maintained. This report describes the set of two simple 'dual energy' metrics that we have selected. A second report (Wurtz, et al. 2009) goes on to demonstrate several characteristics of the metrics, including how sensitive they are (or are not) to changes in the detection systems, shielding, etc.

  20. Combining Traditional Cyber Security Audit Data with Psychosocial Data: Towards Predictive Modeling for Insider Threat Mitigation

    SciTech Connect (OSTI)

    Greitzer, Frank L.; Frincke, Deborah A.

    2010-09-01

    The purpose of this chapter is to motivate the combination of traditional cyber security audit data with psychosocial data, so as to move from an insider threat detection stance to one that enables prediction of potential insider presence. Two distinctive aspects of the approach are the objective of predicting or anticipating potential risks and the use of organizational data in addition to cyber data to support the analysis. The chapter describes the challenges of this endeavor and progress in defining a usable set of predictive indicators, developing a framework for integrating the analysis of organizational and cyber security data to yield predictions about possible insider exploits, and developing the knowledge base and reasoning capability of the system. We also outline the types of errors that one expects in a predictive system versus a detection system and discuss how those errors can affect the usefulness of the results.

  1. program design. Final report Brown, W.H.; Gopalakrishnan, S....

    Office of Scientific and Technical Information (OSTI)

    an improved basis for the design, procurement, testing, and operation of large feed pumps with increased reliability and stability over the full range of operating conditions....

  2. Safety evaluation of MHTGR licensing basis accident scenarios

    SciTech Connect (OSTI)

    Kroeger, P.G.

    1989-04-01

    The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary Safety Information Document (PSID), as submitted by the US Department of Energy to the US Nuclear Regulatory Commission. The relevant reactor safety codes were extended for this purpose and applied to this new reactor concept, searching primarily for potential accident scenarios that might lead to fuel failures due to excessive core temperatures and/or to vessel damage, due to excessive vessel temperatures. The design basis accident scenario leading to the highest vessel temperatures is the depressurized core heatup scenario without any forced cooling and with decay heat rejection to the passive Reactor Cavity Cooling System (RCCS). This scenario was evaluated, including numerous parametric variations of input parameters, like material properties and decay heat. It was found that significant safety margins exist, but that high confidence levels in the core effective thermal conductivity, the reactor vessel and RCCS thermal emissivities and the decay heat function are required to maintain this safety margin. Severe accident extensions of this depressurized core heatup scenario included the cases of complete RCCS failure, cases of massive air ingress, core heatup without scram and cases of degraded RCCS performance due to absorbing gases in the reactor cavity. Except for no-scram scenarios extending beyond 100 hr, the fuel never reached the limiting temperature of 1600/degree/C, below which measurable fuel failures are not expected. In some of the scenarios, excessive vessel and concrete temperatures could lead to investment losses but are not expected to lead to any source term beyond that from the circulating inventory. 19 refs., 56 figs., 11 tabs.

  3. Assessing Beyond Design Basis Seismic Events and Implications on Seismic Risk

    Broader source: Energy.gov [DOE]

    Presenter: Jeffrey Kimball, Technical Specialist (Seismologist) Defense Nuclear Facilities Safety Board

  4. Nuclear Regulatory Commission Handling of Beyond Design Basis Events for Nuclear Power Reactors

    Broader source: Energy.gov [DOE]

    Presenter: Bill Reckley, Chief, Policy and Support Branch, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission US Nuclear Regulatory Commission

  5. Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events

    Broader source: Energy.gov [DOE]

    This report describes the opportunities for improvement identified in DOE’s review, and provides recommendations for short-term and long-term actions for improving safety at DOE nuclear facilities.

  6. DOE M&O Contractor Perspectives on Beyond Design Basis Event Analysis and Response

    Broader source: Energy.gov [DOE]

    Presenter: Ron Crone, Director Research Reactors Division UT-Battelle, LLC Oak Ridge National Laboratory

  7. A Report to the Secretary of Energy, Beyond Design Basis Event...

    Energy Savers [EERE]

    planning and preparedness (such as evaluations of potential loss of infrastructure or severe accident impacts to multiple facilities at a site) can benefit all DOE sites. *...

  8. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011

    Broader source: Energy.gov [DOE]

    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.

  9. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011

    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.

  10. A Report to the Secretary of Energy, Beyond Design Basis Event...

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

    ... LANL - Los Alamos National Laboratory LLNL - Lawrence Livermore National Laboratory NBL - New Brunswick Laboratory NNSS - Nevada National Security Site *ORNL - Oak Ridge ...

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

    Energy Savers [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 ...

  12. Structural basis for the antibody neutralization of Herpes simplex virus

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Structural basis for the antibody neutralization of Herpes simplex virus Citation Details In-Document Search Title: Structural basis for the antibody neutralization of Herpes simplex virus The gD-E317-Fab complex crystal revealed the conformational epitope of human mAb E317 on HSV gD, providing a molecular basis for understanding the viral neutralization mechanism. Glycoprotein D (gD) of Herpes simplex virus (HSV) binds to a host cell surface receptor,

  13. Radiological Threat Reduction (RTR) program : implementing physical security to protect large radioactive sources worldwide.

    SciTech Connect (OSTI)

    Lowe, Daniel L.

    2004-11-01

    The U.S. Department of Energy's Radiological Threat Reduction (RTR) Program strives to reduce the threat of a Radiological Dispersion Device (RDD) incident that could affect U.S. interests worldwide. Sandia National Laboratories supports the RTR program on many different levels. Sandia works directly with DOE to develop strategies, including the selection of countries to receive support and the identification of radioactive materials to be protected. Sandia also works with DOE in the development of guidelines and in training DOE project managers in physical protection principles. Other support to DOE includes performing rapid assessments and providing guidance for establishing foreign regulatory and knowledge infrastructure. Sandia works directly with foreign governments to establish cooperative agreements necessary to implement the RTR Program efforts to protect radioactive sources. Once necessary agreements are in place, Sandia works with in-country organizations to implement various security related initiatives, such as installing security systems and searching for (and securing) orphaned radioactive sources. The radioactive materials of interest to the RTR program include Cobalt 60, Cesium 137, Strontium 90, Iridium 192, Radium 226, Plutonium 238, Americium 241, Californium 252, and Others. Security systems are implemented using a standardized approach that provides consistency through out the RTR program efforts at Sandia. The approach incorporates a series of major tasks that overlap in order to provide continuity. The major task sequence is to: Establish in-country contacts - integrators, Obtain material characterizations, Perform site assessments and vulnerability assessments, Develop upgrade plans, Procure and install equipment, Conduct acceptance testing and performance testing, Develop procedures, and Conduct training. Other tasks are incorporated as appropriate and commonly include such as support of reconfiguring infrastructure, and developing security plans, etc. This standardized approach is applied to specific country and regional needs. Recent examples (FY 2003-2004) include foreign missions to Lithuania, Russian Federation Navy, Russia - PNPI, Greece (joint mission with IAEA), Tanzania, Iraq, Chile, Ecuador, and Egypt. Some of the ambitions and results of the RTR program may be characterized by the successes in Lithuania, Greece, and Russia.

  14. Structural basis for ubiquitin-mediated antiviral signal activation...

    Office of Scientific and Technical Information (OSTI)

    Title: Structural basis for ubiquitin-mediated antiviral signal activation by RIG-I Authors: Peisley, Alys ; Wu, Bin ; Xu, Hui ; Chen, Zhijian J. ; Hur , Sun 1 ; HHMI) 2 ; ...

  15. The Three-Dimensional Structural Basis of Type II Hyperprolinemia...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: The Three-Dimensional Structural Basis of Type II Hyperprolinemia Citation Details In-Document Search ... Here, we report the first structure of human P5CDH (HsP5CDH) ...

  16. CRAD, Review of Safety Basis Development- October 11, 2012

    Broader source: Energy.gov [DOE]

    Review of Safety Basis Development for the Y-12 National Security Complex Uranium Processing Facility Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 45-55, Rev. 0)

  17. Structural basis for the antibody neutralization of Herpes simplex...

    Office of Scientific and Technical Information (OSTI)

    of Herpes simplex virus Citation Details In-Document Search Title: Structural basis for the antibody neutralization of Herpes simplex virus The gD-E317-Fab complex ...

  18. General Engineer/Physical Scientist (Safety Basis Engineer/Scientist)

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will serve as an authority in the safety basis functional area. The incumbent is responsible for managing, coordinating, and authorizing work in the context...

  19. FHR Generic Design Criteria

    SciTech Connect (OSTI)

    Flanagan, George F; Holcomb, David Eugene; Cetiner, Sacit M

    2012-06-01

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC) - based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  20. FHR Generic Design Criteria

    SciTech Connect (OSTI)

    Flanagan, G.F.; Holcomb, D.E.; Cetiner, S.M.

    2012-06-15

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC)–based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  1. Structural and Functional Basis for Inhibition of Erythrocyte Invasion by

    Office of Scientific and Technical Information (OSTI)

    Antibodies that Target Plasmodium falciparum EBA-175 (Journal Article) | SciTech Connect Journal Article: Structural and Functional Basis for Inhibition of Erythrocyte Invasion by Antibodies that Target Plasmodium falciparum EBA-175 Citation Details In-Document Search Title: Structural and Functional Basis for Inhibition of Erythrocyte Invasion by Antibodies that Target Plasmodium falciparum EBA-175 Authors: Chen, Edwin ; Paing, May M. ; Salinas, Nichole ; Sim, B. Kim Lee ; Tolia, Niraj H.

  2. Structural basis for biomolecular recognition in overlapping binding sites

    Office of Scientific and Technical Information (OSTI)

    in a diiron enzyme system (Journal Article) | SciTech Connect Structural basis for biomolecular recognition in overlapping binding sites in a diiron enzyme system Citation Details In-Document Search Title: Structural basis for biomolecular recognition in overlapping binding sites in a diiron enzyme system Authors: Acheson, Justin F. ; Bailey, Lucas J. ; Elsen, Nathaniel L. ; Fox, Brian G. [1] + Show Author Affiliations UW Publication Date: 2016-01-22 OSTI Identifier: 1229904 Resource Type:

  3. Structural basis of JAZ repression of MYC transcription factors in

    Office of Scientific and Technical Information (OSTI)

    jasmonate signalling (Journal Article) | SciTech Connect Journal Article: Structural basis of JAZ repression of MYC transcription factors in jasmonate signalling Citation Details In-Document Search Title: Structural basis of JAZ repression of MYC transcription factors in jasmonate signalling Authors: Zhang, Feng ; Yao, Jian ; Ke, Jiyuan ; Zhang, Li ; Lam, Vinh Q. ; Xin, Xiu-Fang ; Zhou, X. Edward ; Chen, Jian ; Brunzelle, Joseph ; Griffin, Patrick R. ; Zhou, Mingguo ; Xu, H. Eric ; Melcher,

  4. Structural basis for Tetrahymena telomerase processivity factor Teb1

    Office of Scientific and Technical Information (OSTI)

    binding to single-stranded telomeric-repeat DNA (Journal Article) | SciTech Connect Journal Article: Structural basis for Tetrahymena telomerase processivity factor Teb1 binding to single-stranded telomeric-repeat DNA Citation Details In-Document Search Title: Structural basis for Tetrahymena telomerase processivity factor Teb1 binding to single-stranded telomeric-repeat DNA Authors: Zeng, Zhixiong ; Min, Bosun ; Huang, Jing ; Hong, Kyungah ; Yang, Yuting ; Collins, Kathleen ; Lei, Ming [1]

  5. Structural basis for substrate specificity in the Escherichia coli maltose

    Office of Scientific and Technical Information (OSTI)

    transport system (Journal Article) | SciTech Connect Structural basis for substrate specificity in the Escherichia coli maltose transport system Citation Details In-Document Search Title: Structural basis for substrate specificity in the Escherichia coli maltose transport system Authors: Oldham, Michael L. ; Chen, Shanshuang ; Chen, Jue [1] ; HHMI) [2] + Show Author Affiliations (Purdue) [Purdue ( Publication Date: 2013-11-11 OSTI Identifier: 1105053 Resource Type: Journal Article Resource

  6. Atomic substitution reveals the structural basis for substrate adenine

    Office of Scientific and Technical Information (OSTI)

    recognition and removal by adenine DNA glycosylase (Journal Article) | SciTech Connect Atomic substitution reveals the structural basis for substrate adenine recognition and removal by adenine DNA glycosylase Citation Details In-Document Search Title: Atomic substitution reveals the structural basis for substrate adenine recognition and removal by adenine DNA glycosylase Adenine DNA glycosylase catalyzes the glycolytic removal of adenine from the promutagenic A {center_dot} oxoG base pair in

  7. Special Report: IG-0705 | Department of Energy

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

    5 Special Report: IG-0705 October 7, 2005 The National Nuclear Security Administration's Implementation of the 2003 Design Basis Threat The National Nuclear Security Administration (NNSA) has Threat Progress experienced delays in implementing permanent upgrades, including new technologies, to meet the increased threat identified in the 2003 Design Basis Threat (DBT). Instead, NNSA is relying on more costly interim measures to meet the requirements of the DBT by the end of Fiscal Year (FY) 2006.

  8. An overview of the global threat reduction initiative's physical protection work in Tanzania.

    SciTech Connect (OSTI)

    Banzi, Firmi Paul; Itamura, Michael Takeshi; Robinson, Phillip W.; Strosinski, Micheal Vernon

    2010-06-01

    The U.S. Department of Energy's (DOE) National Nuclear Security Administration (NNSA) established the Global Threat Reduction Initiative's (GTRI) mission to reduce and protect nuclear and radiological materials located at civilian sites worldwide. Internationally, over 80 countries are cooperating with GTRI to enhance security of facilities with these materials. In 2004, a GTRI delegation began working with the Tanzania Atomic Energy Commission, (TAEC). The team conducted site assessments for the physical protection of radiological materials in Tanzania. Today, GTRI and the Government of Tanzania continue cooperative efforts to enhance physical security at several radiological sites, including a central sealed-source storage facility, and sites in the cities of Arusha, Dar Es Salaam, and Tanga. This paper describes the scope of physical protection work, lessons learned, and plans for future cooperation between the GTRI program and the TAEC. Additionally the paper will review the cooperative efforts between TAEC and the International Atomic Energy Agency (IAEA) with regards to a remote monitoring system at a storage facility and to the repackaging of radioactive sources.

  9. Global Threat Reduction Initiative Fuel Thermo-Physical Characterization Project: Sample Management Plan

    SciTech Connect (OSTI)

    Casella, Amanda J.; Pereira, Mario M.; Steen, Franciska H.

    2013-01-01

    This sample management plan provides guidelines for sectioning, preparation, acceptance criteria, analytical path, and end-of-life disposal for the fuel element segments utilized in the Global Threat Reduction Initiative (GTRI), Fuel Thermo-Physical Characterization Project. The Fuel Thermo-Physical Characterization Project is tasked with analysis of irradiated Low Enriched Uranium (LEU) Molybdenum (U-Mo) fuel element samples to support the GTRI conversion program. Sample analysis may include optical microscopy (OM), scanning electron microscopy (SEM) fuel-surface interface analysis, gas pycnometry (density) measurements, laser flash analysis (LFA), differential scanning calorimetry (DSC), thermogravimetry and differential thermal analysis with mass spectroscopy (TG /DTA-MS), Inductively Coupled Plasma Spectrophotometry (ICP), alpha spectroscopy, and Thermal Ionization Mass Spectroscopy (TIMS). The project will utilize existing Radiochemical Processing Laboratory (RPL) operating, technical, and administrative procedures for sample receipt, processing, and analyses. Test instructions (TIs), which are documents used to provide specific details regarding the implementation of an existing RPL approved technical or operational procedure, will also be used to communicate to staff project specific parameters requested by the Principal Investigator (PI). TIs will be developed, reviewed, and issued in accordance with the latest revision of the RPL-PLN-700, RPL Operations Plan. Additionally, the PI must approve all project test instructions and red-line changes to test instructions.

  10. Identifying at-risk employees: A behavioral model for predicting potential insider threats

    SciTech Connect (OSTI)

    Greitzer, Frank L.; Kangas, Lars J.; Noonan, Christine F.; Dalton, Angela C.

    2010-09-01

    A psychosocial model was developed to assess an employee’s behavior associated with an increased risk of insider abuse. The model is based on case studies and research literature on factors/correlates associated with precursor behavioral manifestations of individuals committing insider crimes. In many of these crimes, managers and other coworkers observed that the offenders had exhibited signs of stress, disgruntlement, or other issues, but no alarms were raised. Barriers to using such psychosocial indicators include the inability to recognize the signs and the failure to record the behaviors so that they could be assessed by a person experienced in psychosocial evaluations. We have developed a model using a Bayesian belief network with the help of human resources staff, experienced in evaluating behaviors in staff. We conducted an experiment to assess its agreement with human resources and management professionals, with positive results. If implemented in an operational setting, the model would be part of a set of management tools for employee assessment that can raise an alarm about employees who pose higher insider threat risks. In separate work, we combine this psychosocial model’s assessment with computer workstation behavior to raise the efficacy of recognizing an insider crime in the making.

  11. Nuclear education campaign: on how to eliminate the threat of nuclear war

    SciTech Connect (OSTI)

    Markusen, E.; Dunham, J.; Bee, R.

    1981-05-01

    The threat of a nuclear war creates a chronic erosion of moral and intellectual integrity and places the future of humanity in the hands of a few hundred people. The nuclear elite probably requires a degree of psychological numbing and desensitization in order to separate themselves emotionally from decisions that might require exercise of their power. They may also lose the ability to question basic assumptions and may identify themselves with the rightness of their policies and the need to use nuclear technology to preserve those policies. To reform the nuclear-industrial complex, the American public must become educated to give the prevention of nuclear war a higher priority than the economy. Fears and anxieties may underlie apparent apathy, taking the form of denial and a focus on immediate problems. A campaign by knowledgeable people to educate the public should stress the empirical data necessary for objectivity and should use a multidisciplinary approach in the same way that recent death education programs have broken the taboos about discussing the Nazi holocaust. An outline of a nuclear-education program suggests a number of social and economic benefits. 13 references. (DCK)

  12. Audit Report: IG-0749 | Department of Energy

    Office of Environmental Management (EM)

    9 Audit Report: IG-0749 December 14, 2006 The Department's Energy, Science,and Environment Sites' Implementationof the Design Basis Threat 'The Department of Energy uses the...

  13. GRiP - A flexible approach for calculating risk as a function of consequence, vulnerability, and threat.

    SciTech Connect (OSTI)

    Whitfield, R. G.; Buehring, W. A.; Bassett, G. W.

    2011-04-08

    Get a GRiP (Gravitational Risk Procedure) on risk by using an approach inspired by the physics of gravitational forces between body masses! In April 2010, U.S. Department of Homeland Security Special Events staff (Protective Security Advisors [PSAs]) expressed concern about how to calculate risk given measures of consequence, vulnerability, and threat. The PSAs believed that it is not 'right' to assign zero risk, as a multiplicative formula would imply, to cases in which the threat is reported to be extremely small, and perhaps could even be assigned a value of zero, but for which consequences and vulnerability are potentially high. They needed a different way to aggregate the components into an overall measure of risk. To address these concerns, GRiP was proposed and developed. The inspiration for GRiP is Sir Isaac Newton's Universal Law of Gravitation: the attractive force between two bodies is directly proportional to the product of their masses and inversely proportional to the squares of the distance between them. The total force on one body is the sum of the forces from 'other bodies' that influence that body. In the case of risk, the 'other bodies' are the components of risk (R): consequence, vulnerability, and threat (which we denote as C, V, and T, respectively). GRiP treats risk as if it were a body within a cube. Each vertex (corner) of the cube represents one of the eight combinations of minimum and maximum 'values' for consequence, vulnerability, and threat. The risk at each of the vertices is a variable that can be set. Naturally, maximum risk occurs when consequence, vulnerability, and threat are at their maximum values; minimum risk occurs when they are at their minimum values. Analogous to gravitational forces among body masses, the GRiP formula for risk states that the risk at any interior point of the box depends on the squares of the distances from that point to each of the eight vertices. The risk value at an interior (movable) point will be dominated by the value of one vertex as that point moves closer and closer to that one vertex. GRiP is a visualization tool that helps analysts better understand risk and its relationship to consequence, vulnerability, and threat. Estimates of consequence, vulnerability, and threat are external to GRiP; however, the GRiP approach can be linked to models or data that provide estimates of consequence, vulnerability, and threat. For example, the Enhanced Critical Infrastructure Program/Infrastructure Survey Tool produces a vulnerability index (scaled from 0 to 100) that can be used for the vulnerability component of GRiP. We recognize that the values used for risk components can be point estimates and that, in fact, there is uncertainty regarding the exact values of C, V, and T. When we use T = t{sub o} (where t{sub o} is a value of threat in its range), we mean that threat is believed to be in an interval around t{sub o}. Hence, a value of t{sub o} = 0 indicates a 'best estimate' that the threat level is equal to zero, but still allows that it is not impossible for the threat to occur. When t{sub o} = 0 but is potentially small and not exactly zero, there will be little impact on the overall risk value as long as the C and V components are not large. However, when C and/or V have large values, there can be large differences in risk given t{sub o} = 0, and t{sub o} = epsilon (where epsilon is small but greater than a value of zero). We believe this scenario explains the PSA's intuition that risk is not equal to zero when t{sub o} = 0 and C and/or V have large values. (They may also be thinking that if C has an extremely large value, it is unlikely that T is equal to 0; in the terrorist context, T would likely be dependent on C when C is extremely large.) The PSAs are implicitly recognizing the potential that t{sub o} = epsilon. One way to take this possible scenario into account is to replace point estimates for risk with interval values that reflect the uncertainty in the risk components. In fact, one could argue that T never equals zero for a man-made hazard. This

  14. Order Module--DOE-STD-1104-2009, REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS

    Broader source: Energy.gov [DOE]

    The familiar level of this module is divided into two sections that are intended to provide only an overview of the material contained in DOE-STD-1104-2009, which should be consulted for complete...

