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1

Design Basis Threat | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Design Basis Threat | National Nuclear Security Administration Design Basis Threat | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Design Basis Threat Home > About Us > Our Programs > Nuclear Security > 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)

2

Beyond Design Basis Events  

NLE Websites -- All DOE Office Websites (Extended Search)

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 results of these initiatives: Review of Requirements and Capabilities for Analyzing and Responding to BDBEs, August 2011, and 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.

3

Office of Nuclear Facility Basis & Facility Design  

NLE Websites -- All DOE Office Websites (Extended Search)

Office of Nuclear Safety Basis & Facility Design(HS-31) Reports to the Office of Nuclear Safety About Us The Office of Nuclear Safety Basis & Facility Design establishes safety...

4

Beyond Design Basis Events | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Beyond Design Basis Events 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 results of these initiatives: Review of Requirements and Capabilities for Analyzing and Responding to BDBEs, August 2011, and 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,

5

Assessing Beyond Design Basis Seismic Events and Implications on Seismic  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Assessing Beyond Design Basis Seismic Events and Implications on Assessing Beyond Design Basis Seismic Events and Implications on Seismic Risk Assessing Beyond Design Basis Seismic Events and Implications on Seismic Risk September 19, 2012 Presenter: Jeffrey Kimball, Technical Specialist (Seismologist) Defense Nuclear Facilities Safety Board Topics Covered: Department of Energy Approach to Natural Phenomena Hazards Analysis and Design (Seismic) Design Basis and Beyond Design Basis Seismic Events Seismic Risk Implications - Key Parameters and Insights Conclusions Assessing Beyond Design Basis Seismic Events and Implications on Seismic Risk More Documents & Publications DOE's Approach to Nuclear Facility Safety Analysis and Management Results from Beyond Design Basis Event Pilots Idaho National Laboratory Advanced Test Reactor Probabilistic Risk

6

Technical Basis for Regulatory Guidance on Design-Basis ...  

Science Conference Proceedings (OSTI)

... To ensure the safety of nuclear power plants in the event of a ... attained by potential hurricane-borne missiles specified for nuclear power plant design ...

2013-09-27T23:59:59.000Z

7

Beyond Design Basis Events Analysis and Response Information | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Beyond Design Basis Events Analysis Beyond Design Basis Events Analysis and Response Information Beyond Design Basis Events Analysis and Response Information September 19-20, 2012 Beyond Design Basis Events Analysis and Response Information DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011 DOE's Nuclear Safety Workshop Newsletter, June 2011 2011 Nuclear Safety Workshop Presentations, June 2011 Transmittal Memorandum, Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events, September 2011 Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events, August 2011 NRC Report - Recommendations for Enhancing Reactor Safety in the 21st Century; The Near-Term Task Force Review of Insights from the

8

CRAD, Engineering Design and Safety Basis - December 22, 2009 | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Engineering Design and Safety Basis - December 22, 2009 Engineering Design and Safety Basis - December 22, 2009 CRAD, Engineering Design and Safety Basis - December 22, 2009 December 22, 2009 Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0) The engineering design and safety basis inspection will evaluate the effectiveness of programs and processes for the design and safety basis of selected safety structures, systems, and components (SSCs) of a nuclear facility. The nuclear facility may be an existing facility, a major modification to an existing facility, or a new facility under construction. Accordingly, the safety basis for the facility, for example, a documented safety analysis (DSA) or a preliminary documented safety analysis (PDSA),

9

CRAD, Engineering Design and Safety Basis - December 22, 2009 | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Engineering Design and Safety Basis - December 22, 2009 Engineering Design and Safety Basis - December 22, 2009 CRAD, Engineering Design and Safety Basis - December 22, 2009 December 22, 2009 Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0) The engineering design and safety basis inspection will evaluate the effectiveness of programs and processes for the design and safety basis of selected safety structures, systems, and components (SSCs) of a nuclear facility. The nuclear facility may be an existing facility, a major modification to an existing facility, or a new facility under construction. Accordingly, the safety basis for the facility, for example, a documented safety analysis (DSA) or a preliminary documented safety analysis (PDSA),

10

Results from Beyond Design Basis Event Pilots | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Results from Beyond Design Basis Event Pilots Results from Beyond Design Basis Event Pilots Results from Beyond Design Basis Event Pilots September 19, 2012 Presenter: Mike Hillman, Program Manager, Office of Health, Safety and Security, US Department of Energy Topics covered: Update DOE safety analysis and emergency management requirements/guidance and perform pilot applications Perform system walkdowns and evaluations at several Cat 1 and 2 DOE nuclear facilities to assess potential susceptibilities to natural phenomena hazards and external BDBEs Conduct emergency drills and exercises at DOE sites with nuclear facilities, focusing on BDBEs Results from Beyond Design Basis Event Pilots More Documents & Publications Development of Guidance for Analysis of Beyond Design Basis Events Report to the Secretary of Energy on Beyond Design Basis Event Pilot

11

Design basis for the NRC Operations Center  

SciTech Connect

This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project.

Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

1983-05-01T23:59:59.000Z

12

Perspective on Beyond Design Basis Event Analysis and Response | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Perspective on Beyond Design Basis Event Analysis and Response Perspective on Beyond Design Basis Event Analysis and Response Perspective on Beyond Design Basis Event Analysis and Response September 20, 2012 Presenter: John Schwenker, Nuclear Safety Manager for Liquid Operations, Savannah River Remediation, LLC, Savannah River Site Topics Covered: Waste Tanks can contain up to 1.3 Millions Gallons of highly radioactive waste (sludge, salt, supernate). Type III/IIIA Waste Tank Structures and berms are PC-3 Qualified. Tanks may fail in a Beyond Design Basis Seismic Event. Waste could flow above ground to streams and rivers. Unmitigated Tank Explosion exceeds offsite Evaluation Guidelines Hydrogen gas can be trapped in the sludge and saltcake structure. Seismic Event can cause a prompt release of trapped hydrogen. It is not physically practical to install a ventilation system that

13

Development of Guidance for Analysis of Beyond Design Basis Events |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Development of Guidance for Analysis of Beyond Design Basis Events Development of Guidance for Analysis of Beyond Design Basis Events Development of Guidance for Analysis of Beyond Design Basis Events Wednesday, September 19 Presenter: Dr. James O'Brien, Director, Office of Nuclear Safety, Office of Health, Safety and Security, US Department of Energy Topics covered: Types of DOE Facilities ◦ Research Reactors; ◦ Weapons disassembly, maintenance, and testing facilities; ◦ Nuclear material storage facilities; ◦ Processing facilities; and waste disposal facilities. Safety Analysis Framework ◦ DOE Nuclear Safety Policy ◦ Nuclear Safety Rule ◦ Nuclear Safety Analysis Standards ◦ Documented Safety Analysis Guide Development of Guidance for Analysis of Beyond Design Basis Events More Documents & Publications DOE's Approach to Nuclear Facility Safety Analysis and Management

14

The Functional Requirements and Design Basis for Information Barriers  

SciTech Connect

This report summarizes the results of the Information Barrier Working Group workshop held at Sandia National Laboratory in Albuquerque, NM, February 2-4, 1999. This workshop was convened to establish the functional requirements associated with warhead radiation signature information barriers, to identify the major design elements of any such system or approach, and to identify a design basis for each of these major elements. Such information forms the general design basis to be used in designing, fabricating, and evaluating the complete integrated systems developed for specific purposes.

Fuller, James L.

2012-05-01T23:59:59.000Z

15

SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747  

SciTech Connect

'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents.

RYAN GW

2007-09-24T23:59:59.000Z

16

Solar Power Tower Design Basis Document, Revision 0  

DOE Green Energy (OSTI)

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.

ZAVOICO,ALEXIS B.

2001-07-01T23:59:59.000Z

17

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

18

Canister Storage Building (CSB) Design Basis Accident Analysis Documentation  

Science Conference Proceedings (OSTI)

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.

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

2000-03-23T23:59:59.000Z

19

Basis for NGNP Reactor Design Down-Selection  

Science Conference Proceedings (OSTI)

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.

L.E. Demick

2010-08-01T23:59:59.000Z

20

Basis for NGNP Reactor Design Down-Selection  

SciTech Connect

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.

L.E. Demick

2011-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Cold Vacuum Drying facility design basis accident analysis documentation  

SciTech Connect

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.

CROWE, R.D.

2000-08-08T23:59:59.000Z

22

Engineering Design and Safety Basis Inspection Criteria, Inspection...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

also may address certain other interfacing functional areas, such as configuration management, operations, maintenance, testing, design procedures, personnel training and...

23

First-Generation Monitoring System for ADA: Design Basis  

Science Conference Proceedings (OSTI)

The vision of the EPRI ADA Program (Program 124) is to create the technology basis for the distribution system of the future by transforming traditional single-function distribution systems into multifunctional power and information exchange systems with increased reliability, improved performance (lower system losses), better economics, better power quality, and more customer service options. Achieving this vision will require capturing the benefits of new capabilities in power electronics, information ...

2006-12-18T23:59:59.000Z

24

Threat Characterization  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

to work with publicprivate stakeholders - Develop a mechanism for sharing threat information Technology Transfer, Collaborations, and Partnerships Next Steps * Approach...

25

Threat Characterization  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Michalski Michalski SNL Department 5621 Threat Characterization Summary Slide: Threat Characterization Outcomes: Develop a network analysis toolset to allow an analyst to efficiently "crawl" large data sets to discover relevant threat information. Road Map Challenges:"The ability to discover & understand emerging threats and vulnerabilities is a prerequisite to developing effective countermeasures" Major Successes: * Implemented prototype front end crawler and semantic analysis engine (Sandia National Labs). * Transition Development work to the Institute for Complex Additive System Analysis