  15. CRAD, Safety Basis- Idaho MF-628 Drum Treatment Facility

    Broader source: Energy.gov [DOE]

    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) used for a May 2007 readiness assessment of the Safety Basis at the Advanced Mixed Waste Treatment Project.

  16. CRAD, Safety Basis- Idaho Accelerated Retrieval Project Phase II

    Broader source: Energy.gov [DOE]

    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) used for a February 2006 Commencement of Operations assessment of the Safety Basis at the Idaho Accelerated Retrieval Project Phase II.

  17. Grid and basis adaptive polynomial chaos techniques for sensitivity and uncertainty analysis

    SciTech Connect (OSTI)

    Perkó, Zoltán Gilli, Luca Lathouwers, Danny Kloosterman, Jan Leen

    2014-03-01

    The demand for accurate and computationally affordable sensitivity and uncertainty techniques is constantly on the rise and has become especially pressing in the nuclear field with the shift to Best Estimate Plus Uncertainty methodologies in the licensing of nuclear installations. Besides traditional, already well developed methods – such as first order perturbation theory or Monte Carlo sampling – Polynomial Chaos Expansion (PCE) has been given a growing emphasis in recent years due to its simple application and good performance. This paper presents new developments of the research done at TU Delft on such Polynomial Chaos (PC) techniques. Our work is focused on the Non-Intrusive Spectral Projection (NISP) approach and adaptive methods for building the PCE of responses of interest. Recent efforts resulted in a new adaptive sparse grid algorithm designed for estimating the PC coefficients. The algorithm is based on Gerstner's procedure for calculating multi-dimensional integrals but proves to be computationally significantly cheaper, while at the same it retains a similar accuracy as the original method. More importantly the issue of basis adaptivity has been investigated and two techniques have been implemented for constructing the sparse PCE of quantities of interest. Not using the traditional full PC basis set leads to further reduction in computational time since the high order grids necessary for accurately estimating the near zero expansion coefficients of polynomial basis vectors not needed in the PCE can be excluded from the calculation. Moreover the sparse PC representation of the response is easier to handle when used for sensitivity analysis or uncertainty propagation due to the smaller number of basis vectors. The developed grid and basis adaptive methods have been implemented in Matlab as the Fully Adaptive Non-Intrusive Spectral Projection (FANISP) algorithm and were tested on four analytical problems. These show consistent good performance both in terms of the accuracy of the resulting PC representation of quantities and the computational costs associated with constructing the sparse PCE. Basis adaptivity also seems to make the employment of PC techniques possible for problems with a higher number of input parameters (15–20), alleviating a well known limitation of the traditional approach. The prospect of larger scale applicability and the simplicity of implementation makes such adaptive PC algorithms particularly appealing for the sensitivity and uncertainty analysis of complex systems and legacy codes.

  18. Modular High Temperature Gas-Cooled Reactor Safety Basis and Approach

    SciTech Connect (OSTI)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

    Various international efforts are underway to assess the safety of advanced nuclear reactor designs. For example, the International Atomic Energy Agency has recently held its first Consultancy Meeting on a new cooperative research program on high temperature gas-cooled reactor (HTGR) safety. Furthermore, the Generation IV International Forum Reactor Safety Working Group has recently developed a methodology, called the Integrated Safety Assessment Methodology, for use in Generation IV advanced reactor technology development, design, and design review. A risk and safety assessment white paper is under development with respect to the Very High Temperature Reactor to pilot the Integrated Safety Assessment Methodology and to demonstrate its validity and feasibility. To support such efforts, this information paper on the modular HTGR safety basis and approach has been prepared. The paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach. The paper gives those involved in the assessment of advanced reactor designs an opportunity to assess an advanced design that has already received extensive review by regulatory authorities and to judge the utility of recently proposed new methods for advanced reactor safety assessment such as the Integrated Safety Assessment Methodology.

  19. Design Rational

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

    ... designed for maximal cryptographic strength and high speed ... for Pair-Wise Key Establishment Schemes Using ... two benefits: careful management admits some ...

  20. Basis functions for electronic structure calculations on spheres

    SciTech Connect (OSTI)

    Gill, Peter M. W. Loos, Pierre-François Agboola, Davids

    2014-12-28

    We introduce a new basis function (the spherical Gaussian) for electronic structure calculations on spheres of any dimension D. We find general expressions for the one- and two-electron integrals and propose an efficient computational algorithm incorporating the Cauchy-Schwarz bound. Using numerical calculations for the D = 2 case, we show that spherical Gaussians are more efficient than spherical harmonics when the electrons are strongly localized.

  1. Online Monitoring Technical Basis and Analysis Framework for Emergency

    Energy Savers [EERE]

    Diesel Generators-Interim Report for FY 2013 | Department of Energy for Emergency Diesel Generators-Interim Report for FY 2013 Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators-Interim Report for FY 2013 The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the U.S. Department of Energy Office of Nuclear Energy. The program is operated in collaboration with the Electric Power Research Institute's

  2. Online Monitoring Technical Basis and Analysis Framework for Large Power

    Energy Savers [EERE]

    Transformers; Interim Report for FY 2012 | Department of Energy for Large Power Transformers; Interim Report for FY 2012 Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012 The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the U.S. Department of Energy Office of Nuclear Energy. The program is operated in collaboration with the Electric Power Research Institute's (EPRI's)

  3. Interim Safety Basis for Fuel Supply Shutdown Facility

    SciTech Connect (OSTI)

    BENECKE, M.W.

    2000-09-07

    This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines.

  4. Engineering Basis Document Review Supporting the Double Shell Tank (DST) System Specification Development

    SciTech Connect (OSTI)

    LEONARD, M.W.

    2000-03-14

    The Double-Shell Tank (DST) System is required to transition from its current storage mission to a storage and retrieval mission supporting the River Protection Project Phase 1 privatization, defined in HNF-SD-WM-MAR-008, Tank Waste Remediation System Mission Analysis Report. Requirements for the DST subsystems are being developed using the top-down systems engineering process outlined in HNF-SD-WM-SEMP-002, Tank Waste Remediation System Systems Engineering Management Plan. This top-down process considers existing designs to the extent that these designs impose unavoidable constraints on the Phase 1 mission. Existing engineering-basis documents were screened, and the unavoidable constraints were identified. The constraints identified herein will be added to the DST System specification (HNF-SD-WM-TRD-007, System Specification for the Double-Shell Tank System). While the letter revisions of the DST System specification were constructed with a less rigorous review of the existing engineering-basis documents, the Revision 0 release of the specification must incorporate the results of the review documented herein. The purpose of this document is to describe the screening process and criteria used to determine which constraints are unavoidable and to document the screening results.

  5. 5th International REAC/TS Symposium: The Medical Basis for Radiation...

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

    The Medical Basis for Radiation Accident Preparedness Skip site navigation and ... The Medical Basis for Radiation Accident Preparedness Sept. 27-29, 2011 | Miami, ...

  6. CRAD, Safety Basis Upgrade Review (DOE-STD-3009-2014) - May 15...

    Office of Environmental Management (EM)

    1) provides objectives, criteria, and approaches for establishing and maintaining the safety basis at nuclear facilities. CRAD, Safety Basis Upgrade Review (DOE-STD-3009-2014)...

  7. CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP

    SciTech Connect (OSTI)

    Kessler, S

    2009-04-21

    With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5, Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since February of 2008 and has proven to be simple and effective. Each control identified i

  8. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    SciTech Connect (OSTI)

    KOZLOWSKI, S.D.

    2007-05-30

    This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below.

  9. Guidance For Preparatioon of Basis For Interim Operation (BIO) Documents

    Energy Savers [EERE]

    3011-2002 December 2002 Superceding DOE-STD-3011-94 November 1994 DOE STANDARD GUIDANCE FOR PREPARATION OF BASIS FOR INTERIM OPERATION (BIO) DOCUMENTS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-3011-2002 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S.

  10. The Bender-Dunne basis operators as Hilbert space operators

    SciTech Connect (OSTI)

    Bunao, Joseph; Galapon, Eric A. E-mail: eric.galapon@upd.edu.ph

    2014-02-15

    The Bender-Dunne basis operators, T{sub ?m,n}=2{sup ?n}?{sub k=0}{sup n}(n/k )q{sup k}p{sup ?m}q{sup n?k} where q and p are the position and momentum operators, respectively, are formal integral operators in position representation in the entire real line R for positive integers n and m. We show, by explicit construction of a dense domain, that the operators T{sub ?m,n}'s are densely defined operators in the Hilbert space L{sup 2}(R)

  11. Development of an objective questionnaire to assess perception, concern, and knowledge of, and attention and response to, the threat of nuclear war

    SciTech Connect (OSTI)

    Kulman, I.R.

    1985-01-01

    In addition to the subject objective, the relationship of specified personality variables (i.e., trait anxiety, locus of control, response tendency towards threat, and denial) to behavioral and psychological responses to the threat of nuclear war were assessed. The quantitative questionnaire, titled the Nuclear Reaction Scale, was composed of items selected from issues discussed in the psychological literature on the threat of nuclear war. These issues included: psychic numbing, cognitive reality, perceptions of likelihood and survival, nuclear illusions, and attention to the threat of nuclear war. A standardization sample of 360 college students was administered the Nuclear Reaction Scale, Trait Anxiety Scale, Internal-External Locus of Control Scale, Facilitation-Inhibition Scale, and Haan Denial Scale. Three additional subsamples, identified as Military, Nuclear Freeze, and Church, were given the Nuclear Reaction Scale to assess the validity of the scale. A factor analysis of the Nuclear Reaction Scale indicated a nine-factor solution that described issues such as concern perceptions, likelihood, survivability, and control over the threat of nuclear war. A number of strong relationships existed between computed factors on the Nuclear Reaction Scale. Demographic comparisons found significant differences related to sex and political affiliation.

  12. Behavior and potential threats to survival of migrating lamprey ammocoetes and macrophthalmia

    SciTech Connect (OSTI)

    Moser, Mary L.; Jackson, Aaron D.; Lucas, Martyn C.; Mueller, Robert P.

    2015-03-01

    Upon metamorphosis, anadromous juvenile lamprey (macrophthalmia) exhibit distinct migration behaviors that take them from larval rearing habitats in streams to the open ocean. While poorly studied, lamprey larvae (ammocoetes) also engage in downstream movement to some degree. Like migrating salmon smolts, lamprey macrophthalmia undergo behavioral changes associated with a highly synchronized metamorphosis. Unlike salmon smolts, the timing of juvenile migration in lamprey is protracted and poorly documented. Lamprey macrophthalmia and ammocoetes are not strong swimmers, attaining maximum individual speeds of less than 1 m s-1, and sustained speeds of less than 0.5 m s-1. They are chiefly nocturnal and distribute throughout the water column, but appear to concentrate near the bottom in the thalweg of deep rivers. At dams and irrigation diversions, macrophthalmia can become impinged on screens or entrained in irrigation canals, suffer increased predation, and experience physical injury that may result in direct or delayed mortality. The very structures designed to protect migrating juvenile salmonids can be harmful to juvenile lamprey. Yet at turbine intakes and spillways, lampreys, which have no swim bladder, can withstand changes in pressure and shear stress large enough to injure or kill most teleosts. Lamprey populations are in decline in many parts of the world, with some species designated as species of concern for conservation that merit legally mandated protections. Hence, provisions for safe passage of juvenile lamprey are being considered at dams and water diversions in North America and Europe.

  13. Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    OHara, J.M.; Higgins, J.C.

    2010-01-31

    Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.

  14. Human System Simulation in Support of Human Performance Technical Basis at NPPs

    SciTech Connect (OSTI)

    David Gertman; Katya Le Blanc; alan mecham; william phoenix; Magdy Tawfik; Jeffrey Joe

    2010-06-01

    This paper focuses on strategies and progress toward establishing the Idaho National Laboratory’s (INL’s) Human Systems Simulator Laboratory at the Center for Advanced Energy Studies (CAES), a consortium of Idaho State Universities. The INL is one of the National Laboratories of the US Department of Energy. One of the first planned applications for the Human Systems Simulator Laboratory is implementation of a dynamic nuclear power plant simulation (NPP) where studies of operator workload, situation awareness, performance and preference will be carried out in simulated control rooms including nuclear power plant control rooms. Simulation offers a means by which to review operational concepts, improve design practices and provide a technical basis for licensing decisions. In preparation for the next generation power plant and current government and industry efforts in support of light water reactor sustainability, human operators will be attached to a suite of physiological measurement instruments and, in combination with traditional Human Factors Measurement techniques, carry out control room tasks in simulated advanced digital and hybrid analog/digital control rooms. The current focus of the Human Systems Simulator Laboratory is building core competence in quantitative and qualitative measurements of situation awareness and workload. Of particular interest is whether introduction of digital systems including automated procedures has the potential to reduce workload and enhance safety while improving situation awareness or whether workload is merely shifted and situation awareness is modified in yet to be determined ways. Data analysis is carried out by engineers and scientists and includes measures of the physical and neurological correlates of human performance. The current approach supports a user-centered design philosophy (see ISO 13407 “Human Centered Design Process for Interactive Systems, 1999) wherein the context for task performance along with the requirements of the end-user are taken into account during the design process and the validity of design is determined through testing of real end users

  15. A design methodology for unattended monitoring systems

    SciTech Connect (OSTI)

    SMITH,JAMES D.; DELAND,SHARON M.

    2000-03-01

    The authors presented a high-level methodology for the design of unattended monitoring systems, focusing on a system to detect diversion of nuclear materials from a storage facility. The methodology is composed of seven, interrelated analyses: Facility Analysis, Vulnerability Analysis, Threat Assessment, Scenario Assessment, Design Analysis, Conceptual Design, and Performance Assessment. The design of the monitoring system is iteratively improved until it meets a set of pre-established performance criteria. The methodology presented here is based on other, well-established system analysis methodologies and hence they believe it can be adapted to other verification or compliance applications. In order to make this approach more generic, however, there needs to be more work on techniques for establishing evaluation criteria and associated performance metrics. They found that defining general-purpose evaluation criteria for verifying compliance with international agreements was a significant undertaking in itself. They finally focused on diversion of nuclear material in order to simplify the problem so that they could work out an overall approach for the design methodology. However, general guidelines for the development of evaluation criteria are critical for a general-purpose methodology. A poor choice in evaluation criteria could result in a monitoring system design that solves the wrong problem.

  16. Electronic structure basis for the extraordinary magnetoresistance in WTe2

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

    Pletikosić, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. As a result, a change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior ofmore » the magnetoresistance in WTe₂ was identified.« less

  17. Electronic structure basis for the titanic magnetoresistance in WTe?

    SciTech Connect (OSTI)

    Pletikosic, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. A change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior of the magnetoresistance in WTe? was identified.

  18. Electronic structure basis for the titanic magnetoresistance in WTe?

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

    Pletikosic, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. A change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior of the magnetoresistance inmore »WTe? was identified.« less

  19. Draft Geologic Disposal Requirements Basis for STAD Specification

    SciTech Connect (OSTI)

    Ilgen, Anastasia G.; Bryan, Charles R.; Hardin, Ernest

    2015-03-25

    This document provides the basis for requirements in the current version of Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems, (FCRD-NFST-2014-0000579) that are driven by storage and geologic disposal considerations. Performance requirements for the Standardized Transportation, Aging, and Disposal (STAD) canister are given in Section 3.1 of that report. Here, the requirements are reviewed and the rationale for each provided. Note that, while FCRD-NFST-2014-0000579 provides performance specifications for other components of the STAD storage system (e.g. storage overpack, transfer and transportation casks, and others), these have no impact on the canister performance during disposal, and are not discussed here.

  20. Composition and Technical Basis for K Basin Settler Sludge Simulant for Inspection, Retrieval, and Pump Testing

    SciTech Connect (OSTI)

    Schmidt, Andrew J.; Zacher, Alan H.

    2007-06-25

    This report provides the formulation and technical basis for a K Basin Settler Tank Sludge simulant that will be used by the K Basin Closure Project (KBC) to test and develop equipment/approaches for Settler Tank sludge level measurement and retrieval in a mock-up test system of the actual Settler Tanks. The sludge simulant may also be used to demonstrate that the TOYO high pressure positive displacement pump design (reversing valves and hollow balls) is suitable for transfer of Settler Tank sludge from the K West (KW) Basin to the Cold Vacuum Drying Facility (CVDF) (~500 ft). As requested the by the K Basins Sludge Treatment Project (STP) the simulant is comprised of non-radioactive (and non-uranium) constituents.

  1. Designing and constructing/installing technical security countermeasures (TSCM) into supersensitive facilities

    SciTech Connect (OSTI)

    Davis, D.L.

    1988-01-01

    The design and construction of supersensitive facilities and the installation of systems secure from technical surveillance and sabotage penetration involve ''TSCM'' in the broad sense of technical ''security'' countermeasures. When the technical threat was at a lower level of intensity and sophistication, it was common practice to defer TSCM to the future facility occupant. However, the New Moscow Embassy experience has proven this course of action subject to peril. Although primary concern with the embassy was audio surveillance, elsewhere there are other threats of equal or greater concern, e.g., technical implants may be used to monitor readiness status or interfere with the operation of C3I and weapons systems. Present and future technical penetration threats stretch the imagination. The Soviets have committed substantial hard scientific resources to a broad range of technical intelligence, even including applications or parapsychology. Countering these threats involves continuous TSCM precautions from initial planning to completion. Designs and construction/installation techniques must facilitate technical inspections and preclude the broadest range of known and suspected technical penetration efforts.

  2. System Design Description PFP Thermal Stabilization

    SciTech Connect (OSTI)

    RISENMAY, H.R.

    2000-04-25

    The purpose of this document is to provide a system design description (SDD) and design basis for the Plutonium Finishing Plant (PFP) Thermal Stabilization project. The chief objective of the SDD is to document the Structures, Systems, and Components (SSCs) that establish and maintain the facility Safety Envelope necessary for normal safe operation of the facility; as identified in the FSAR, the OSRs, and Safety Assessment Documents (SADs). This safety equipment documentation should satisfy guidelines for the SDD given in WHC-SD-CP-TI-18 1, Criteria for Identification and Control of Equipment Necessary for Preservation of the Safety Envelope and Safe Operation of PFP. The basis for operational, alarm response, maintenance, and surveillance procedures are also identified and justified in this document. This document and its appendices address the following elements of the PFP Thermal Stabilization project: Functional and design requirements; Design description; Safety Envelope Analysis; Safety Equipment Class; and Operational, maintenance and surveillance procedures.

  3. Statement of Patricia Hoffman, Acting Assistant Secretary for Electricity Delivery and Energy Reliability Before the Subcommittee on Emerging Threats, Cyber Security and Science and Technology Committee on Homeland Security U.S. House of Representatives,

    Broader source: Energy.gov [DOE]

    Statement of Patricia Hoffman, Acting Assistant Secretary for Electricity Delivery and Energy Reliability, before the Subcommittee on Emerging Threats, Cyber Security and Science and Technology,...

  4. A Designed Protein Maps Brain Activity

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

    A Designed Protein Maps Brain Activity Print A team of scientists from the Howard Hughes Medical Institute's Janelia Research Campus designed and validated via x-ray crystallographic studies a fluorescent protein (CaMPARI) that allows the permanent marking of active brain cells. The protein was then used to study live changes via fluorescence in the active nerve cells in brains of fruit flies, zebrafish, and mice. The Neural Basis of Behavior Signals in our brains are propagated with voltage and

  5. A Designed Protein Maps Brain Activity

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

    A Designed Protein Maps Brain Activity Print A team of scientists from the Howard Hughes Medical Institute's Janelia Research Campus designed and validated via x-ray crystallographic studies a fluorescent protein (CaMPARI) that allows the permanent marking of active brain cells. The protein was then used to study live changes via fluorescence in the active nerve cells in brains of fruit flies, zebrafish, and mice. The Neural Basis of Behavior Signals in our brains are propagated with voltage and

  6. A Designed Protein Maps Brain Activity

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

    A Designed Protein Maps Brain Activity Print A team of scientists from the Howard Hughes Medical Institute's Janelia Research Campus designed and validated via x-ray crystallographic studies a fluorescent protein (CaMPARI) that allows the permanent marking of active brain cells. The protein was then used to study live changes via fluorescence in the active nerve cells in brains of fruit flies, zebrafish, and mice. The Neural Basis of Behavior Signals in our brains are propagated with voltage and

  7. A Designed Protein Maps Brain Activity

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

    A Designed Protein Maps Brain Activity Print A team of scientists from the Howard Hughes Medical Institute's Janelia Research Campus designed and validated via x-ray crystallographic studies a fluorescent protein (CaMPARI) that allows the permanent marking of active brain cells. The protein was then used to study live changes via fluorescence in the active nerve cells in brains of fruit flies, zebrafish, and mice. The Neural Basis of Behavior Signals in our brains are propagated with voltage and

  8. Hanford Technical Basis for Multiple Dosimetry Effective Dose Methodology

    SciTech Connect (OSTI)

    Hill, Robin L.; Rathbone, Bruce A.

    2010-08-01

    The current method at Hanford for dealing with the results from multiple dosimeters worn during non-uniform irradiation is to use a compartmentalization method to calculate the effective dose (E). The method, as documented in the current version of Section 6.9.3 in the 'Hanford External Dosimetry Technical Basis Manual, PNL-MA-842,' is based on the compartmentalization method presented in the 1997 ANSI/HPS N13.41 standard, 'Criteria for Performing Multiple Dosimetry.' With the adoption of the ICRP 60 methodology in the 2007 revision to 10 CFR 835 came changes that have a direct affect on the compartmentalization method described in the 1997 ANSI/HPS N13.41 standard, and, thus, to the method used at Hanford. The ANSI/HPS N13.41 standard committee is in the process of updating the standard, but the changes to the standard have not yet been approved. And, the drafts of the revision of the standard tend to align more with ICRP 60 than with the changes specified in the 2007 revision to 10 CFR 835. Therefore, a revised method for calculating effective dose from non-uniform external irradiation using a compartmental method was developed using the tissue weighting factors and remainder organs specified in 10 CFR 835 (2007).

  9. Climate Change: The Physical Basis and Latest Results

    ScienceCinema (OSTI)

    None

    2011-10-06

    The 2007 Assessment Report of the Intergovernmental Panel on Climate Change (IPCC) concludes: "Warming in the climate system is unequivocal." Without the contribution of Physics to climate science over many decades, such a statement would not have been possible. Experimental physics enables us to read climate archives such as polar ice cores and so provides the context for the current changes. For example, today the concentration of CO2 in the atmosphere, the second most important greenhouse gas, is 28% higher than any time during the last 800,000 years. Classical fluid mechanics and numerical mathematics are the basis of climate models from which estimates of future climate change are obtained. But major instabilities and surprises in the Earth System are still unknown. These are also to be considered when the climatic consequences of proposals for geo-engineering are estimated. Only Physics will permit us to further improve our understanding in order to provide the foundation for policy decisions facing the global climate change challenge.

  10. Physics of compact ignition tokamak designs

    SciTech Connect (OSTI)

    Singer, C.E.; Ku, L.P.; Bateman, G.; Seidl, F.; Sugihara, M.

    1986-03-01

    Models for predicting plasma performance in compact ignition experiments are constructed on the basis of theoretical and empirical constraints and data from tokamak experiments. Emphasis is placed on finding transport and confinement models which reproduce results of both ohmically and auxiliary heated tokamak data. Illustrations of the application of the models to compact ignition designs are given.

  11. Center for Inverse Design: Inverse Design Approach

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

    Inverse Design Approach This page describes the inverse materials design methodology used by the Center for Inverse Design, which integrates and combines the following: (1) theory,...

  12. The Structural Basis for Tight Control of PP2A Methylation and...

    Office of Scientific and Technical Information (OSTI)

    The Structural Basis for Tight Control of PP2A Methylation and Function by LCMT-1 Citation Details In-Document Search Title: The Structural Basis for Tight Control of PP2A ...

  13. Basis for the US Modern Grid Strategy - A Changing World

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

    Importance of Smart Grid to Our Nation's Energy Future Steve Pullins President, Horizon Energy Group Steve Bossart Senior Manager, National Energy Technology Laboratory Today's Electricity Grid The U.S. electricity grid is an aging infrastructure based largely on designs of the 1950s before the era of the microprocessor and it was mostly constructed in the 1960s and 1970s. Since the 1970s, the U.S. grid has been expanded as needed to meet load growth using the same vintage technologies. The U.S.

  14. A new paradigm for the molecular basis of rubber elasticity

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

    Hanson, David E.; Barber, John L.

    2015-02-19

    The molecular basis for rubber elasticity is arguably the oldest and one of the most important questions in the field of polymer physics. The theoretical investigation of rubber elasticity began in earnest almost a century ago with the development of analytic thermodynamic models, based on simple, highly-symmetric configurations of so-called Gaussian chains, i.e. polymer chains that obey Markov statistics. Numerous theories have been proposed over the past 90 years based on the ansatz that the elastic force for individual network chains arises from the entropy change associated with the distribution of end-to-end distances of a free polymer chain. There aremore » serious philosophical objections to this assumption and others, such as the assumption that all network nodes undergo affine motion and that all of the network chains have the same length. Recently, a new paradigm for elasticity in rubber networks has been proposed that is based on mechanisms that originate at the molecular level. Using conventional statistical mechanics analyses, quantum chemistry, and molecular dynamics simulations, the fundamental entropic and enthalpic chain extension forces for polyisoprene (natural rubber) have been determined, along with estimates for the basic force constants. Concurrently, the complex morphology of natural rubber networks (the joint probability density distributions that relate the chain end-to-end distance to its contour length) has also been captured in a numerical model. When molecular chain forces are merged with the network structure in this model, it is possible to study the mechanical response to tensile and compressive strains of a representative volume element of a polymer network. As strain is imposed on a network, pathways of connected taut chains, that completely span the network along strain axis, emerge. Although these chains represent only a few percent of the total, they account for nearly all of the elastic stress at high strain. Here we provide a brief review of previous elasticity theories and their deficiencies, and present a new paradigm with an emphasis on experimental comparisons.« less

  15. Post Quench Ductility Evaluation of Zircaloy-4 and Select Iron Alloys under Design Basis and Extended LOCA Conditions

    SciTech Connect (OSTI)

    Yan, Yong; Keiser, James R; Terrani, Kurt A; Bell, Gary L; Snead, Lance

    2014-01-01

    Oxidation experiments were conducted at 1200 C in flowing steam with tubing specimens of Zircaloy-4, 317, 347 stainless steels, and the commercial FeCrAl alloy APMT. The purpose was to determine the oxidation behavior and post quench ductility of these alloys under postulated loss-of-coolant accident conditions. The parabolic rate constant for Zircaloy-4 tubing samples at 1200 were determined to be k = 2.173 107 g2/cm4/s C, in excellent agreement with the Cathcart-Pawel correlation. The APMT alloy experienced the slowest oxidation rate among all materials examined in this work. The ductility of post quenched samples was evaluated by ring compression tests at 135 C. For Zircaloy-4, the ductile to brittle transition occurs at an equivalent cladding reacted (ECR) of 19.3%. SS-347 was still ductile after being oxidized for 2400 s (CP-ECR 50%), but the maximum load was reduced significantly owing to the metal layer thickness reduction. No ductility decrease was observed for the post-quenched APMT samples oxidized up to four hours.

  16. Transmittal Memorandum, Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events, September 2011

    Broader source: Energy.gov [DOE]

    The March 2011 accident at the Fukushima Daiichi nuclear power plant, the Department of Energy (DOE) took several actions to review the safety of its nuclear facilities.

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

    Office of Environmental Management (EM)

    - March 2001 | Department of Energy Review of the Lawrence Livermore National Laboratory - March 2001 Independent Oversight Review of the Lawrence Livermore National Laboratory - March 2001 March 2001 Review of the Lawrence Livermore National Laboratory Health Services Department This report provides the results of an independent oversight review of the Health Services Division at the Department of Energy's (DOE) Lawrence Livermore National Laboratory. The review was performed March 19-21,

  18. Molecular medicine for the 21. century: A computational basis for design and critique of vaccines and therapeutics

    SciTech Connect (OSTI)

    Lapedes, A.; Myers, G.; Perelson, A.; Farber, R.; Tung, C.S.

    1997-08-01

    This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The kissing-loop RNA motif is thought to modulate different steps in the retroviral life cycle. Using an RNA folding protocol developed under this project, the authors are studying the folding of the potential kissing-loop motif in HIV. Using only limited information on base-springs, and the constraints based on the connectivities, they are modeling the structure and the flexibility of this particular structural motif and have developed three predicted structures with low conformational energy. Following on the earlier work which analyzed correlated mutations in the V3 loop of HIV, they have developed an evolutionary model which incorporates non-independent mutations at different sequence positions in model sequences. This model takes into account the effects of the phylogenetic tree on the analysis of mutations, and shows a higher correspondence of correlated positions with structurally adjacent positions in the model than previous analyses. Additional research under this project has dealt with analyzing the dynamics of HIV in vivo. Using some simple models and patient data, they were able to establish for the first time some quantitative estimates of HIV dynamics in vivo.

  19. TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

    SciTech Connect (OSTI)

    BERGLIN, E J

    2003-06-23

    This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

  20. Establishing the Technical Basis for Disposal of Heat-generating Waste in

    Energy Savers [EERE]

    Salt | Department of Energy Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt The report summarizes available historic tests and the developed technical basis for disposal of heat-generating waste in salt, and the means by which a safety case for disposal of heat generating waste at a generic salt site can be initiated from the existing technical basis. Though the basis for a salt

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

    SciTech Connect (OSTI)

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

    2009-09-01

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

  2. Structural basis for inhibition of DNA replication by aphidicolin

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

    Baranovskiy, A. G.; Babayeva, N. D.; Suwa, Y.; Gu, J.; Pavlov, Y. I.; Tahirov, T. H.

    2014-11-27

    Natural tetracyclic diterpenoid aphidicolin is a potent and specific inhibitor of B-family DNA polymerases, haltering replication and possessing a strong antimitotic activity in human cancer cell lines. Clinical trials revealed limitations of aphidicolin as an antitumor drug because of its low solubility and fast clearance from human plasma. The absence of structural information hampered the improvement of aphidicolin-like inhibitors: more than 50 modifications have been generated so far, but all have lost the inhibitory and antitumor properties. Here we report the crystal structure of the catalytic core of human DNA polymerase α (Pol α) in the ternary complex with anmore » RNA-primed DNA template and aphidicolin. The inhibitor blocks binding of dCTP by docking at the Pol α active site and by rotating the template guanine. The structure provides a plausible mechanism for the selectivity of aphidicolin incorporation opposite template guanine and explains why previous modifications of aphidicolin failed to improve its affinity for Pol α. With new structural information, aphidicolin becomes an attractive lead compound for the design of novel derivatives with enhanced inhibitory properties for B-family DNA polymerases.« less

  3. Structural basis for the blockade of MATE multidrug efflux pumps

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

    Radchenko, Martha; Symersky, Jindrich; Nie, Rongxin; Lu, Min

    2015-08-06

    Multidrug and toxic compound extrusion (MATE) transporters underpin multidrug resistance by using the H+ or Na+ electrochemical gradient to extrude different drugs across cell membranes. MATE transporters can be further parsed into the DinF, NorM and eukaryotic subfamilies based on their amino-acid sequence similarity. Here we report the 3.0 Å resolution X-ray structures of a protonation-mimetic mutant of an H+-coupled DinF transporter, as well as of an H+-coupled DinF and a Na+-coupled NorM transporters in complexes with verapamil, a small-molecule pharmaceutical that inhibits MATE-mediated multidrug extrusion. Combining structure-inspired mutational and functional studies, we confirm the biological relevance of our crystalmore » structures, reveal the mechanistic differences among MATE transporters, and suggest how verapamil inhibits MATE-mediated multidrug efflux. Our findings offer insights into how MATE transporters extrude chemically and structurally dissimilar drugs and could inform the design of new strategies for tackling multidrug resistance.« less

  4. Structural basis for inhibition of DNA replication by aphidicolin

    SciTech Connect (OSTI)

    Baranovskiy, A. G.; Babayeva, N. D.; Suwa, Y.; Gu, J.; Pavlov, Y. I.; Tahirov, T. H.

    2014-11-27

    Natural tetracyclic diterpenoid aphidicolin is a potent and specific inhibitor of B-family DNA polymerases, haltering replication and possessing a strong antimitotic activity in human cancer cell lines. Clinical trials revealed limitations of aphidicolin as an antitumor drug because of its low solubility and fast clearance from human plasma. The absence of structural information hampered the improvement of aphidicolin-like inhibitors: more than 50 modifications have been generated so far, but all have lost the inhibitory and antitumor properties. Here we report the crystal structure of the catalytic core of human DNA polymerase α (Pol α) in the ternary complex with an RNA-primed DNA template and aphidicolin. The inhibitor blocks binding of dCTP by docking at the Pol α active site and by rotating the template guanine. The structure provides a plausible mechanism for the selectivity of aphidicolin incorporation opposite template guanine and explains why previous modifications of aphidicolin failed to improve its affinity for Pol α. With new structural information, aphidicolin becomes an attractive lead compound for the design of novel derivatives with enhanced inhibitory properties for B-family DNA polymerases.

  5. Structural basis for the blockade of MATE multidrug efflux pumps

    SciTech Connect (OSTI)

    Radchenko, Martha; Symersky, Jindrich; Nie, Rongxin; Lu, Min

    2015-08-06

    Multidrug and toxic compound extrusion (MATE) transporters underpin multidrug resistance by using the H+ or Na+ electrochemical gradient to extrude different drugs across cell membranes. MATE transporters can be further parsed into the DinF, NorM and eukaryotic subfamilies based on their amino-acid sequence similarity. Here we report the 3.0 Å resolution X-ray structures of a protonation-mimetic mutant of an H+-coupled DinF transporter, as well as of an H+-coupled DinF and a Na+-coupled NorM transporters in complexes with verapamil, a small-molecule pharmaceutical that inhibits MATE-mediated multidrug extrusion. Combining structure-inspired mutational and functional studies, we confirm the biological relevance of our crystal structures, reveal the mechanistic differences among MATE transporters, and suggest how verapamil inhibits MATE-mediated multidrug efflux. Our findings offer insights into how MATE transporters extrude chemically and structurally dissimilar drugs and could inform the design of new strategies for tackling multidrug resistance.

  6. Emerging Threats and Opportunities

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

    to formation of consortium led by the University of Michigan that focuses on research and development of arms control verification technologies. Contact Operator Los Alamos...

  7. nuclear threat science

    National Nuclear Security Administration (NNSA)

    8%2A en Office of Counterterrorism Policy and Cooperation http:www.nnsa.energy.govaboutusourprogramsctcppolicyandcooperation

  8. Global Threat Reduction Initiative

    Office of Environmental Management (EM)

    Department of Energy Minimize Nuclear Waste Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear Waste GNEP will increase the efficiency in the management of used nuclear fuel, also known as spent fuel, and defer the need for additional geologic nuclear waste repositories until the next century. PDF icon Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear Waste More Documents & Publications GNEP Element:Develop Enhanced Nuclear Safeguards Global Nuclear Energy

  9. Global Threat Reduction Initiative

    Office of Environmental Management (EM)

    comprehensive strategy to prevent nuclear terrorism; and  The key organization responsible for implementing the U.S. HEU minimization policy. GTRI MISSION Reduce and protect vulnerable nuclear and radiological material located at civilian sites worldwide. DOE STRATEGIC GOAL 2.2 Prevent the acquisition of nuclear and radiological materials for use in weapons of mass destruction and other acts of terrorism Protect high priority nuclear and radiological materials from theft and sabotage These

  10. Physics Basis for the Advanced Tokamak Fusion Power Plant ARIES-AT

    SciTech Connect (OSTI)

    S.C. Jardin; C.E. Kessel; T.K. Mau; R.L. Miller; F. Najmabadi; V.S. Chan; M.S. Chu; R. LaHaye; L.L. Lao; T.W. Petrie; P. Politzer; H.E. St. John; P. Snyder; G.M. Staebler; A.D. Turnbull; W.P. West

    2003-10-07

    The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A always equal to R/a = 4.0, an elongation and triangularity of kappa = 2.20, delta = 0.90 (evaluated at the separatrix surface), a toroidal beta of beta = 9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of bN * 100 x b/(I(sub)P(MA)/a(m)B(T)) = 5.4. These beta values are chosen to be 10% below the ideal-MHD stability limit. The bootstrap-current fraction is fBS * I(sub)BS/I(sub)P = 0.91. This leads to a design with total plasma current I(sub)P = 12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m, respectively. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current-drive system consists of ICRF/FW for on-axis current drive and a lower-hybrid system for off-axis. Tran sport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.

  11. Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

    SciTech Connect (OSTI)

    Hickey, Eva E.; Strom, Daniel J.

    2005-08-01

    Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

  12. Enterprise Assessments Targeted Review of the Safety Basis at the Savannah

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

    River Site F-Area Central Laboratory Facility - January 2016 | Department of Energy Basis at the Savannah River Site F-Area Central Laboratory Facility - January 2016 Enterprise Assessments Targeted Review of the Safety Basis at the Savannah River Site F-Area Central Laboratory Facility - January 2016 January 2016 Review of the Safety Basis F-Area Central Laboratory Facility at the Savannah River Site The Office of Nuclear Safety and Environmental Assessments, within the U.S. Department of

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

    Broader source: Energy.gov [DOE]

    This SRP, Nuclear Safety Basis Program Review, consists of five volumes. It provides information to help strengthen the technical rigor of line management oversight and federal monitoring of DOE nuclear facilities. It provides a primer on the safety basis development and documentation process used by the DOE. It also provides a set of LOIs for the review of safety basis programs and documents of nuclear facilities at various stages of the facility life cycle.

  14. Technical Basis and Considerations for DOE M 435.1-1 (Appendix A)

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

    1999-07-09

    This appendix establishes the technical basis of the order revision process and of each of the requirements included in the revised radioactive waste management order.

  15. Structural basis for the prion-like MAVS filaments in antiviral...

    Office of Scientific and Technical Information (OSTI)

    in antiviral innate immunity Citation Details In-Document Search Title: Structural basis for the prion-like MAVS filaments in antiviral innate immunity Authors: Xu, Hui ; He, ...

  16. 2010 DOE National Science BowlÂź Photos - Basis Charter School...

    Office of Science (SC) Website

    Basis Charter School National Science Bowl (NSB) NSB Home About National Science Bowl Contacts Regional Science Bowl Coordinators National Science Bowl FAQ's Alumni Past National ...

  17. Advanced conceptual design report. Phase II. Liquid effluent treatment and disposal Project W-252

    SciTech Connect (OSTI)

    1995-01-31

    This Advanced Conceptual Design Report (ACDR) provides a documented review and analysis of the Conceptual Design Report (CDR), WHC-SD-W252-CDR-001, June 30, 1993. The ACDR provides further design evaluation of the major design approaches and uncertainties identified in the original CDR. The ACDR will provide a firmer basis for the both the design approach and the associated planning for the performance of the Definitive Design phase of the project.

  18. Open PCS Security Architecture For Interoperable Design (OPSAID) |

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

    Department of Energy Open PCS Security Architecture For Interoperable Design (OPSAID) Open PCS Security Architecture For Interoperable Design (OPSAID) The OPSAID program provides a design basis for vendors to build add-on security devices. The addition of these devices can bring the security of legacy systems up to an acceptable level, while providing a path forward for the development of inherently-secure PCS elements in the future. PDF icon Open PCS Security Architecture For Interoperable

  19. Safety Design Strategy Standard Review Plan (SRP)

    Broader source: Energy.gov [DOE]

    This SRP on Safety Design Strategy (SDS) provides the starting point for a set of corporate Performance Objectives and Criteria contain in Appendix A. Review teams are expected to build on these and develop additional project-specific Lines of Inquiry, as needed. The criteria and the review process are intended to be used on an ongoing basis during the appropriate CD phase to ensure that issues are identified and resolved.

  20. Criteria Document for B-plant Surveillance and Maintenance Phase Safety Basis Document

    SciTech Connect (OSTI)

    SCHWEHR, B.A.

    1999-08-31

    This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S&M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S&M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S&M Phase safety basis document.

  1. ARIES-ACT1 Safety Design and Analysis

    SciTech Connect (OSTI)

    Humrickhouse, Paul W.; Merrill, Brad J.

    2014-01-01

    ARIES-ACT1 (Advanced and Conservative Tokamak) is a 1000-MW(electric) tokamak design featuring advanced plasma physics and divertor and blanket engineering. Some relevant features include an advanced SiC blanket with PbLi as coolant and breeder; a helium-cooled steel structural ring and tungsten divertors; a thin-walled, helium-cooled vacuum vessel; and a room-temperature, water-cooled shield outside the vacuum vessel. We consider here some safety aspects of the ARIES-ACT1 design and model a series of design-basis and beyond-design-basis accidents with the MELCOR code modified for fusion. The presence of multiple coolants (PbLi, helium, and water) makes possible a variety of such accidents. We consider here a loss-of-flow accident caused by a long-term station blackout (LTSBO), an ex-vessel helium break into the cryostat, and a beyond-design-basis accident in which a LTSBO is aggravated by a loss-of-coolant accident in ARIES-ACT1's ultimate decay heat removal system, the water-cooled shield. In the design-basis accidents, we find that the secondary confinement boundaries are not challenged, and the structural integrity of in-vessel components is not threatened by high temperatures or pressures; decay heat can be passively removed.

  2. Structural basis for effectiveness of siderophore-conjugated monocarbams against clinically relevant strains of Pseudomonas aeruginosa

    SciTech Connect (OSTI)

    Han, Seungil; Zaniewski, Richard P.; Marr, Eric S.; Lacey, Brian M.; Tomaras, Andrew P.; Evdokimov, Artem; Miller, J. Richard; Shanmugasundaram, Veerabahu

    2012-02-08

    Pseudomonas aeruginosa is an opportunistic Gram-negative pathogen that causes nosocomial infections for which there are limited treatment options. Penicillin-binding protein PBP3, a key therapeutic target, is an essential enzyme responsible for the final steps of peptidoglycan synthesis and is covalently inactivated by {beta}-lactam antibiotics. Here we disclose the first high resolution cocrystal structures of the P. aeruginosa PBP3 with both novel and marketed {beta}-lactams. These structures reveal a conformational rearrangement of Tyr532 and Phe533 and a ligand-induced conformational change of Tyr409 and Arg489. The well-known affinity of the monobactam aztreonam for P. aeruginosa PBP3 is due to a distinct hydrophobic aromatic wall composed of Tyr503, Tyr532, and Phe533 interacting with the gem-dimethyl group. The structure of MC-1, a new siderophore-conjugated monocarbam complexed with PBP3 provides molecular insights for lead optimization. Importantly, we have identified a novel conformation that is distinct to the high-molecular-weight class B PBP subfamily, which is identifiable by common features such as a hydrophobic aromatic wall formed by Tyr503, Tyr532, and Phe533 and the structural flexibility of Tyr409 flanked by two glycine residues. This is also the first example of a siderophore-conjugated triazolone-linked monocarbam complexed with any PBP. Energetic analysis of tightly and loosely held computed hydration sites indicates protein desolvation effects contribute significantly to PBP3 binding, and analysis of hydration site energies allows rank ordering of the second-order acylation rate constants. Taken together, these structural, biochemical, and computational studies provide a molecular basis for recognition of P. aeruginosa PBP3 and open avenues for future design of inhibitors of this class of PBPs.

  3. NNSA?s Computing Strategy, Acquisition Plan, and Basis for Computing Time Allocation

    SciTech Connect (OSTI)

    Nikkel, D J

    2009-07-21

    This report is in response to the Omnibus Appropriations Act, 2009 (H.R. 1105; Public Law 111-8) in its funding of the National Nuclear Security Administration's (NNSA) Advanced Simulation and Computing (ASC) Program. This bill called for a report on ASC's plans for computing and platform acquisition strategy in support of stockpile stewardship. Computer simulation is essential to the stewardship of the nation's nuclear stockpile. Annual certification of the country's stockpile systems, Significant Finding Investigations (SFIs), and execution of Life Extension Programs (LEPs) are dependent on simulations employing the advanced ASC tools developed over the past decade plus; indeed, without these tools, certification would not be possible without a return to nuclear testing. ASC is an integrated program involving investments in computer hardware (platforms and computing centers), software environments, integrated design codes and physical models for these codes, and validation methodologies. The significant progress ASC has made in the past derives from its focus on mission and from its strategy of balancing support across the key investment areas necessary for success. All these investment areas must be sustained for ASC to adequately support current stockpile stewardship mission needs and to meet ever more difficult challenges as the weapons continue to age or undergo refurbishment. The appropriations bill called for this report to address three specific issues, which are responded to briefly here but are expanded upon in the subsequent document: (1) Identify how computing capability at each of the labs will specifically contribute to stockpile stewardship goals, and on what basis computing time will be allocated to achieve the goal of a balanced program among the labs. (2) Explain the NNSA's acquisition strategy for capacity and capability of machines at each of the labs and how it will fit within the existing budget constraints. (3) Identify the technical challenges facing the program and a strategy to resolve them.

  4. Technical basis for flawed cylinder test specification to assure adequate fracture resistance of ISO high-strength steel cylinder

    SciTech Connect (OSTI)

    Rana, M.D.; Smith, J.H.; Tribolet, R.O.

    1997-11-01

    High-pressure industrial gases (such as oxygen, nitrogen, argon, hydrogen, etc.) are stored and transported in portable cylinders. ISO TC58 SC3 has developed a draft specification 9809 for design and fabrication of high-pressure cylinders with maximum tensile strength limitation of 1,100 N/mm{sup 2}. In order to extend the ISO 9809 rules for higher than 1,100 N/mm{sup 2} strength level cylinders, a working group WG14 was formed in 1989 to develop new rules to assure adequate fracture resistance. In 1994, WG14 recommended a simple, but unique flawed cylinder test method for design qualification of the cylinder and acceptance criteria to assure adequate fracture resistance. WG14 also recommended Charpy-V-notch impact tests to control the required fracture resistance on production cylinders. This paper presents the technical basis that was employed in developing the flawed cylinder test method and acceptance criteria. The specification was developed for seamless steel cylinders having actual strength in the range of 1,100 to 1,400 N/mm{sup 2} and cylindrical section wall thickness in the range of 3 to 10 mm. Flawed cylinder tests were conducted on several hundred cylinders of varying sizes and strength levels. The specification requires to demonstrate LEAK-BEFORE-BREAK performance of the cylinder having flaw length equal to 1.6 (o.d. {times} t{sub design}){sup 0.5} at failure pressure = (t{sub design}/t{sub actual}) x Design Pressure.

  5. Technical basis for flawed cylinder test specification to assure adequate fracture resistance of ISO high strength steel cylinder

    SciTech Connect (OSTI)

    Rana, M.D.; Smith, J.H.; Tribolet, R.O.

    1996-12-01

    High pressure industrial gases (such as oxygen, nitrogen, argon, hydrogen, etc.) are stored and transported in portable cylinders. ISO TC58 SC3 has developed a draft specification 9809 for design and fabrication of high pressure cylinders with maximum tensile strength limitation of 1,100 N/mm{sup 2}. In order to extend the ISO 9809 rules for higher than 1,100 N/mm{sup 2} strength level cylinders, a working group WG14 was formed in 1989 to develop new rules to assure adequate fracture resistance. In 1994, WG14 recommended a simple, but unique flawed cylinder test method for design qualification of the cylinder and acceptance criteria to assure adequate fracture resistance. WG14 also recommended Charpy-V-Notch impact tests to control the required fracture resistance on production cylinders. This paper presents the technical basis that was employed in developing the flawed cylinder test method and acceptance criteria. The specification was developed for seamless steel cylinders having actual strength in the range of 1,100 to 1,400 N/mm{sup 2} and cylindrical section wall thickness in the range of 3mm to 10mm. Flawed cylinder tests were conducted on several hundred cylinders of varying sizes and strength levels. The specification requires to demonstrate LEAK-BEFORE-BREAK performance of the cylinder having flaw length equal to 1.6(O.D. {times} t{sub design}){sup 0.5} at failure pressure = (t{sub design}/t{sub actual}) {times} Design Pressure.

  6. Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.

    SciTech Connect (OSTI)

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

    2008-03-01

    This report summarizes the results of three detailed studies of the physical protection systems for the protection of nuclear materials transport in Japan, with an emphasis on the transportation of mixed oxide fuel materials1. The Japanese infrastructure for transporting nuclear fuel materials is addressed in the first section. The second section of this report presents a summary of baseline data from the open literature on the threats of sabotage and theft during the transport of nuclear fuel materials in Japan. The third section summarizes a review of current International Atomic Energy Agency, Japanese and United States guidelines and regulations concerning the physical protection for the transportation of nuclear fuel materials.

  7. Structural basis for Notch1 engagement of Delta-like 4 (Journal...

    Office of Scientific and Technical Information (OSTI)

    Title: Structural basis for Notch1 engagement of Delta-like 4 Authors: Luca, Vincent C. ; Jude, Kevin M. ; Pierce, Nathan W. ; Nachury, Maxence V. ; Fischer, Suzanne ; Garcia, K. ...

  8. Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2...

    Office of Scientific and Technical Information (OSTI)

    Recognition by the DDB1-DDB2 Complex Citation Details In-Document Search Title: Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Ultraviolet (UV) ...

  9. Structure of P-Glycoprotein Reveals a Molecular Basis for Poly...

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

    Structure of P-Glycoprotein Reveals a Molecular Basis for Poly-Specific Drug Binding figure 1 Figure 1. Structure of P-gp. Many forms of cancer fail to respond to chemotherapy by ...

  10. NSS 18.3 Verification of Authorization Basis Documentation 12/8/03

    Broader source: Energy.gov [DOE]

    The objective of this surveillance is for the Facility Representative to verify that the facility's configuration and operations remain consistent with the authorization basis.  As defined in DOE...

  11. Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Citation Details In-Document Search Title: Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Ultraviolet (UV) light-induced pyrimidine photodimers are repaired by the nucleotide excision repair pathway. Photolesions have biophysical parameters closely resembling undamaged DNA, impeding discovery through damage surveillance proteins. The DDB1DDB2 complex serves in

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

    Office of Scientific and Technical Information (OSTI)

    National Laboratory fission basis Citation Details In-Document Search Title: Los Alamos National Laboratory fission basis Authors: Keksis, August L [1] ; Chadwick, Mark B [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2011-05-06 OSTI Identifier: 1063939 Report Number(s): LA-UR-11-02744; LA-UR-11-2744 DOE Contract Number: AC52-06NA25396 Resource Type: Conference Resource Relation: Conference: 14th International Symposium on Reactor Dosimetry ; May 22, 2011 ;

  13. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    SciTech Connect (OSTI)

    KURTZ, J.E.

    2000-05-10

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, and radiation surveys of the Cold Vacuum Drying Facility (CVD) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  14. Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | DOE PAGES Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Title: Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Authors: Zeng, Zhixiong ; Wang, Wei ; Yang, Yuting ; Chen, Yong ; Yang, Xiaomei ; Diehl, J. Alan ; Liu, Xuedong ; Lei, Ming Publication Date: 2010-02-01 OSTI Identifier: 1198117 Grant/Contract Number: AC02-06CH11357 Type: Published Article Journal Name: Developmental Cell Additional Journal Information: Journal Volume: 18; Journal Issue:

  15. Structural basis for the prion-like MAVS filaments in antiviral innate

    Office of Scientific and Technical Information (OSTI)

    immunity (Journal Article) | SciTech Connect Structural basis for the prion-like MAVS filaments in antiviral innate immunity Citation Details In-Document Search Title: Structural basis for the prion-like MAVS filaments in antiviral innate immunity Authors: Xu, Hui ; He, Xiaojing ; Zheng, Hui ; Huang, Lily J ; Hou, Fajian ; Yu, Zhiheng ; de la Cruz, Michael Jason ; Borkowski, Brian ; Zhang, Xuewu ; Chen, Zhijian J ; Jiang, Qiu-Xing [1] ; HHMI) [2] + Show Author Affiliations (UTSMC) (

  16. Structural Basis for Specificity and Flexibility in a Plant 4-Coumarate:CoA

    Office of Scientific and Technical Information (OSTI)

    Ligase (Journal Article) | SciTech Connect Structural Basis for Specificity and Flexibility in a Plant 4-Coumarate:CoA Ligase Citation Details In-Document Search Title: Structural Basis for Specificity and Flexibility in a Plant 4-Coumarate:CoA Ligase Authors: Li, Zhi ; Nair, Satish K. [1] + Show Author Affiliations UIUC Publication Date: 2015-12-04 OSTI Identifier: 1227510 Resource Type: Journal Article Resource Relation: Journal Name: Structure; Journal Volume: 23; Journal Issue: (11) ;

  17. Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Citation Details In-Document Search Title: Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Authors: Zeng, Zhixiong ; Wang, Wei ; Yang, Yuting ; Chen, Yong ; Yang, Xiaomei ; Diehl, J. Alan ; Liu, Xuedong ; Lei, Ming Publication Date: 2010-02-01 OSTI Identifier: 1198117 Grant/Contract Number: AC02-06CH11357 Type: Published Article Journal Name: Developmental Cell Additional Journal

  18. Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Citation Details In-Document Search Title: Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Ultraviolet (UV) light-induced pyrimidine photodimers are repaired by the nucleotide excision repair pathway. Photolesions have biophysical parameters closely resembling undamaged DNA, impeding discovery through damage surveillance proteins. The DDB1DDB2 complex serves in

  19. Crystal structure of a ;#8203;BRAF kinase domain monomer explains basis for

    Office of Scientific and Technical Information (OSTI)

    allosteric regulation (Journal Article) | SciTech Connect Crystal structure of a ;#8203;BRAF kinase domain monomer explains basis for allosteric regulation Citation Details In-Document Search Title: Crystal structure of a ;#8203;BRAF kinase domain monomer explains basis for allosteric regulation Authors: Thevakumaran, Neroshan ; Lavoie, Hugo ; Critton, David A. ; Tebben, Andrew ; Marinier, Anne ; Sicheri, Frank ; Therrien , Marc [1] ; Montreal) [2] ; BMS) [2] + Show Author Affiliations

  20. The Three-Dimensional Structural Basis of Type II Hyperprolinemia (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect The Three-Dimensional Structural Basis of Type II Hyperprolinemia Citation Details In-Document Search Title: The Three-Dimensional Structural Basis of Type II Hyperprolinemia Type II hyperprolinemia is an autosomal recessive disorder caused by a deficiency in {Delta}{sup 1}-pyrroline-5-carboxylate dehydrogenase (P5CDH; also known as ALDH4A1), the aldehyde dehydrogenase that catalyzes the oxidation of glutamate semialdehyde to glutamate. Here, we report the first

  1. Non-homogeneous solutions of a Coulomb Schrödinger equation as basis set for scattering problems

    SciTech Connect (OSTI)

    Del Punta, J. A.; Ambrosio, M. J.; Gasaneo, G.; Zaytsev, S. A.; Ancarani, L. U.

    2014-05-15

    We introduce and study two-body Quasi Sturmian functions which are proposed as basis functions for applications in three-body scattering problems. They are solutions of a two-body non-homogeneous Schrödinger equation. We present different analytic expressions, including asymptotic behaviors, for the pure Coulomb potential with a driven term involving either Slater-type or Laguerre-type orbitals. The efficiency of Quasi Sturmian functions as basis set is numerically illustrated through a two-body scattering problem.

  2. Design | Department of Energy

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

    Design Design Earth-sheltered homes, like the one pictured, are a unique option for efficiently designed homes. No matter the type of home you choose, energy efficient design strategies will save you money and energy. | Photo courtesy of Pamm McFadden/NREL. Earth-sheltered homes, like the one pictured, are a unique option for efficiently designed homes. No matter the type of home you choose, energy efficient design strategies will save you money and energy. | Photo courtesy of Pamm

  3. TECHNICAL BASIS FOR EVALUATING SURFACE BARRIERS TO PROTECT GROUNDWATER FROM DEEP VADOSE ZONE CONTAMINATION

    SciTech Connect (OSTI)

    FAYER JM; FREEDMAN VL; WARD AL; CHRONISTER GB

    2010-02-24

    The U.S. DOE and its predecessors released nearly 2 trillion liters (450 billion gallons) of contaminated liquid into the vadose zone at the Hanford Site. Some of the contaminants currently reside in the deeper parts of the vadose zone where they are much less accessible to characterization, monitoring, and typical remediation activities. The DOE Richland Operations Office (DOE-RL) prepared a treatability test plan in 2008 to examine remediation options for addressing contaminants in the deep vadose zone; one of the technologies identified was surface barriers (also known as engineered barriers, covers, and caps). In the typical configuration, the contaminants are located relatively close to the surface, generally within 15 m, and thus they are close to the base of the surface barrier. The proximity of the surface barrier under these conditions yielded few concerns about the effectiveness of the barrier at depth, particularly for cases in which the contaminants were in a lined facility. At Hanford, however, some unlined sites have contaminants located well below depths of 15 m. The issue raised about these sites is the degree of effectiveness of a surface barrier in isolating contaminants in the deep vadose zone. Previous studies by Hanford Site and PNNL researchers suggest that surface barriers have the potential to provide a significant degree of isolation of deep vadose zone contaminants. The studies show that the actual degree of isolation is site-specific and depends on many factors, including recharge rates, barrier size, depth of contaminants, geohydrologic properties ofthe sediments, and the geochemical interactions between the contaminants and the sediments. After the DOE-RL treatability test plan was published, Pacific Northwest National Laboratory was contracted to review the information available to support surface barrier evaluation for the deep vadose zone, identify gaps in the information and outcomes necessary to fill the data gaps, and outline tasks to achieve those outcomes. Full understanding of contaminant behavior in the deep vadose zone is constrained by four key data gaps: limited access; limited data; limited time; and the lack of an accepted predictive capability for determining whether surface barriers can effectively isolate deep vadose zone contaminants. Activities designed to fill these data gaps need to have these outcomes: (1) common evaluation methodology that provides a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination; (2) deep vadose zone data that characterize the lithology, the spatial distribution of moisture and contaminants, the physical, chemical, and biological process that affect the mobility of each contaminant, and the impacts to the contaminants following placement of a surface barrier; (3) subsurface monitoring to provide subsurface characterization of initial conditions and changes that occur during and following remediation activities; and (4) field observations that span years to decades to validate the evaluation methodology. A set of six proposed tasks was identified to provide information needed to address the above outcomes. The proposed tasks are: (1) Evaluation Methodology - Develop common evaluation methodology that will provide a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination. (2) Case Studies - Conduct case studies to demonstrate the applicability ofthe common evaluation methodology and provide templates for subsequent use elsewhere. Three sites expected to have conditions that would yield valuable information and experience pertinent to deep vadose zone contamination were chosen to cover a range of conditions. The sites are BC Cribs and Trenches, U Plant Cribs, and the T Farm Interim Cover. (3) Subsurface Monitoring Technologies - Evaluate minimally invasive geophysical approaches for delineating subsurface plumes and monitoring their migration in the deep

  4. AHTR Mechanical, Structural, And Neutronic Preconceptual Design

    SciTech Connect (OSTI)

    Varma, Venugopal Koikal; Holcomb, David Eugene; Peretz, Fred J; Bradley, Eric Craig; Ilas, Dan; Qualls, A L; Zaharia, Nathaniel M

    2012-10-01

    This report provides an overview of the mechanical, structural, and neutronic aspects of the Advanced High Temperature Reactor (AHTR) design concept. The AHTR is a design concept for a large output Fluoride salt cooled High-temperature Reactor (FHR) that is being developed to enable evaluation of the technology hurdles remaining to be overcome prior to FHRs becoming a commercial reactor class. This report documents the incremental AHTR design maturation performed over the past year and is focused on advancing the design concept to a level of a functional, self-consistent system. The AHTR employs plate type coated particle fuel assemblies with rapid, off-line refueling. Neutronic analysis of the core has confirmed the viability of a 6-month 2-batch cycle with 9 weight-percent enriched uranium fuel. Refueling is intended to be performed automatically under visual guidance using dedicated robotic manipulators. The present design intent is for used fuel to be stored inside of containment for at least 6 months and then transferred to local dry wells for intermediate term, on-site storage. The mechanical and structural concept development effort has included an emphasis on transportation and constructability to minimize construction costs and schedule. The design intent is that all components be factory fabricated into rail transportable modules that are assembled into subsystems at an on-site workshop prior to being lifted into position using a heavy-lift crane in an open-top style construction. While detailed accident identification and response sequence analysis has yet to be performed, the design concept incorporates multiple levels of radioactive material containment including fully passive responses to all identified design basis or non-very-low frequency beyond design basis accidents. Key building design elements include: 1) below grade siting to minimize vulnerability to aircraft impact, 2) multiple natural circulation decay heat rejection chimneys, 3) seismic base isolation, and 4) decay heat powered back-up electricity generation. The report provides a preconceptual design of the manipulators, the fuel transfer system, and the salt transfer loops. The mechanical handling of the fuel and how it is accomplished without instrumentation inside the salt is described within the report. All drives for the manipulators reside outside the reactor top flange. The design has also taken into account the transportability of major components and how they will be assembled on site

  5. AHTR Mechanical, Structural, and Neutronic Preconceptual Design

    SciTech Connect (OSTI)

    Varma, V.K.; Holcomb, D.E.; Peretz, F.J.; Bradley, E.C.; Ilas, D.; Qualls, A.L.; Zaharia, N.M.

    2012-09-15

    This report provides an overview of the mechanical, structural, and neutronic aspects of the Advanced High Temperature Reactor (AHTR) design concept. The AHTR is a design concept for a large output Fluoride salt cooled High-temperature Reactor (FHR) that is being developed to enable evaluation of the technology hurdles remaining to be overcome prior to FHRs becoming an option for commercial reactor deployment. This report documents the incremental AHTR design maturation performed over the past year and is focused on advancing the design concept to a level of a functional, self-consistent system. The reactor concept development remains at a preconceptual level of maturity. While the overall appearance of an AHTR design is anticipated to be similar to the current concept, optimized dimensions will differ from those presented here. The AHTR employs plate type coated particle fuel assemblies with rapid, off-line refueling. Neutronic analysis of the core has confirmed the viability of a 6-month two-batch cycle with 9 wt. % enriched uranium fuel. Refueling is intended to be performed automatically under visual guidance using dedicated robotic manipulators. The report includes a preconceptual design of the manipulators, the fuel transfer system, and the used fuel storage system. The present design intent is for used fuel to be stored inside of containment for at least six months and then transferred to local dry wells for intermediate term, on-site storage. The mechanical and structural concept development effort has included an emphasis on transportation and constructability to minimize construction costs and schedule. The design intent is that all components be factory fabricated into rail transportable modules that are assembled into subsystems at an on-site workshop prior to being lifted into position using a heavy-lift crane in an open-top style construction. While detailed accident identification and response sequence analysis has yet to be performed, the design concept incorporates fully passive responses to all identified design basis or non-very-low frequency beyond design basis accidents as well as multiple levels of radioactive material containment. Key building design elements include (1) below grade siting to minimize vulnerability to aircraft impact, (2) multiple natural circulation decay heat rejection chimneys, (3) seismic base isolation, and (4) decay heat powered back-up electricity generation.

  6. SNL Mechanical Computer Aided Design (MCAD) guide 2007.

    SciTech Connect (OSTI)

    Moore, Brandon; Pollice, Stephanie L.; Martinez, Jack R.

    2007-12-01

    This document is considered a mechanical design best-practice guide to new and experienced designers alike. The contents consist of topics related to using Computer Aided Design (CAD) software, performing basic analyses, and using configuration management. The details specific to a particular topic have been leveraged against existing Product Realization Standard (PRS) and Technical Business Practice (TBP) requirements while maintaining alignment with sound engineering and design practices. This document is to be considered dynamic in that subsequent updates will be reflected in the main title, and each update will be published on an annual basis.

  7. Solar Design Workbook

    SciTech Connect (OSTI)

    Franta, G.; Baylin, F.; Crowther, R.; Dubin, F.; Grace, A., Griffith, J.W.; Holtz, M.; Kutscher, C.; Nordham, D.; Selkowitz, S.; Villecco, M.

    1981-06-01

    This Solar Design Workbook presents solar building design applications for commercial buildir^s. The book is divided into four sections. The first section describes the variety of solar applications in buildings including conservation aspects, solar fundamentals, passive systems, active systems, daylighting, and other solar options. Solar system design evaluation techniques including considerations for building energy requirements, passive systems, active systems, and economics are presented in Section II. The third section attempts to assist the designer in the building design process for energy conservation and solar applications including options and considerations for pre-design, design, and post-design phases. The information required for the solar design proee^ has not been fully developed at this time. Therefore, Section III is incomplete, but an overview of the considerations with some of the design proces elements is presented. Section IV illustrates ease studies that utilize solar applications in the building design.

  8. DOE handbook: Design considerations

    SciTech Connect (OSTI)

    1999-04-01

    The Design Considerations Handbook includes information and suggestions for the design of systems typical to nuclear facilities, information specific to various types of special facilities, and information useful to various design disciplines. The handbook is presented in two parts. Part 1, which addresses design considerations, includes two sections. The first addresses the design of systems typically used in nuclear facilities to control radiation or radioactive materials. Specifically, this part addresses the design of confinement systems and radiation protection and effluent monitoring systems. The second section of Part 1 addresses the design of special facilities (i.e., specific types of nonreactor nuclear facilities). The specific design considerations provided in this section were developed from review of DOE 6430.1A and are supplemented with specific suggestions and considerations from designers with experience designing and operating such facilities. Part 2 of the Design Considerations Handbook describes good practices and design principles that should be considered in specific design disciplines, such as mechanical systems and electrical systems. These good practices are based on specific experiences in the design of nuclear facilities by design engineers with related experience. This part of the Design Considerations Handbook contains five sections, each of which applies to a particular engineering discipline.

  9. Severe Accident Test Station Design Document

    SciTech Connect (OSTI)

    Snead, Mary A.; Yan, Yong; Howell, Michael; Keiser, James R.; Terrani, Kurt A.

    2015-09-01

    The purpose of the ORNL severe accident test station (SATS) is to provide a platform for evaluation of advanced fuels under projected beyond design basis accident (BDBA) conditions. The SATS delivers the capability to map the behavior of advanced fuels concepts under accident scenarios across various temperature and pressure profiles, steam and steam-hydrogen gas mixtures, and thermal shock. The overall facility will include parallel capabilities for examination of fuels and irradiated materials (in-cell) and non-irradiated materials (out-of-cell) at BDBA conditions as well as design basis accident (DBA) or loss of coolant accident (LOCA) conditions. Also, a supporting analytical infrastructure to provide the data-needs for the fuel-modeling components of the Fuel Cycle Research and Development (FCRD) program will be put in place in a parallel manner. This design report contains the information for the first, second and third phase of design and construction of the SATS. The first phase consisted of the design and construction of an out-of-cell BDBA module intended for examination of non-irradiated materials. The second phase of this work was to construct the BDBA in-cell module to test irradiated fuels and materials as well as the module for DBA (i.e. LOCA) testing out-of-cell, The third phase was to build the in-cell DBA module. The details of the design constraints and requirements for the in-cell facility have been closely captured during the deployment of the out-of-cell SATS modules to ensure effective future implementation of the in-cell modules.

  10. Control system design guide

    SciTech Connect (OSTI)

    Sellers, David; Friedman, Hannah; Haasl, Tudi; Bourassa, Norman; Piette, Mary Ann

    2003-05-01

    The ''Control System Design Guide'' (Design Guide) provides methods and recommendations for the control system design process and control point selection and installation. Control systems are often the most problematic system in a building. A good design process that takes into account maintenance, operation, and commissioning can lead to a smoothly operating and efficient building. To this end, the Design Guide provides a toolbox of templates for improving control system design and specification. HVAC designers are the primary audience for the Design Guide. The control design process it presents will help produce well-designed control systems that achieve efficient and robust operation. The spreadsheet examples for control valve schedules, damper schedules, and points lists can streamline the use of the control system design concepts set forth in the Design Guide by providing convenient starting points from which designers can build. Although each reader brings their own unique questions to the text, the Design Guide contains information that designers, commissioning providers, operators, and owners will find useful.

  11. Performance and Fabrication Status of TREAT LEU Conversion Conceptual Design Concepts

    SciTech Connect (OSTI)

    IJ van Rooyen; SR Morrell; AE Wright; E. P Luther; K Jamison; AL Crawford; HT III Hartman

    2014-10-01

    Resumption of transient testing at the TREAT facility was approved in February 2014 to meet U.S. Department of Energy (DOE) objectives. The National Nuclear Security Administration’s Global Threat Reduction Initiative Convert Program is evaluating conversion of TREAT from its existing highly enriched uranium (HEU) core to a new core containing low enriched uranium (LEU). This paper describes briefly the initial pre-conceptual designs screening decisions with more detailed discussions on current feasibility, qualification and fabrication approaches. Feasible fabrication will be shown for a LEU fuel element assembly that can meet TREAT design, performance, and safety requirements. The statement of feasibility recognizes that further development, analysis, and testing must be completed to refine the conceptual design. Engineering challenges such as cladding oxidation, high temperature material properties, and fuel block fabrication along with neutronics performance, will be highlighted. Preliminary engineering and supply chain evaluation provided confidence that the conceptual designs can be achieved.

  12. Human Factors Principles in Design of Computer-Mediated Visualization for Robot Missions

    SciTech Connect (OSTI)

    David I Gertman; David J Bruemmer

    2008-12-01

    With increased use of robots as a resource in missions supporting countermine, improvised explosive devices (IEDs), and chemical, biological, radiological nuclear and conventional explosives (CBRNE), fully understanding the best means by which to complement the human operator’s underlying perceptual and cognitive processes could not be more important. Consistent with control and display integration practices in many other high technology computer-supported applications, current robotic design practices rely highly upon static guidelines and design heuristics that reflect the expertise and experience of the individual designer. In order to use what we know about human factors (HF) to drive human robot interaction (HRI) design, this paper reviews underlying human perception and cognition principles and shows how they were applied to a threat detection domain.

  13. deslover-99.PDF

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

    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 SNM) and nuclear weapons in its custody. One major challenge has been, and remains, ensuring that SNM is well protected, while at the same time

    Cloud Optical Depth Retrieval From MPL-Measured Cloud Boundaries D. H. DeSlover University of Wisconsin-Madison Cooperative Institute for Meteorological Satellite Studies

  14. Time-dependent density functional theory quantum transport simulation in non-orthogonal basis

    SciTech Connect (OSTI)

    Kwok, Yan Ho; Xie, Hang; Yam, Chi Yung; Chen, Guan Hua; Zheng, Xiao

    2013-12-14

    Basing on the earlier works on the hierarchical equations of motion for quantum transport, we present in this paper a first principles scheme for time-dependent quantum transport by combining time-dependent density functional theory (TDDFT) and Keldysh's non-equilibrium Green's function formalism. This scheme is beyond the wide band limit approximation and is directly applicable to the case of non-orthogonal basis without the need of basis transformation. The overlap between the basis in the lead and the device region is treated properly by including it in the self-energy and it can be shown that this approach is equivalent to a lead-device orthogonalization. This scheme has been implemented at both TDDFT and density functional tight-binding level. Simulation results are presented to demonstrate our method and comparison with wide band limit approximation is made. Finally, the sparsity of the matrices and computational complexity of this method are analyzed.

  15. Hamiltonian Light-Front Ffield Theory in a Basis Function Approach

    SciTech Connect (OSTI)

    Vary, J.P.; Honkanen, H.; Li, Jun; Maris, P.; Brodsky, S.J.; Harindranath, A.; de Teramond, G.F.; Sternberg, P.; Ng, E.G.; Yang, C.

    2009-05-15

    Hamiltonian light-front quantum field theory constitutes a framework for the non-perturbative solution of invariant masses and correlated parton amplitudes of self-bound systems. By choosing the light-front gauge and adopting a basis function representation, we obtain a large, sparse, Hamiltonian matrix for mass eigenstates of gauge theories that is solvable by adapting the ab initio no-core methods of nuclear many-body theory. Full covariance is recovered in the continuum limit, the infinite matrix limit. There is considerable freedom in the choice of the orthonormal and complete set of basis functions with convenience and convergence rates providing key considerations. Here, we use a two-dimensional harmonic oscillator basis for transverse modes that corresponds with eigensolutions of the soft-wall AdS/QCD model obtained from light-front holography. We outline our approach, present illustrative features of some non-interacting systems in a cavity and discuss the computational challenges.

  16. JLab Will Begin Testing its Public Address System on a Monthly Basis |

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

    Jefferson Lab Will Begin Testing its Public Address System on a Monthly Basis On April 20, Jefferson Lab Will Begin Testing its Public Address System on a Monthly Basis On Wednesday, April 20, Jefferson Lab will begin conducting a monthly test of its Public Address (PA) System - the live audible announcement feature - available through the lab's Cisco phones. Starting on April 20, these tests will occur at 5:30 p.m. on the third Wednesday of each month. The Public Address System may be used

  17. Structural Basis of Wnt Signaling Inhibition by Dickkopf Binding to LRP5/6

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Basis of Wnt Signaling Inhibition by Dickkopf Binding to LRP5/6 Citation Details In-Document Search Title: Structural Basis of Wnt Signaling Inhibition by Dickkopf Binding to LRP5/6 Authors: Ahn, Victoria E. ; Chu, Matthew Ling-Hon ; Choi, Hee-Jung ; Tran, Denise ; Abo, Arie ; Weis, William I. Publication Date: 2011-11-01 OSTI Identifier: 1198118 Type: Published Article Journal Name: Developmental Cell Additional Journal Information: Journal Volume: 21;

  18. Structural basis of GSK-3 inhibition by N-terminal phosphorylation and by

    Office of Scientific and Technical Information (OSTI)

    the Wnt receptor LRP6 (Journal Article) | SciTech Connect Structural basis of GSK-3 inhibition by N-terminal phosphorylation and by the Wnt receptor LRP6 Citation Details In-Document Search Title: Structural basis of GSK-3 inhibition by N-terminal phosphorylation and by the Wnt receptor LRP6 Authors: Stamos, Jennifer L. ; Chu, Matthew Ling-Hon ; Enos, Michael D. ; Shah, Niket ; Weis, William I. [1] + Show Author Affiliations (Stanford) Publication Date: 2015-02-19 OSTI Identifier: 1168492

  19. Structural Basis for Microcin C7 Inactivation by the MccE Acetyltransferase

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect SciTech Connect Search Results Journal Article: Structural Basis for Microcin C7 Inactivation by the MccE Acetyltransferase Citation Details In-Document Search Title: Structural Basis for Microcin C7 Inactivation by the MccE Acetyltransferase The antibiotic microcin C7 (McC) acts as a bacteriocide by inhibiting aspartyl-tRNA synthetase and stalling the protein translation machinery. McC is synthesized as a heptapeptide-nucleotide conjugate, which is

  20. Structural Basis of Selective Ubiquitination of TRF1 by SCF[superscript

    Office of Scientific and Technical Information (OSTI)

    Fbx4] (Journal Article) | SciTech Connect SciTech Connect Search Results Journal Article: Structural Basis of Selective Ubiquitination of TRF1 by SCF[superscript Fbx4] Citation Details In-Document Search Title: Structural Basis of Selective Ubiquitination of TRF1 by SCF[superscript Fbx4] TRF1 is a critical regulator of telomere length. As such, TRF1 levels are regulated by ubiquitin-dependent proteolysis via an SCF E3 ligase where Fbx4 contributes to substrate specification. Here, we report

  1. The Structural Basis for Tight Control of PP2A Methylation and Function by

    Office of Scientific and Technical Information (OSTI)

    LCMT-1 (Journal Article) | SciTech Connect The Structural Basis for Tight Control of PP2A Methylation and Function by LCMT-1 Citation Details In-Document Search Title: The Structural Basis for Tight Control of PP2A Methylation and Function by LCMT-1 Proper formation of protein phosphatase 2A (PP2A) holoenzymes is essential for the fitness of all eukaryotic cells. Carboxyl methylation of the PP2A catalytic subunit plays a critical role in regulating holoenzyme assembly; methylation is

  2. Universal basis of two-center functions. Test computations of certain diatomic molecules and ions

    SciTech Connect (OSTI)

    Kirnos, V.F.; Samsonov, B.F.; Cheglokov, E.I.

    1987-05-01

    It is shown that the basis of two-center functions is universal. The dependence of the nuclei of atoms comprising a molecule on charges and on the intranuclear spacing is separated explicitly in the integrals used in analyzing diatomic molecules. The basis integrals constructed once permitted rapid and effective execution of computations for the ground state potential curves for a number of electron systems: H/sub 2/, He/sub 2//sup 2 +/, HeH/sup +/, He/sub 2/, LiH, Li/sub 2/, HeB/sup +/, Be/sub 2/.

  3. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    SciTech Connect (OSTI)

    ELGIN, J.C.

    2000-10-02

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, radiation surveys of the Cold Vacuum Drying Facility (CVD), and radiation surveys of the Canister Storage Building (CSB) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  4. Electron Anomalous Magnetic Moment in Basis Light-Front Quantization Approach

    SciTech Connect (OSTI)

    Zhao, Xingbo; Honkanen, Heli; Maris, Pieter; Vary, James P.; Brodsky, Stanley J.; /SLAC

    2012-02-17

    We apply the Basis Light-Front Quantization (BLFQ) approach to the Hamiltonian field theory of Quantum Electrodynamics (QED) in free space. We solve for the mass eigenstates corresponding to an electron interacting with a single photon in light-front gauge. Based on the resulting non-perturbative ground state light-front amplitude we evaluate the electron anomalous magnetic moment. The numerical results from extrapolating to the infinite basis limit reproduce the perturbative Schwinger result with relative deviation less than 1.2%. We report significant improvements over previous works including the development of analytic methods for evaluating the vertex matrix elements of QED.

  5. Analytic matrix elements for the two-electron atomic basis with logarithmic terms

    SciTech Connect (OSTI)

    Liverts, Evgeny Z.; Barnea, Nir

    2014-08-01

    The two-electron problem for the helium-like atoms in S-state is considered. The basis containing the integer powers of ln r, where r is a radial variable of the Fock expansion, is studied. In this basis, the analytic expressions for the matrix elements of the corresponding Hamiltonian are presented. These expressions include only elementary and special functions, what enables very fast and accurate computation of the matrix elements. The decisive contribution of the correct logarithmic terms to the behavior of the two-electron wave function in the vicinity of the triple-coalescence point is reaffirmed.

  6. Design Evolution Study - Aging Options

    SciTech Connect (OSTI)

    P. McDaniel

    2002-04-05

    The purpose of this study is to identify options and issues for aging commercial spent nuclear fuel received for disposal at the Yucca Mountain Mined Geologic Repository. Some early shipments of commercial spent nuclear fuel to the repository may be received with high-heat-output (younger) fuel assemblies that will need to be managed to meet thermal goals for emplacement. The capability to age as much as 40,000 metric tons of heavy metal of commercial spent nuclear he1 would provide more flexibility in the design to manage this younger fuel and to decouple waste receipt and waste emplacement. The following potential aging location options are evaluated: (1) Surface aging at four locations near the North Portal; (2) Subsurface aging in the permanent emplacement drifts; and (3) Subsurface aging in a new subsurface area. The following aging container options are evaluated: (1) Complete Waste Package; (2) Stainless Steel inner liner of the waste package; (3) Dual Purpose Canisters; (4) Multi-Purpose Canisters; and (5) New disposable canister for uncanistered commercial spent nuclear fuel. Each option is compared to a ''Base Case,'' which is the expected normal waste packaging process without aging. A Value Engineering approach is used to score each option against nine technical criteria and rank the options. Open issues with each of the options and suggested future actions are also presented. Costs for aging containers and aging locations are evaluated separately. Capital costs are developed for direct costs and distributable field costs. To the extent practical, unit costs are presented. Indirect costs, operating costs, and total system life cycle costs will be evaluated outside of this study. Three recommendations for aging commercial spent nuclear fuel--subsurface, surface, and combined surface and subsurface are presented for further review in the overall design re-evaluation effort. Options that were evaluated but not recommended are: subsurface aging in a new subsurface area (high cost); surface aging in the complete waste package (risk to the waste package and impact on the Waste Handling Facility); and aging in the stainless steel liner (impact on the waste package design and new high risk operations added to the waste packaging process). The selection of a design basis for aging will be made in conjunction with the other design re-evaluation studies.

  7. System Design | Department of Energy

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

    System Design System Design This template is used to define the system design PDF icon System Design More Documents & Publications Transition Plan Training Plan Feasibility Study ...

  8. development-plans-and-design

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

    detonation detection Radiological Security The program collaborates with domestic and international partners to address the threat of illicit use of high-priority radiological materials in the United States and abroad. The Radiological Security program accomplishes its mission by removing and disposing of excess or orphaned... Global Material Security The mission of the Office of Global Material Security (GMS) is to help partner countries secure and account for nuclear weapons, weapons-useable

  9. Designated Team Leader

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

    Designated Team Leader Each user project is coordinated by a Designated Team Leader (DTL) who may also be the Principal Investigator (PI). The DTL must provide details of all...

  10. Final Design RM

    Office of Environmental Management (EM)

    ... Do adequate calculations exist to support the selected design? (ED-2.3) Are vessels and piping systems designed, sized, and qualified to the ASME Boiler and Pressure Vessel Code ...

  11. Conceptual Safety Design RM

    Broader source: Energy.gov [DOE]

    The Conceptual Safety Design (CSD) Review Module (RM) is a tool that assists DOE federal project review teams in evaluating the adequacy of the Conceptual Safety Design work, processes and...

  12. Energy design for architects

    SciTech Connect (OSTI)

    Shaw, A.

    1989-01-01

    This book contains techniques for energy efficiency in architectural design. Many aspects are covered including: cost; comfort and health; energy use; the design process; and analytical techniques. 202 figs. (JF)

  13. Photonic Design for Photovoltaics

    SciTech Connect (OSTI)

    Kosten, E.; Callahan, D.; Horowitz, K.; Pala, R.; Atwater, H.

    2014-08-28

    We describe photonic design approaches for silicon photovoltaics including i) trapezoidal broadband light trapping structures ii) broadband light trapping with photonic crystal superlattices iii) III-V/Si nanowire arrays designed for broadband light trapping.

  14. System Design Stage

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

    1997-05-21

    This chapter addresses translating the user-oriented functional design specifications into a set of technical, computer-oriented system design specifications; and designing the data structure and processes to the level of detail necessary to plan and execute the Programming and Installation Stages.

  15. Margin of Safety Definition and Examples Used in Safety Basis Documents and the USQ Process

    SciTech Connect (OSTI)

    Beaulieu, R. A.

    2013-10-03

    The Nuclear Safety Management final rule, 10 CFR 830, provides an undefined term, margin of safety (MOS). Safe harbors listed in 10 CFR 830, Table 2, such as DOE-STD-3009 use but do not define the term. This lack of definition has created the need for the definition. This paper provides a definition of MOS and documents examples of MOS as applied in a U.S. Department of Energy (DOE) approved safety basis for an existing nuclear facility. If we understand what MOS looks like regarding Technical Safety Requirements (TSR) parameters, then it helps us compare against other parameters that do not involve a MOS. This paper also documents parameters that are not MOS. These criteria could be used to determine if an MOS exists in safety basis documents. This paper helps DOE, including the National Nuclear Security Administration (NNSA) and its contractors responsible for the safety basis improve safety basis documents and the unreviewed safety question (USQ) process with respect to MOS.

  16. CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor

    Broader source: Energy.gov [DOE]

    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) used for a February 2007 assessment of the Safety Basis in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

  17. CRAD, Safety Basis- Oak Ridge National Laboratory TRU ALPHA LLWT Project

    Broader source: Energy.gov [DOE]

    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) used for a November 2003 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

  18. CRAD, Safety Basis- Los Alamos National Laboratory TA 55 SST Facility

    Broader source: Energy.gov [DOE]

    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) used for an assessment of the Safety Basis at the Los Alamos National Laboratory TA 55 SST Facility.

  19. CRAD, Safety Basis- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    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) used for an assessment of the Safety Basis portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  20. CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR

    Broader source: Energy.gov [DOE]

    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) used for a February 2007 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

  1. CRAD, Safety Basis- Y-12 Enriched Uranium Operations Oxide Conversion Facility

    Broader source: Energy.gov [DOE]

    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) used for a January 2005 assessment of the Safety Basis at the Y-12 - Enriched Uranium Operations Oxide Conversion Facility.

  2. Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan

    SciTech Connect (OSTI)

    HARRIS, J.P.

    1999-08-31

    This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522.

  3. Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan

    SciTech Connect (OSTI)

    HARRIS, J.P.

    2000-03-27

    This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522.

  4. Sensitivity of the Properties of Ruthenium “Blue Dimer” to Method, Basis Set, and Continuum Model

    SciTech Connect (OSTI)

    Ozkanlar, Abdullah; Clark, Aurora E.

    2012-05-23

    The ruthenium “blue dimer” [(bpy)2RuIIIOH2]2O4+ is best known as the first well-defined molecular catalyst for water oxidation. It has been subject to numerous computational studies primarily employing density functional theory. However, those studies have been limited in the functionals, basis sets, and continuum models employed. The controversy in the calculated electronic structure and the reaction energetics of this catalyst highlights the necessity of benchmark calculations that explore the role of density functionals, basis sets, and continuum models upon the essential features of blue-dimer reactivity. In this paper, we report Kohn-Sham complete basis set (KS-CBS) limit extrapolations of the electronic structure of “blue dimer” using GGA (BPW91 and BP86), hybrid-GGA (B3LYP), and meta-GGA (M06-L) density functionals. The dependence of solvation free energy corrections on the different cavity types (UFF, UA0, UAHF, UAKS, Bondi, and Pauling) within polarizable and conductor-like polarizable continuum model has also been investigated. The most common basis sets of double-zeta quality are shown to yield results close to the KS-CBS limit; however, large variations are observed in the reaction energetics as a function of density functional and continuum cavity model employed.

  5. Dynamical properties of non-ideal plasma on the basis of effective potentials

    SciTech Connect (OSTI)

    Ramazanov, T. S.; Kodanova, S. K.; Moldabekov, Zh. A.; Issanova, M. K.

    2013-11-15

    In this work, stopping power has been calculated on the basis of the Coulomb logarithm using the effective potentials. Calculations of the Coulomb logarithm and stopping power for different interaction potentials and degrees of ionization are compared. The comparison with the data of other theoretical and experimental works was carried out.

  6. Advanced Design Mixer Pump Tank 18 Design Modifications Summary Report

    SciTech Connect (OSTI)

    Adkins, B.J.

    2002-12-03

    The Westinghouse Savannah River Company (WSRC) is preparing to retrieve high level waste (HLW) from Tank 18 in early FY03 to provide feed for the Defense Waste Processing Facility (DWPF) and to support tank closure in FY04. As part of the Tank 18 project, WSRC will install a single Advanced Design Mixer Pump (ADMP) in the center riser of Tank 18 to mobilize, suspend, and mix radioactive sludge in preparation for transfer to Tank 7. The use of a single ADMP is a change to the current baseline of four (4) standard slurry pumps used during previous waste retrieval campaigns. The ADMP was originally conceived by Hanford and supported by SRS to provide a more reliable and maintainable mixer pump for use throughout the DOE complex. The ADMP underwent an extensive test program at SRS between 1998 and 2002 to assess reliability and hydraulic performance. The ADMP ran for approximately 4,200 hours over the four-year period. A detailed tear down and inspection of the pump following the 4,2 00-hour run revealed that the gas mechanical seals and anti-friction bearings would need to be refurbished/replaced prior to deployment in Tank 18. Design modifications were also needed to meet current Authorization Basis safety requirements. This report documents the modifications made to the ADMP in support of Tank 18 deployment. This report meets the requirements of Tanks Focus Area (TFA) Milestone 3591.4-1, ''Issue Report on Modifications Made to the ADMP,'' contained in Technical Task Plan (TTP) SR16WT51, ''WSRC Retrieval and Closure.''

  7. Topsides equipment, operating flexibility key floating LNG design

    SciTech Connect (OSTI)

    Yost, K.; Lopez, R.; Mok, J.

    1998-03-09

    Use of a large-scale floating liquefied natural gas (LNG) plant is an economical alternative to an onshore plant for producing from an offshore field. Mobil Technology Co., Dallas, has advanced a design for such a plant that is technically feasible, economical, safe, and reliable. Presented were descriptions of the general design basis, hull modeling and testing, topsides and storage layouts, and LNG offloading. But such a design also presents challenges for designing topsides equipment in an offshore environment and for including flexibility and safety. These are covered in this second article. Mobil`s floating LNG plant design calls for a square concrete barge with a moon-pool in the center. It is designed to produce 6 million tons/year of LNG with up to 55,000 b/d of condensate from 1 bcfd of raw feed gas.

  8. Automated design synthesis of robotic/human workcells for improved manufacturing system design in hazardous environments

    SciTech Connect (OSTI)

    Williams, Joshua M.

    2012-06-12

    Manufacturing tasks that are deemed too hazardous for workers require the use of automation, robotics, and/or other remote handling tools. The associated hazards may be radiological or nonradiological, and based on the characteristics of the environment and processing, a design may necessitate robotic labor, human labor, or both. There are also other factors such as cost, ergonomics, maintenance, and efficiency that also effect task allocation and other design choices. Handling the tradeoffs of these factors can be complex, and lack of experience can be an issue when trying to determine if and what feasible automation/robotics options exist. To address this problem, we utilize common engineering design approaches adapted more for manufacturing system design in hazardous environments. We limit our scope to the conceptual and embodiment design stages, specifically a computational algorithm for concept generation and early design evaluation. In regard to concept generation, we first develop the functional model or function structure for the process, using the common 'verb-noun' format for describing function. A common language or functional basis for manufacturing was developed and utilized to formalize function descriptions and guide rules for function decomposition. Potential components for embodiment are also grouped in terms of this functional language and are stored in a database. The properties of each component are given as quantitative and qualitative criteria. Operators are also rated for task-relevant criteria which are used to address task compatibility. Through the gathering of process requirements/constraints, construction of the component database, and development of the manufacturing basis and rule set, design knowledge is stored and available for computer use. Thus, once the higher level process functions are defined, the computer can automate the synthesis of new design concepts through alternating steps of embodiment and function structure updates/decomposition. In the process, criteria guide function allocation of components/operators and help ensure compatibility and feasibility. Through multiple function assignment options and varied function structures, multiple design concepts are created. All of the generated designs are then evaluated based on a number of relevant evaluation criteria: cost, dose, ergonomics, hazards, efficiency, etc. These criteria are computed using physical properties/parameters of each system based on the qualities an engineer would use to make evaluations. Nuclear processes such as oxide conversion and electrorefining are utilized to aid algorithm development and provide test cases for the completed program. Through our approach, we capture design knowledge related to manufacturing and other operations in hazardous environments to enable a computational program to automatically generate and evaluate system design concepts.

  9. Assessment of Offshore Wind System Design, Safety, and Operation Standards

    SciTech Connect (OSTI)

    Sirnivas, S.; Musial, W.; Bailey, B.; Filippelli, M.

    2014-01-01

    This report is a deliverable for a project sponsored by the U.S. Department of Energy (DOE) entitled National Offshore Wind Energy Resource and Design Data Campaign -- Analysis and Collaboration (contract number DE-EE0005372; prime contractor -- AWS Truepower). The project objective is to supplement, facilitate, and enhance ongoing multiagency efforts to develop an integrated national offshore wind energy data network. The results of this initiative are intended to 1) produce a comprehensive definition of relevant met-ocean resource assets and needs and design standards, and 2) provide a basis for recommendations for meeting offshore wind energy industry data and design certification requirements.

  10. Foundation Design Handbook

    SciTech Connect (OSTI)

    Carmody, John; Mosiman, Garrett; Handeen, Daniel; Huelman, Patrick; Christian, Jeffery

    2013-10-01

    The purpose of this handbook is to provide information that will enable designers, builders, and homeowners to understand foundation design problems and solutions. The foundation of a house is a somewhat invisible and sometimes ignored component of the building. It is increasingly evident, however, that attention to good foundation design and construction has significant benefits to the homeowner and the builder, and can avoid some serious future problems. Good foundation design and construction practice means not only insulating to save energy, but also providing effective structural design as well as moisture, termite, and radon control techniques where appropriate.

  11. Hanford Site waste tank farm facilities design reconstitution program plan

    SciTech Connect (OSTI)

    Vollert, F.R.

    1994-09-06

    Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980`s has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan.

  12. Correlation consistent basis sets for actinides. I. The Th and U atoms

    SciTech Connect (OSTI)

    Peterson, Kirk A.

    2015-02-21

    New correlation consistent basis sets based on both pseudopotential (PP) and all-electron Douglas-Kroll-Hess (DKH) Hamiltonians have been developed from double- to quadruple-zeta quality for the actinide atoms thorium and uranium. Sets for valence electron correlation (5f6s6p6d), cc − pV nZ − PP and cc − pV nZ − DK3, as well as outer-core correlation (valence + 5s5p5d), cc − pwCV nZ − PP and cc − pwCV nZ − DK3, are reported (n = D, T, Q). The -PP sets are constructed in conjunction with small-core, 60-electron PPs, while the -DK3 sets utilized the 3rd-order Douglas-Kroll-Hess scalar relativistic Hamiltonian. Both series of basis sets show systematic convergence towards the complete basis set limit, both at the Hartree-Fock and correlated levels of theory, making them amenable to standard basis set extrapolation techniques. To assess the utility of the new basis sets, extensive coupled cluster composite thermochemistry calculations of ThF{sub n} (n = 2 − 4), ThO{sub 2}, and UF{sub n} (n = 4 − 6) have been carried out. After accurately accounting for valence and outer-core correlation, spin-orbit coupling, and even Lamb shift effects, the final 298 K atomization enthalpies of ThF{sub 4}, ThF{sub 3}, ThF{sub 2}, and ThO{sub 2} are all within their experimental uncertainties. Bond dissociation energies of ThF{sub 4} and ThF{sub 3}, as well as UF{sub 6} and UF{sub 5}, were similarly accurate. The derived enthalpies of formation for these species also showed a very satisfactory agreement with experiment, demonstrating that the new basis sets allow for the use of accurate composite schemes just as in molecular systems composed only of lighter atoms. The differences between the PP and DK3 approaches were found to increase with the change in formal oxidation state on the actinide atom, approaching 5-6 kcal/mol for the atomization enthalpies of ThF{sub 4} and ThO{sub 2}. The DKH3 atomization energy of ThO{sub 2} was calculated to be smaller than the DKH2 value by ∌1 kcal/mol.

  13. Explosiv3Design

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

    Explosiv3Design 1663 Los Alamos science and technology magazine Latest Issue:March 2016 past issues All Issues » submit Explosiv3Design 3D-printing technology is booming and could revolutionize the design of high explosives. March 8, 2016 3D printer makes cones of explosive materials A 3D printer is the ideal tool to make these cones of explosive material with finely controlled internal microstructure. Scientists are revolutionizing both the manufacturing process and the explosive materials

  14. Structural design considerations

    SciTech Connect (OSTI)

    Marshall, P.; Chang, B.

    1996-12-31

    This paper is one of seven presented at a special OTC session on international standards for the design of offshore platforms for earthquakes. Companion papers describe an overview of proposed ISO provisions, seismic exposure, foundation design, performance characteristics, a site-specific example, and probability-based LRFD. The focus of this paper is upon results of interest to structural designers, such as: simplified load and resistance factors; lifetime reliability estimates; ductility analysis using API jolts; and example North Sea application.

  15. Kinetically balanced Gaussian basis-set approach to relativistic Compton profiles of atoms

    SciTech Connect (OSTI)

    Jaiswal, Prerit; Shukla, Alok

    2007-02-15

    Atomic Compton profiles (CPs) are a very important property which provide us information about the momentum distribution of atomic electrons. Therefore, for CPs of heavy atoms, relativistic effects are expected to be important, warranting a relativistic treatment of the problem. In this paper, we present an efficient approach aimed at ab initio calculations of atomic CPs within a Dirac-Hartree-Fock (DHF) formalism, employing kinetically balanced Gaussian basis functions. The approach is used to compute the CPs of noble gases ranging from He to Rn, and the results have been compared to the experimental and other theoretical data, wherever possible. The influence of the quality of the basis set on the calculated CPs has also been systematically investigated.

  16. Hamiltonian Light-front Field Theory Within an AdS/QCD Basis

    SciTech Connect (OSTI)

    Vary, J.P.; Honkanen, H.; Li, Jun; Maris, P.; Brodsky, S.J.; Harindranath, A.; de Teramond, G.F.; Sternberg, P.; Ng, E.G.; Yang, C.; /LBL, Berkeley

    2009-12-16

    Non-perturbative Hamiltonian light-front quantum field theory presents opportunities and challenges that bridge particle physics and nuclear physics. Fundamental theories, such as Quantum Chromodynamics (QCD) and Quantum Electrodynamics (QED) offer the promise of great predictive power spanning phenomena on all scales from the microscopic to cosmic scales, but new tools that do not rely exclusively on perturbation theory are required to make connection from one scale to the next. We outline recent theoretical and computational progress to build these bridges and provide illustrative results for nuclear structure and quantum field theory. As our framework we choose light-front gauge and a basis function representation with two-dimensional harmonic oscillator basis for transverse modes that corresponds with eigensolutions of the soft-wall AdS/QCD model obtained from light-front holography.

  17. Polychromatic sparse image reconstruction and mass attenuation spectrum estimation via B-spline basis function expansion

    SciTech Connect (OSTI)

    Gu, Renliang E-mail: ald@iastate.edu; DogandĆŸić, Aleksandar E-mail: ald@iastate.edu

    2015-03-31

    We develop a sparse image reconstruction method for polychromatic computed tomography (CT) measurements under the blind scenario where the material of the inspected object and the incident energy spectrum are unknown. To obtain a parsimonious measurement model parameterization, we first rewrite the measurement equation using our mass-attenuation parameterization, which has the Laplace integral form. The unknown mass-attenuation spectrum is expanded into basis functions using a B-spline basis of order one. We develop a block coordinate-descent algorithm for constrained minimization of a penalized negative log-likelihood function, where constraints and penalty terms ensure nonnegativity of the spline coefficients and sparsity of the density map image in the wavelet domain. This algorithm alternates between a Nesterov’s proximal-gradient step for estimating the density map image and an active-set step for estimating the incident spectrum parameters. Numerical simulations demonstrate the performance of the proposed scheme.

  18. Inherently Risky Design?

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

    Inherently Risky Design? The History of Soviet Nuclear Reactors and the Notion of Safety Sonja Schmid, ... Program * Kurchatov turns to power reactors before first Soviet ...

  19. The LCLS Design Group

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

    R-593 April 2002 UC-414 Linac Coherent Light Source (LCLS) Conceptual Design Report Published April 2002 Prepared for the Department of Energy under contract number...

  20. Effective Design Strategies

    Broader source: Energy.gov [DOE]

    As described in the Whole Building Design Guide (WBDG), all Federal agencies are required to follow the Guiding Principles for New Construction and Major Renovations, which include considerations...

  1. ERHIC INTERACTION REGION DESIGN.

    SciTech Connect (OSTI)

    MONTAG,C.PARKER,B.PTITSYN,V.TEPIKIAN,S.WANG,D.WANG,F.

    2003-10-13

    This paper presents the current interaction region design status of the ring-ring version of the electron-ion collider eRHIC (release 2.0).

  2. Technical Basis for Work Place Air Monitoring for the Plutonium Finishing Plan (PFP)

    SciTech Connect (OSTI)

    JONES, R.A.

    1999-10-06

    This document establishes the basis for the Plutonium Finishing Plant's (PFP) work place air monitoring program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), Part 835 ''Occupational Radiation Protection''; Hanford Site Radiological Control Manual (HSRCM-1); HNF-PRO-33 1, Work Place Air Monitoring; WHC-SD-CP-SAR-021, Plutonium Finishing Plant Final Safety Analysis Report; and Applicable recognized national standards invoked by DOE Orders and Policies.

  3. Hydro-Kansas (HK) Research Project: Tests of a Physical Basis of

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

    Statistical Self-Similarity in Peak Flows in the Whitewater Basin, Kansas Hydro-Kansas (HK) Research Project: Tests of a Physical Basis of Statistical Self-Similarity in Peak Flows in the Whitewater Basin, Kansas Gupta, Vijay University of Colorado Furey, Peter Colorado Research Associates Mantila, Ricardo University of Colorado Krajewski, Witold University of Iowa Kruger, Anton The University of Iowa Clayton, Jordan US Geological Survey and University of Iowa Category: Atmospheric State and

  4. Integrated Safety Management System as the Basis for Work Planning and Control for Research and Development

    Broader source: Energy.gov [DOE]

    Slide Presentation by Rich Davies, Kami Lowry, Mike Schlender, Pacific Northwest National Laboratory (PNNL) and Ted Pietrok, Pacific Northwest Site Office (PNSO). Integrated Safety Management System as the Basis for Work Planning and Control for Research and Development. Work Planning and Control (WP&C) is essential to assuring the safety of workers and the public regardless of the scope of work Research and Development (R&D) activities are no exception.

  5. Tank waste remediation system retrieval and disposal mission authorization basis amendment task plan

    SciTech Connect (OSTI)

    Goetz, T.G.

    1998-01-08

    This task plan is a documented agreement between Nuclear Safety and Licensing and the Process Development group within the Waste Feed Delivery organization. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Waste Delivery Program, Project W-211, and Project W-TBD.

  6. Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1

    Broader source: Energy.gov [DOE]

    This document provides the technical basis for the Department of Energy (DOE) Policy (P) 420.1, Nuclear Safety Policy, dated 2-8-2011. It includes an analysis of the revised Policy to determine whether it provides the necessary and sufficient high-level expectations that will lead DOE to establish and implement appropriate requirements to assure protection of the public, workers, and the environment from the hazards of DOE’s operation of nuclear facilities.

  7. A probabilistic risk assessment of the LLNL Plutonium facility`s evaluation basis fire operational accident

    SciTech Connect (OSTI)

    Brumburgh, G.

    1994-08-31

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility.

  8. Safety basis for the 241-AN-107 mixer pump installation and caustic addition

    SciTech Connect (OSTI)

    Van Vleet, R.J.

    1994-10-05

    This safety Basis was prepared to determine whether or not the proposed activities of installing a 76 HP jet mixer pump and the addition of approximately 50,000 gallons of 19 M (50:50 wt %) aqueous caustic are within the safety envelope as described by Tank Farms (chapter six of WHC-SD-WM-ISB-001, Rev. 0). The safety basis covers the components, structures and systems for the caustic addition and mixer pump installation. These include: installation of the mixer pump and monitoring equipment; operation of the mixer pump, process monitoring equipment and caustic addition; the pump stand, caustic addition skid, the electrical skid, the video camera system and the two densitometers. Also covered is the removal and decontamination of the mixer pump and process monitoring system. Authority for this safety basis is WHC-IP-0842 (Waste Tank Administration). Section 15.9, Rev. 2 (Unreviewed Safety Questions) of WHC-IP-0842 requires that an evaluation be performed for all physical modifications.

  9. Central Facilities Area Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-11-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Central Facilities Area facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facilityspecific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  10. Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Not Listed

    2011-09-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  11. Research and Education Campus Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    L. Harvego; Brion Bennett

    2011-11-01

    U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory Research and Education Campus facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

  12. Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-09-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  13. Design and development for a low emission boiler system

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

    The Department of Energy initiated the Combustion 2000 program to develop the next generation of coal-fired power plants. Sargent & Lundy (S&L) is working on the Low Emission Boiler System (LEBS) portion of the program led by Riley Stoker Corporation, with support from Textron Defense Systems, Tecogen, and Reaction Engineering International. Together these organizations form {open_quotes}the Riley Team.{close_quotes} There are four phases of the LEBS development program. Currently, we are working in Phase I, which involves the design of a 400 MWe unit. Phase II through IV will involve pilot scale component testing and a Proof-of-Concept facility ({approximately}40MWe) design, construction, and operation. This document comprises the Design and Development Report for the LEBS. The report describes the design basis, design uncertainties and development plan for each of the major LEBS subsystems.

  14. Core Design Applications

    Energy Science and Technology Software Center (OSTI)

    1995-07-12

    CORD-2 is intended for core desigh applications of pressurized water reactors. The main objective was to assemble a core design system which could be used for simple calculations (such as frequently required for fuel management) as well as for accurate calculations (for example, core design after refueling).

  15. Basis for Identification of Disposal Options for R and D for...

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

    conditions on the design of the repository, the engineered barrier, and the waste. Salt, clayshale, and granitic rocks represent a reasonable cross-section of behavior....

  16. Beam director design report

    SciTech Connect (OSTI)

    Younger, F.C.

    1986-08-01

    A design and fabrication effort for a beam director is documented. The conceptual design provides for the beam to pass first through a bending and focusing system (or ''achromat''), through a second achromat, through an air-to-vacuum interface (the ''beam window''), and finally through the vernier steering system. Following an initial concept study for a beam director, a prototype permanent magnet 30/sup 0/ beam-bending achromat and prototype vernier steering magnet were designed and built. In volume II, copies are included of the funding instruments, requests for quotations, purchase orders, a complete set of as-built drawings, magnetic measurement reports, the concept design report, and the final report on the design and fabrication project. (LEW)

  17. Lighting Design | Department of Energy

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

    Design Lighting Design Energy-efficient indoor and outdoor lighting design focuses on ways to improve both the quality and efficiency of lighting. | Photo courtesy of ...

  18. Lighting Design | Department of Energy

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

    as part of your whole-house design -- an approach for building an energy-efficient home. Indoor Lighting Design When designing indoor lighting for energy efficiency,...

  19. Race to Zero Design Competition Webinar: Housing Design Best...

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

    Race to Zero Design Competition Webinar: Housing Design Best Practices Race to Zero Design Competition Webinar: Housing Design Best Practices November 18, 2014 1:00PM to 2:30PM EST ...

  20. Design criteria for a self-actuated shutdown system to ensure limitation of core damage. [LMFBR

    SciTech Connect (OSTI)

    Deane, N.A.; Atcheson, D.B.

    1981-09-01

    Safety-based functional requirements and design criteria for a self-actuated shutdown system (SASS) are derived in accordance with LOA-2 success criteria and reliability goals. The design basis transients have been defined and evaluated for the CDS Phase II design, which is a 2550 MWt mixed oxide heterogeneous core reactor. A partial set of reactor responses for selected transients is provided as a function of SASS characteristics such as reactivity worth, trip points, and insertion times.

  1. Improving Design Methods for Fixed-Foundation Offshore Wind Energy Systems

    Broader source: Energy.gov [DOE]

    The design basis for an offshore wind farm establishes the conditions, needs, and requirements to be taken into account in designing the facility. To address design knowledge gaps and facilitate safe deployment of U.S. offshore wind projects in areas along the U.S. Atlantic Coast, DOE is funding research by a team consisting of DOE's Savannah River National Laboratory, Coastal Carolina University, MMI Engineering, and DOE's National Renewable Energy Laboratory.

  2. WASTE PACKAGE TRANSPORTER DESIGN

    SciTech Connect (OSTI)

    D.C. Weddle; R. Novotny; J. Cron

    1998-09-23

    The purpose of this Design Analysis is to develop preliminary design of the waste package transporter used for waste package (WP) transport and related functions in the subsurface repository. This analysis refines the conceptual design that was started in Phase I of the Viability Assessment. This analysis supports the development of a reliable emplacement concept and a retrieval concept for license application design. The scope of this analysis includes the following activities: (1) Assess features of the transporter design and evaluate alternative design solutions for mechanical components. (2) Develop mechanical equipment details for the transporter. (3) Prepare a preliminary structural evaluation for the transporter. (4) Identify and recommend the equipment design for waste package transport and related functions. (5) Investigate transport equipment interface tolerances. This analysis supports the development of the waste package transporter for the transport, emplacement, and retrieval of packaged radioactive waste forms in the subsurface repository. Once the waste containers are closed and accepted, the packaged radioactive waste forms are termed waste packages (WP). This terminology was finalized as this analysis neared completion; therefore, the term disposal container is used in several references (i.e., the System Description Document (SDD)) (Ref. 5.6). In this analysis and the applicable reference documents, the term ''disposal container'' is synonymous with ''waste package''.

  3. Proposals and Design Reports

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

    Proposals and Design Reports Proposals and Design Reports Proposal (1/2/04) Proposal Addendum (29/3/04) Physics Case and Detector Technology Report (12/04) Technical Design Report (7/06) Reviews DOE CD-4 DOE 2008 DOE CD-3b CD-3b Readiness DOE CD-1/2/3a CD-2/3a Readiness CD-1 Readiness PAC Report (4/05) Approvals FNAL PAC Approval: April 15, 2004 DOE Critical Decision 1,2,3a (Performance Baseline, Construction Start) Approval: March 30, 2007 DOE Critical Decision 4 (Project Completion) Approval:

  4. Policies for green design

    SciTech Connect (OSTI)

    Fullerton, D.; Wu, W.

    1998-09-01

    A simple general equilibrium model is used to analyze disposal-content fees, subsidies for recyclable designs, unit-pricing of household disposal, deposit-refund systems, and manufacturer take-back requirements. Firms use primary and recycled inputs to produce output that has two attributes: packaging per unit output, and recyclability. If households pay the social cost of disposal, then they send the right signals to producers to reduce packaging and to design products that can more easily be recycled. If garbage is collected for free, then socially optimum attributes can still be achieved by a tax on producers` use of packaging and subsidy to recyclable designs.

  5. Rampressor Turbine Design

    SciTech Connect (OSTI)

    Ramgen Power Systems

    2003-09-30

    The design of a unique gas turbine engine is presented. The first Rampressor Turbine engine rig will be a configuration where the Rampressor rotor is integrated into an existing industrial gas turbine engine. The Rampressor rotor compresses air which is burned in a traditional stationary combustion system in order to increase the enthalpy of the compressed air. The combustion products are then expanded through a conventional gas turbine which provides both compressor and electrical power. This in turn produces shaft torque, which drives a generator to provide electricity. The design and the associated design process of such an engine are discussed in this report.

  6. Novel rocket design flight tested

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

    Novel rocket design flight tested Novel rocket design flight tested Scientists recently flight tested a new rocket design that includes a high-energy fuel and a motor design that...

  7. The NOvA Technical Design Report

    SciTech Connect (OSTI)

    Ayres, D.S.; Drake, G.R.; Goodman, M.C.; Grudzinski, J.J.; Guarino, V.J.; Talaga, R.L.; Zhao, A.; Stamoulis, P.; Stiliaris, E.; Tzanakos, G.; Zois, M.; /Athens U. /Caltech /UCLA /Fermilab /College de France /Harvard U. /Indiana U. /Lebedev Inst. /Michigan State U. /Minnesota U., Duluth /Minnesota U.

    2007-10-08

    Technical Design Report (TDR) describes the preliminary design of the NOvA accelerator upgrades, NOvA detectors, detector halls and detector sites. Compared to the March 2006 and November 2006 NOvA Conceptual Design Reports (CDR), critical value engineering studies have been completed and the alternatives still active in the CDR have been narrowed to achieve a preliminary technical design ready for a Critical Decision 2 review. Many aspects of NOvA described this TDR are complete to a level far beyond a preliminary design. In particular, the access road to the NOvA Far Detector site in Minnesota has an advanced technical design at a level appropriate for a Critical Decision 3a review. Several components of the accelerator upgrade and new neutrino detectors also have advanced technical designs appropriate for a Critical Decision 3a review. Chapter 1 is an Executive Summary with a short description of the NOvA project. Chapter 2 describes how the Fermilab NuMI beam will provide a narrow band beam of neutrinos for NOvA. Chapter 3 gives an updated overview of the scientific basis for the NOvA experiment, focusing on the primary goal to extend the search for {nu}{sub {mu}} {yields} {nu}{sub e} oscillations and measure the sin{sup 2}(2{theta}{sub 13}) parameter. This parameter has not been measured in any previous experiment and NOvA would extend the search by about an order of magnitude beyond the current limit. A secondary goal is to measure the dominant mode oscillation parameters, sin{sup 2}(2{theta}{sub 23}) and {Delta}m{sub 32}{sup 2} to a more precise level than previous experiments. Additional physics goals for NOvA are also discussed. Chapter 4 describes the Scientific Design Criteria which the Fermilab accelerator complex, NOvA detectors and NOvA detector sites must satisfy to meet the physics goals discussed in Chapter 3. Chapter 5 is an overview of the NOvA project. The changes in the design relative to the NOvA CDR are discussed. Chapter 6 summarizes the NOvA design performance relative to the Design Criteria set out in Chapter 4. Chapter 7 presents the Work Breakdown Structure dictionary at Level 3 and the Milestone dictionary. Chapters 8 through 17 then take each Level 2 WBS element of the NOvA project and present each part of the design in more detail than the overview given in Chapter 5. Specific technical design criteria are delineated for each part of the project in addition to the scientific design criteria outlined in Chapter 4. Changes in the design since the NOvA CDR are discussed in detail. The work remaining to bring each part of this preliminary design to a final design is outlined. Appendix A is a guide to other NOvA Project documentation with links to those documents.

  8. Just in Time DSA-The Hanford Nuclear Safety Basis Strategy

    SciTech Connect (OSTI)

    Olinger, S. J.; Buhl, A. R.

    2002-02-26

    The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safety Basis Requirements (the Rule) in January 2001 imposed the requirement that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSA that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: compliance with the Rule; a ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD&D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD&D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex.

  9. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    SciTech Connect (OSTI)

    Petersen, C.A., Westinghouse Hanford

    1996-07-17

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  10. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    SciTech Connect (OSTI)

    Petersen, C.A.

    1996-09-20

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  11. Technical basis for cases N-629 and N-631 as an alternative for RTNDT reference temperature

    SciTech Connect (OSTI)

    Merkle, John Graham; Server, W. L.

    2007-01-01

    ASME Code Cases N-629/N-631, published in 1999, provided an important new approach to allow material specific, measured fracture toughness curves for ferritic steels in the code applications. This has enabled some of the nuclear power plants whose reactor pressure vessel materials reached a certain threshold level based on overly conservative rules to use an alternative RTNDT to justify continued operation of their plants. These code cases have been approved by the US Nuclear Regulatory Commission and these have been proposed to be codified in Appendix A and Appendix G of the ASME Boiler and Pressure Vessel Code. This paper summarizes the basis of this approach for the record.

  12. Structural Basis of Pre-existing Immunity to the 2009 H1N1 Pandemic

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

    Influenza Virus Structural Basis of Pre-existing Immunity to the 2009 H1N1 Pandemic Influenza Virus The emergence of the 2009 H1N1 influenza pandemic, also known as the "swine flu", marks the first human flu pandemic in 40 years and has caused significant human infection and mortality globally (1). The emergence of the 2009 H1N1 flu marks the first time that an influenza pandemic was triggered by a virus carrying the same hemagglutinin (HA) subtype as circulating seasonal strains.

  13. Subsea HIPPS design procedure

    SciTech Connect (OSTI)

    Aaroe, R.; Lund, B.F.; Onshus, T.

    1995-12-31

    The paper is based on a feasibility study investigating the possibilities of using a HIPPS (High Integrity Pressure Protection System) to protect a subsea pipeline that is not rated for full wellhead shut-in pressure. The study was called the Subsea OPPS Feasibility Study, and was performed by SINTEF, Norway. Here, OPPS is an acronym for Overpressure Pipeline Protection System. A design procedure for a subsea HIPPS is described, based on the experience and knowledge gained through the ``Subsea OPPS Feasibility Study``. Before a subsea HIPPS can be applied, its technical feasibility, reliability and profitability must be demonstrated. The subsea HIPPS design procedure will help to organize and plan the design activities both with respect to development and verification of a subsea HIPPS. The paper also gives examples of how some of the discussed design steps were performed in the Subsea OPPS Feasibility Study. Finally, further work required to apply a subsea HIPPS is discussed.

  14. Conceptual Design RM

    Broader source: Energy.gov [DOE]

    This Review Module is a tool that assists Department of Energy (DOE) federal project review teams in evaluating the adequacy of the conceptual design package prior to CD-1 approval. It focuses on...

  15. DesignForward

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

    National Laboratory | National Nuclear Security Administration Design-Build Contract Awarded for Electrical Substation at Los Alamos National Laboratory April 27, 2016 LOS ALAMOS, NM - Under an interagency agreement with the Department of Energy's National Nuclear Security Administration (DOE/NNSA), the U.S. Army Corps of Engineers (USACE) has awarded a design-build contract at Los Alamos National Laboratory (LANL) to Gardner Zemke Mechanical and Electrical Contractors of Albuquerque. Under

  16. Wind Turbine Blade Design

    K-12 Energy Lesson Plans and Activities Web site (EERE)

    Blade engineering and design is one of the most complicated and important aspects of modern wind turbine technology. Engineers strive to design blades that extract as much energy from the wind as possible throughout a range of wind speeds and gusts, yet are still durable, quiet and cheap. A variety of ideas for building turbines and teacher handouts are included in this document and at the Web site.

  17. Structural Design Feasibility Study for the Global Climate Experiment

    SciTech Connect (OSTI)

    Lewin,K.F.; Nagy, J.

    2008-12-01

    Neon, Inc. is proposing to establish a Global Change Experiment (GCE) Facility to increase our understanding of how ecological systems differ in their vulnerability to changes in climate and other relevant global change drivers, as well as provide the mechanistic basis for forecasting ecological change in the future. The experimental design was initially envisioned to consist of two complementary components; (A) a multi-factor experiment manipulating CO{sub 2}, temperature and water availability and (B) a water balance experiment. As the design analysis and cost estimates progressed, it became clear that (1) the technical difficulties of obtaining tight temperature control and maintaining elevated atmospheric carbon dioxide levels within an enclosure were greater than had been expected and (2) the envisioned study would not fit into the expected budget envelope if this was done in a partially or completely enclosed structure. After discussions between NEON management, the GCE science team, and Keith Lewin, NEON, Inc. requested Keith Lewin to expand the scope of this design study to include open-field exposure systems. In order to develop the GCE design to the point where it can be presented within a proposal for funding, a feasibility study of climate manipulation structures must be conducted to determine design approaches and rough cost estimates, and to identify advantages and disadvantages of these approaches including the associated experimental artifacts. NEON, Inc requested this design study in order to develop concepts for the climate manipulation structures to support the NEON Global Climate Experiment. This study summarizes the design concepts considered for constructing and operating the GCE Facility and their associated construction, maintenance and operations costs. Comparisons and comments about experimental artifacts, construction challenges and operational uncertainties are provided to assist in selecting the final facility design. The overall goal of this report is to provide a cost and technological basis for selection of the appropriate GCE Facility design.

  18. Design documentation: Krypton encapsulation preconceptual design

    SciTech Connect (OSTI)

    Knecht, D.A.

    1994-10-01

    US EPA regulations limit the release of Krypton-85 to the environment from commercial facilities after January 1, 1983. In order to comply with these regulations, Krypton-85, which would be released during reprocessing of commercial nuclear fuel, must be collected and stored. Technology currently exists for separation of krypton from other inert gases, and for its storage as a compressed gas in steel cylinders. The requirements, which would be imposed for 100-year storage of Krypton-85, have led to development of processes for encapsulation of krypton within a stable solid matrix. The objective of this effort was to provide preconceptual engineering designs, technical evaluations, and life cycle costing data for comparison of two alternate candidate processes for encapsulation of Krypton-85. This report has been prepared by The Ralph M. Parsons Company for the US Department of Energy.

  19. The Mechanical Design Optimization of a High Field HTS Solenoid

    SciTech Connect (OSTI)

    Lalitha, SL; Gupta, RC

    2015-06-01

    This paper describes the conceptual design optimization of a large aperture, high field (24 T at 4 K) solenoid for a 1.7 MJ superconducting magnetic energy storage device. The magnet is designed to be built entirely of second generation (2G) high temperature superconductor tape with excellent electrical and mechanical properties at the cryogenic temperatures. The critical parameters that govern the magnet performance are examined in detail through a multiphysics approach using ANSYS software. The analysis results formed the basis for the performance specification as well as the construction of the magnet.

  20. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 2, Technical basis

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume, Volume 2, contains the technical basis for the 1992 PA. Specifically, it describes the conceptual basis for consequence modeling and the PA methodology, including the selection of scenarios for analysis, the determination of scenario probabilities, and the estimation of scenario consequences using a Monte Carlo technique and a linked system of computational models. Additional information about the 1992 PA is provided in other volumes. Volume I contains an overview of WIPP PA and results of a preliminary comparison with the long-term requirements of the EPA`s Environmental Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses related to the preliminary comparison with 40 CFR 191B. Volume 5 contains uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance. Finally, guidance derived from the entire 1992 PA is presented in Volume 6.

  1. YOUR DESIGN PROBABLY NEEDS MORE VDUs

    SciTech Connect (OSTI)

    OHARA, J.; BROWN, W.; LEWIS, P.; PERSENSKY, J.

    2001-10-08

    The most frequent complaint of operators in modern computer-based control rooms is that there just are not enough video display units (VDUs). In this paper we examine the basis for this concern and try to understand the technical and historical reasons for this complaint, and its implications for the design of complex human-machine systems, including the number of VDUs in the control room. The overall aim of our work is to develop human factors guidance for the review of computer-based and modernized control rooms in nuclear power plants. As part of these efforts we have conducted literature reviews and studies using both simulators and actual systems in a broad range of industries, including process control, aerospace, medical, and others. Our findings reflect the general complaint of operators across all these industries: there just are not enough VDUs in the control room. We conclude that there are three primary reasons for this complaint. First, as part of a workload management strategy, operators frequently avoid interface management tasks and do not access all the information available, preferring instead to use a fixed set of familiar displays that provide much (but not all) of the information needed. Performance thereby becomes data limited and operators complain that they do not have a sufficient number of VDUs to set up in the early phases of a high-workload period so they can get all the information they need. Second, display designs are typically not designed with operator tasks in mind. The most common method of representing information is by functions and systems. Since tasks typically cut across many systems, operators need many displays. Thus, to make task performance easier operators need additional VDUs. Finally, there is a differing ''concept of operations'' between designers and operators. Modern computer-based control rooms are designed with vast amounts of data, available through hundreds of displays, viewed by the operator through a limited number of display devices. Designers expect that operators will use the flexibility of the computer-based interfaces to configure them in such a way that they are ideally tailored to the unique demands of the current situation. However, operators usually do not do that and instead configure the interfaces in a spatially dedicated way. Thus, while the number of VDUs may seem reasonable to the designer, it is not to the operator who is attempting to minimize the interface management aspects of workload. The implications of these findings for design are discussed in terms of the need for a method for determining the number of displays, task-relevant displays, data-dense displays, and enhanced interface management design and training.

  2. Advanced solar panel designs

    SciTech Connect (OSTI)

    Ralph, E.L.; Linder, E.

    1995-10-01

    This paper describes solar cell panel designs that utilize new high efficiency solar cells along with lightweight rigid panel technology. The resulting designs push the W/kg and W/sq m parameters to new high levels. These new designs are well suited to meet the demand for higher performance small satellites. This paper reports on progress made on two SBIR Phase 1 contracts. One panel design involved the use of large area (5.5 cm x 6.5 cm) GaAs/Ge solar cells of 19% efficiency combined with a lightweight rigid graphite fiber epoxy isogrid substrate configuration. A coupon (38 cm x 38 cm) was fabricated and tested which demonstrated an array specific power level of 60 W/kg with a potential of reaching 80 W/kg. The second panel design involved the use of newly developed high efficiency (22%) dual junction GaInP2/GaAs/Ge solar cells combined with an advanced lightweight rigid substrate using aluminum honeycomb core with high strength graphite fiber mesh facesheets. A coupon (38 cm x 38 cm) was fabricated and tested which demonstrated an array specific power of 105 W/kg and 230 W/sq m. This paper will address the construction details of the panels and an analysis of the component weights. A strawman array design suitable for a typical small-sat mission is described for each of the two panel design technologies being studied. Benefits in respect to weight reduction, area reduction, and system cost reduction are analyzed and compared to conventional arrays.

  3. Silo Storage Preconceptual Design

    SciTech Connect (OSTI)

    Stephanie L. Austad; Patrick W. Bragassa; Kevin M Croft; David S Ferguson; Scott C Gladson; Annette L Shafer; John H Weathersby

    2012-09-01

    The National Nuclear Security Administration (NNSA) has a need to develop and field a low-cost option for the long-term storage of a variety of radiological material. The storage option’s primary requirement is to provide both environmental and physical protection of the materials. Design criteria for this effort require a low initial cost and minimum maintenance over a 50-year design life. In 1999, Argonne National Laboratory-West was tasked with developing a dry silo storage option for the BN-350 Spent Fuel in Aktau Kazakhstan. Argon’s design consisted of a carbon steel cylinder approximately 16 ft long, 18 in. outside diameter and 0.375 in. wall thickness. The carbon steel silo was protected from corrosion by a duplex coating system consisting of zinc and epoxy. Although the study indicated that the duplex coating design would provide a design life well in excess of the required 50 years, the review board was concerned because of the novelty of the design and the lack of historical use. In 2012, NNSA tasked Idaho National Laboratory (INL) with reinvestigating the silo storage concept and development of alternative corrosion protection strategies. The 2012 study, “Silo Storage Concepts, Cathodic Protection Options Study” (INL/EST-12-26627), concludes that the option which best fits the design criterion is a passive cathotic protection scheme, consisting of a carbon steel tube coated with zinc or a zinc-aluminum alloy encapsulated in either concrete or a cement grout. The hot dipped zinc coating option was considered most efficient, but the flame-sprayed option could be used if a thicker zinc coating was determined to be necessary.

  4. Design requirements document for Project W-465, immobilized low-activity waste interim storage

    SciTech Connect (OSTI)

    Burbank, D.A.

    1998-05-19

    The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project.

  5. 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

    Broader source: Energy.gov [DOE]

    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.

  6. New Concepts in Fish Ladder Design, Volume III of IV, Assessment of Fishway Development and Design, 1982-1983 Final Report.

    SciTech Connect (OSTI)

    Powers, Patrick D.; Orsborn, John F.

    1985-08-01

    This volume covers the broad, though relatively short, historical basis for this project. The historical developments of certain design features, criteria and research activities are traced. Current design practices are summarized based on the results of an international survey and interviews with agency personnel and consultants. The fluid mechanics and hydraulics of fishway systems are discussed. Fishways (or fishpasses) can be classified in two ways: (1) on the basis of the method of water control (chutes, steps (ladders), or slots); and (2) on the basis of the degree and type of water control. This degree of control ranges from a natural waterfall to a totally artificial environment at a hatchery. Systematic procedures for analyzing fishways based on their configuration, species, and hydraulics are presented. Discussions of fish capabilities, energy expenditure, attraction flow, stress and other factors are included.

  7. Design considerations for heavy oil in situ pilots

    SciTech Connect (OSTI)

    Peachey, B.R.; Nodwell, J.A.

    1982-01-01

    Although the primary objectives of heavy oil in situ pilots are reservoir oriented in terms of production rate and recovery efficiency, considerable development of surface engineering technology is a necessary aspect of pilot operations. Esso's basic design philosophy is to use state-of-the-art technology with onsite operator interaction to sequentially develop improvements in surface equipment and processes without comprising reservoir based research objectives. This work reviews Esso's operating experience and technical developments in pilot design at Cold Lake, Alta. The considerations which led to the design basis for the Cold Lake commercial project are examined in the areas of well layout, steam and production distribution system design, oil and water separation, and produced water treatment.

  8. Integrated survey and design for transmission lines

    SciTech Connect (OSTI)

    Miller, M.A.; Simpson, K.D.

    1994-12-31

    Gathering and compiling information on the features and uses of the land within a proposed corridor provides the basis for selecting a route, obtaining easements, and designing and constructing a transmission line. Traditionally, gathering this information involved searches of existing maps and records to obtain the available information, which would then be supplemented with aerial photography to record current conditions. Ground surveys were performed to collect topographic data for design purposes. This information was manually transferred to drawings and other documents to show the terrain, environmentally sensitive areas, property ownership, and existing facilities. These drawing served as the base to which the transmission line right-of-way, structures, and other design information were added. As the design was completed, these drawings became the source of information for constructing the line and ultimately, the record of the facility. New technologies and the every growing need for instantly accessible information have resulted in changes in almost every step of gathering, storing and using information. Electronic data collection, global positioning systems (GPS), digitized terrain models, computerized design techniques, development of drawings using CAD, and graphical information systems (GIS) have individually resulted in significant advancements in this process. Combining these components into an integrated system, however, is truly revolutionizing transmission line engineering. This paper gives an overview of the survey and mapping information that is required for transmission line projects, review the traditional techniques that have been employed to obtain and utilize this information, and discuss the recent advances in the technology. Additionally, a system is presented that integrates the components in this process to achieve efficiency, minimize chances of errors, and provide improved access to project information.

  9. LBB considerations for a new plant design

    SciTech Connect (OSTI)

    Swamy, S.A.; Mandava, P.R.; Bhowmick, D.C.; Prager, D.E.

    1997-04-01

    The leak-before-break (LBB) methodology is accepted as a technically justifiable approach for eliminating postulation of Double-Ended Guillotine Breaks (DEGB) in high energy piping systems. This is the result of extensive research, development, and rigorous evaluations by the NRC and the commercial nuclear power industry since the early 1970s. The DEGB postulation is responsible for the many hundreds of pipe whip restraints and jet shields found in commercial nuclear plants. These restraints and jet shields not only cost many millions of dollars, but also cause plant congestion leading to reduced reliability in inservice inspection and increased man-rem exposure. While use of leak-before-break technology saved hundreds of millions of dollars in backfit costs to many operating Westinghouse plants, value-impacts resulting from the application of this technology for future plants are greater on a per plant basis. These benefits will be highlighted in this paper. The LBB technology has been applied extensively to high energy piping systems in operating plants. However, there are differences between the application of LBB technology to an operating plant and to a new plant design. In this paper an approach is proposed which is suitable for application of LBB to a new plant design such as the Westinghouse AP600. The approach is based on generating Bounding Analyses Curves (BAC) for the candidate piping systems. The general methodology and criteria used for developing the BACs are based on modified GDC-4 and Standard Review Plan (SRP) 3.6.3. The BAC allows advance evaluation of the piping system from the LBB standpoint thereby assuring LBB conformance for the piping system. The piping designer can use the results of the BACs to determine acceptability of design loads and make modifications (in terms of piping layout and support configurations) as necessary at the design stage to assure LBB for the, piping systems under consideration.

  10. Designing tomorrow's warheads -- today

    SciTech Connect (OSTI)

    Schneider, D.P.

    1988-03-15

    Until recently, new weapons' warheads were most often an incremental improvement on a previous warhead design. The tools available to the munition designer today, however, allow for a more comprehensive methodology to be employed. The focus of this paper will be a portion of the process of design of an explosively formed projectile (EFP) which uses tantalum as its liner material. Several questions surrounding tantalum's behavior under high strains require answers before such an EFP can be properly designed. The base-technology issues of different material properties will be explored using a three-dimensional finite element code (DYNA3D) and then compared to experiments. State-of-the-art diagnostics are an integral part of this methodology. Predetermined ''flasher block'' contours will provide specific position/time data which will assist in improving and understanding the high explosive equation of state as well as determining the energy imparted to the liner. In turn, this will lead to improved modeling of the liner as it translates along the line of flight. Flash X-ray Radiograph (FXR) will provide clues to axial symmetry, density, and overall time/distance information. This data will also provide answers to the strain rate depencence of the tantalum. Integration of the data from the experiment with the material response models allows post-experiment normalization of the code. This ''normalized'' tool is, finally used in the point design of the warhead.

  11. Water Cooled Mirror Design

    SciTech Connect (OSTI)

    Dale, Gregory E.; Holloway, Michael Andrew; Pulliam, Elias Noel

    2015-03-30

    This design is intended to replace the current mirror setup being used for the NorthStar Moly 99 project in order to monitor the target coupon. The existing setup has limited movement for camera alignment and is difficult to align properly. This proposed conceptual design for a water cooled mirror will allow for greater thermal transfer between the mirror and the water block. It will also improve positioning of the mirror by using flexible vacuum hosing and a ball head joint capable of a wide range of motion. Incorporating this design into the target monitoring system will provide more efficient cooling of the mirror which will improve the amount of diffraction caused by the heating of the mirror. The process of aligning the mirror for accurate position will be greatly improved by increasing the range of motion by offering six degrees of freedom.

  12. OOTW Force Design Tools

    SciTech Connect (OSTI)

    Bell, R.E.; Hartley, D.S.III; Packard, S.L.

    1999-05-01

    This report documents refined requirements for tools to aid the process of force design in Operations Other Than War (OOTWs). It recommends actions for the creation of one tool and work on other tools relating to mission planning. It also identifies the governmental agencies and commands with interests in each tool, from whom should come the user advisory groups overseeing the respective tool development activities. The understanding of OOTWs and their analytical support requirements has matured to the point where action can be taken in three areas: force design, collaborative analysis, and impact analysis. While the nature of the action and the length of time before complete results can be expected depends on the area, in each case the action should begin immediately. Force design for OOTWs is not a technically difficult process. Like force design for combat operations, it is a process of matching the capabilities of forces against the specified and implied tasks of the operation, considering the constraints of logistics, transport and force availabilities. However, there is a critical difference that restricts the usefulness of combat force design tools for OOTWs: the combat tools are built to infer non-combat capability requirements from combat capability requirements and cannot reverse the direction of the inference, as is required for OOTWs. Recently, OOTWs have played a larger role in force assessment, system effectiveness and tradeoff analysis, and concept and doctrine development and analysis. In the first Quadrennial Defense Review (QDR), each of the Services created its own OOTW force design tool. Unfortunately, the tools address different parts of the problem and do not coordinate the use of competing capabilities. These tools satisfied the immediate requirements of the QDR, but do not provide a long-term cost-effective solution.

  13. Fire protection design criteria

    SciTech Connect (OSTI)

    1997-03-01

    This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, national Fire Protection Association Codes and Standards, and any other applicable DOE construction criteria. This Standard, along with other delineated criteria, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities.

  14. Remote Systems Design & Deployment

    SciTech Connect (OSTI)

    Bailey, Sharon A.; Baker, Carl P.; Valdez, Patrick LJ

    2009-08-28

    The Pacific Northwest National Laboratory (PNNL) was tasked by Washington River Protection Solutions, LLC (WRPS) to provide information and lessons learned relating to the design, development and deployment of remote systems, particularly remote arm/manipulator systems. This report reflects PNNL’s experience with remote systems and lays out the most important activities that need to be completed to successfully design, build, deploy and operate remote systems in radioactive and chemically contaminated environments. It also contains lessons learned from PNNL’s work experiences, and the work of others in the national laboratory complex.

  15. U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)

    Broader source: Energy.gov [DOE]

    "This self-study guide provides an overview of safety basis terminology, requirements, and activities that are applicable to DOE and Oak Ridge Operations Office (ORO) nuclear facilities on the Oak...

  16. Molten carbonate fuel cell product design improvement

    SciTech Connect (OSTI)

    P. Voyentzie; T. Leo; A. Kush; L. Christner; G. Carlson; C. Yuh

    1998-12-20

    Drawing on the manufacture, field test, and post-test experience of the sixteen Santa Clara Demonstration Project (SCDP) stacks, ERC is finalizing the next generation commercial entry product design. The second generation cells are 50% larger in area, 40% lighter on equal geometric area basis, and 30% thinner than the earlier design. These improvements have resulted in doubling of the full-height stack power. A low-cost and high-strength matrix has also been developed for improving product ruggedness. The low-cost advanced cell design incorporating these improvements has been refined through six short stack tests. Power production per cell of two times the SCDP maximum power operation, over ten thermal cycles, and overall operating flexibility with respect to load and thermal changes have been demonstrated in these short stack tests. An internally insulated stack enclosure has been designed and fabricated to eliminate the need for an inert gas environment during operation. ERC has acquired the capability for testing 400kW full-height direct fuel ceil (DFC) stack and balance-of-plant equipment. With the readiness of the power plant test facility, the cell package design, and the stack module, full-height stack testing has begun. The first full- height stack incorporating the post-SCDP second generation design was completed. The stack reached a power level of 253 kW, setting a world record for the highest power production from the advanced fuel cell system. Excellent performance uniformity at this power level affirmed manufacturing reproducibility of the components at the factory. This unoptimized small size test has achieved pipeline natural gas to DC electricity conversion efficiency of 47% (based on lower heating value - LHV) including the parasitic power consumed by the BOP equipment; that should translate to more than 50% efficiency in commercial operation, before employing cogeneration. The power plant system also operated smoothly. With the success of this test confirming the full-height stack basic design and with the completion of SCDP stacks post-test feedback, manufacture of the full-height stack representing the commercial prototype design has been completed and system demonstration is planned to start in the first quarter of 1999. These developments as well as manufacturing advances are discussed in this report.

  17. Structural basis of GDP release and gating in G protein coupled Fe[superscript 2+] transport

    SciTech Connect (OSTI)

    Guilfoyle, Amy; Maher, Megan J.; Rapp, Mikaela; Clarke, Ronald; Harrop, Stephen; Jormakka, Mika

    2009-09-29

    G proteins are key molecular switches in the regulation of membrane protein function and signal transduction. The prokaryotic membrane protein FeoB is involved in G protein coupled Fe{sup 2+} transport, and is unique in that the G protein is directly tethered to the membrane domain. Here, we report the structure of the soluble domain of FeoB, including the G protein domain, and its assembly into an unexpected trimer. Comparisons between nucleotide free and liganded structures reveal the closed and open state of a central cytoplasmic pore, respectively. In addition, these data provide the first observation of a conformational switch in the nucleotide-binding G5 motif, defining the structural basis for GDP release. From these results, structural parallels are drawn to eukaryotic G protein coupled membrane processes.

  18. Scientific basis for risk assessment and management of uranium mill tailings

    SciTech Connect (OSTI)

    Not Available

    1986-01-01

    A National Research Council study panel, convened by the Board on Radioactive Waste Management, has examined the scientific basis for risk assessment and management of uranium mill tailings and issued this final report containing a number of recommendations. Chapter 1 provides a brief introduction to the problem. Chapter 2 examines the processes of uranium extraction and the mechanisms by which radionuclides and toxic chemicals contained in the ore can enter the environment. Chapter 3 is devoted to a review of the evidence on health risks associated with radon and its decay products. Chapter 4 provides a consideration of conventional and possible new technical alternatives for tailings management. Chapter 5 explores a number of issues of comparative risk, provides a brief history of uranium mill tailings regulation, and concludes with a discussion of choices that must be made in mill tailing risk management. 211 refs., 30 figs., 27 tabs.

  19. Micrometer-scale fabrication of complex three dimensional lattice + basis structures in silicon

    SciTech Connect (OSTI)

    Burckel, D. Bruce; Resnick, Paul J.; Finnegan, Patrick S.; Sinclair, Michael B.; Davids, Paul S.

    2015-01-01

    A complementary metal oxide semiconductor (CMOS) compatible version of membrane projection lithography (MPL) for fabrication of micrometer-scale three-dimensional structures is presented. The approach uses all inorganic materials and standard CMOS processing equipment. In a single layer, MPL is capable of creating all 5 2D-Bravais lattices. Furthermore, standard semiconductor processing steps can be used in a layer-by-layer approach to create fully three dimensional structures with any of the 14 3D-Bravais lattices. The unit cell basis is determined by the projection of the membrane pattern, with many degrees of freedom for defining functional inclusions. Here we demonstrate several unique structural motifs, and characterize 2D arrays of unit cells with split ring resonators in a silicon matrix. The structures exhibit strong polarization dependent resonances and, for properly oriented split ring resonators (SRRs), coupling to the magnetic field of a normally incident transverse electromagnetic wave, a response unique to 3D inclusions.

  20. Good, Better, Best: Designing a Designation Program for Solar | Department

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

    of Energy Good, Better, Best: Designing a Designation Program for Solar Good, Better, Best: Designing a Designation Program for Solar December 4, 2012 - 4:00pm Addthis The Energy Department is gathering input on solar designation programs that could one day help consumers recognize the best products and services that the solar industry has to offer. | Photo by Dennis Schroeder/NREL. The Energy Department is gathering input on solar designation programs that could one day help consumers

  1. Designing a Benchmarking Plan

    Broader source: Energy.gov [DOE]

    U.S. Department of Energy Office of Energy Efficiency and Renewable Energy (EERE) Weatherization and Intergovernmental Program (WIP) Solution Center document about how state and local governments, Indian tribes, and overseas U.S. territories can design a plan to benchmark the energy consumption in public buildings.

  2. Microresonator electrode design

    DOE Patents [OSTI]

    Olsson, III, Roy H.; Wojciechowski, Kenneth; Branch, Darren W.

    2016-05-10

    A microresonator with an input electrode and an output electrode patterned thereon is described. The input electrode includes a series of stubs that are configured to isolate acoustic waves, such that the waves are not reflected into the microresonator. Such design results in reduction of spurious modes corresponding to the microresonator.

  3. Tool and Fixture Design

    SciTech Connect (OSTI)

    Graham, Mark W.

    2015-07-28

    In a manufacturing process, a need is identified and a product is created to fill this need. While design and engineering of the final product is important, the tools and fixtures that aid in the creation of the final product are just as important, if not more so. Power supplies assembled at the TA-55 PF-5 have been designed by an excellent engineering team. The task in PF-5 now is to ensure that all steps of the assembly and manufacturing process can be completed safely, reliably, and in a quality repeatable manner. One of these process steps involves soldering fine wires to an electrical connector. During the process development phase, the method of soldering included placing the power supply in a vice in order to manipulate it into a position conducive to soldering. This method is unacceptable from a reliability, repeatability, and ergonomic standpoint. To combat these issues, a fixture was designed to replace the current method. To do so, a twelve step engineering design process was used to create the fixture that would provide a solution to a multitude of problems, and increase the safety and efficiency of production.

  4. Wood energy system design

    SciTech Connect (OSTI)

    Not Available

    1988-01-01

    This handbook, Wood Energy System Design, was prepared with the support of the Council of Great Lakes Governors and the US Department of Energy. It contains: wood fuel properties; procurement; receiving, handling, and storage; combustion; gasification; emission control; electric power generation and cogeneration; and case studies. (JF)

  5. Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-11-01

    U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Advanced Test Reactor Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. U.S. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

  6. AUDIT REPORT Follow-up on Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National

    Energy Savers [EERE]

    Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National Laboratory DOE/IG-0941 July 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 July 16, 2015 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report: "Follow-up on Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National Laboratory" BACKGROUND A primary

  7. Engineering Basis Document Review for Waste Feed Delivery from Single Shell Tanks (SST)

    SciTech Connect (OSTI)

    SMITH, D.F.

    1999-10-07

    This report provides the results of a review conducted on existing operating specifications and safety requirements and provides a summary of applicable design constraints on the Single-Shell Tank (SST) System. The SST System is required to transition from the current waste storage mission to support the Tank Waste Remediation System (TWRS) waste retrieval mission described in the Tank Waste Remediation System Mission Analysis Report (Acree 1998). The SST System is also required to support the Project Hanford Management Contract (PHMC) portions of the Waste Feed Delivery (WFD) mission. In Phase 1 the SST System will be required to retrieve waste from selected SSTs (tanks 241-C-102 and 241-C-104) for transfer to the Double-Shell Tank (DST) System (tanks 241-AZ-101,241-AY-102). The SST System will include all the systems, structures and components required to safely store, retrieve, and transfer waste in support of the TWRS mission. Operational Specification Documents (OSDs) govern operation of the existing SST System components. However, the system will be highly modified to support the TWRS mission. Therefore OSD requirements may not apply to the new system's design. This document describes the review of existing SST OSDs and provides the rationale for selecting or rejecting requirements as constraints on the SST System design. The selected requirements (or design constraints) will be included in System Specification for the Single-Shell Tank System, HNF-3912(Conrads 1999).

  8. Turbulence-Turbine Interaction: The Basis for the Development of the TurbSim Stochastic Simulator

    SciTech Connect (OSTI)

    Kelley, N. D.

    2011-11-01

    A combination of taller wind turbines with more flexible rotors and towers operating in turbulent conditions that are not well understood is contributing to much higher than anticipated maintenance and repairs costs and is associated with lower energy production. This report documents evidence of this and offers the turbine designers an expanded tool that resolves many of these shortcomings.

  9. Ventuno Design | Open Energy Information

    Open Energy Info (EERE)

    Ventuno Design Jump to: navigation, search Name: Ventuno Design Place: Lower Saxony, Germany Zip: 49767 Sector: Wind energy Product: German-based wind farm developer with...

  10. Residential Retrofit Program Design Guide

    Broader source: Energy.gov [DOE]

    This Residential Retrofit Program Design Guide focuses on the key elements and design characteristics of building and maintaining a successful residential retrofit program.

  11. Thermionic Reactor Design Studies

    SciTech Connect (OSTI)

    Schock, Alfred

    1994-08-01

    Paper presented at the 29th IECEC in Monterey, CA in August 1994. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their (thermionic reactor) performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling.

  12. Achromatic Interaction Point Design

    SciTech Connect (OSTI)

    Guimei Wang,, Yaroslav Derbenev, S.Alex Bogacz, P. Chevtsov, Andre Afanaciev, Charles Ankenbrandt, Valentin Ivanov, Rolland P. Johnson

    2009-05-01

    Designers of high-luminosity energy-frontier muon colliders must provide strong beam focusing in the interaction regions. However, the construction of a strong, aberration-free beam focus is difficult and space consuming, and long straight sections generate an off-site radiation problem due to muon decay neutrinos that interact as they leave the surface of the earth. Without some way to mitigate the neutrino radiation problem, the maximum c.m. energy of a muon collider will be limited to about 3.5 TeV. A new concept for achromatic low beta design is being developed, in which the interaction region telescope and optical correction elements, are installed in the bending arcs. The concept, formulated analytically, combines space economy, a preventative approach to compensation for aberrations, and a reduction of neutrino flux concentration. An analytical theory for the aberration-free, low beta, spatially compact insertion is being developed.

  13. ESF BLAST DESIGN ANALYSIS

    SciTech Connect (OSTI)

    E.F. fitch

    1995-03-13

    The purpose and objective of this design analysis are to develop controls considered necessary and sufficient to implement the requirements for the controlled drilling and blasting excavation of operations support alcoves and test support alcoves in the Exploratory Studies Facility (ESF). The conclusions reached in this analysis will flow down into a construction specification ensuring controlled drilling and blasting excavation will be performed within the bounds established here.

  14. NRT preliminary design

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

    preliminary design - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  15. Rotor Aerodynamic Design

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

    Aerodynamic Design - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  16. Rotor Design Tools

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

    Design Tools - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear

  17. QA in Design Guidance

    Office of Environmental Management (EM)

    9 U.S. DEPARTMENT OF ENERGY OFFICE OF ENVIRONMENTAL MANAGEMENT Guidance Document for Integrating Quality Assurance During the Design and Construction Life Cycle September 2011 Page 2 of 29 FOREWORD This Department of Energy (DOE) Environmental Management (EM) guidance document is approved for use by all DOE EM organizational units and contractors performing work for EM. A project's Quality Assurance Program assigns responsibilities and authorities, defines policies and requirements, and provides

  18. GEM Technical Design Report

    SciTech Connect (OSTI)

    Not Available

    1993-07-31

    The GEM collaboration was formed in June 1991 to develop a major detector for the SSC. The primary physics objectives of GEM are those central to the motivation for the SSC, to study high p{sub T} physics - exemplified by the search for Higgs bosons - and to search for new physics beyond the standard model. The authors present in this Technical Design Report (TDR) a detector with broad capabilities for the discovery and subsequent study of electroweak symmetry breaking, the origin of mass and flavor, and other physics requiring precise measurements of gammas, electrons, and muons - hence the name, GEM. In addition, as a design goal, they have taken care to provide the robustness needed to do the physics that requires high luminosity. Finally, good coverage and hermeticity allow the detection of missing transverse energy, E{sub T}. The GEM design emphasizes clean identification and high resolution measurement of the primary physics signatures for high p{sub T} physics. The approach is to make precise energy measurements that maximize the sensitivity to rare narrow resonances, to detect the elementary interaction products (quarks, leptons, and photons), and to build in the features required to reduce backgrounds.

  19. Slurry reactor design studies

    SciTech Connect (OSTI)

    Fox, J.M.; Degen, B.D.; Cady, G.; Deslate, F.D.; Summers, R.L. ); Akgerman, A. ); Smith, J.M. )

    1990-06-01

    The objective of these studies was to perform a realistic evaluation of the relative costs of tublar-fixed-bed and slurry reactors for methanol, mixed alcohols and Fischer-Tropsch syntheses under conditions where they would realistically be expected to operate. The slurry Fischer-Tropsch reactor was, therefore, operated at low H{sub 2}/CO ratio on gas directly from a Shell gasifier. The fixed-bed reactor was operated on 2.0 H{sub 2}/CO ratio gas after adjustment by shift and CO{sub 2} removal. Every attempt was made to give each reactor the benefit of its optimum design condition and correlations were developed to extend the models beyond the range of the experimental pilot plant data. For the methanol design, comparisons were made for a recycle plant with high methanol yield, this being the standard design condition. It is recognized that this is not necessarily the optimum application for the slurry reactor, which is being proposed for a once-through operation, coproducing methanol and power. Consideration is also given to the applicability of the slurry reactor to mixed alcohols, based on conditions provided by Lurgi for an Octamix{trademark} plant using their standard tubular-fixed reactor technology. 7 figs., 26 tabs.

  20. Photovoltaic Incentive Design Handbook

    SciTech Connect (OSTI)

    Hoff, T. E.

    2006-12-01

    Investments in customer-owned grid-connected photovoltaic (PV) energy systems are growing at a steady pace. This is due, in part, to the availability of attractive economic incentives offered by public state agencies and utilities. In the United States, these incentives have largely been upfront lump payments tied to the system capacity rating. While capacity-based ''buydowns'' have stimulated the domestic PV market, they have been criticized for subsidizing systems with potentially poor energy performance. As a result, the industry has been forced to consider alternative incentive structures, particularly ones that pay based on long-term measured performance. The industry, however, lacks consensus in the debate over the tradeoffs between upfront incentive payments versus longer-term payments for energy delivery. This handbook is designed for agencies and utilities that offer or intend to offer incentive programs for customer-owned PV systems. Its purpose is to help select, design, and implement incentive programs that best meet programmatic goals. The handbook begins with a discussion of the various available incentive structures and then provides qualitative and quantitative tools necessary to design the most appropriate incentive structure. It concludes with program administration considerations.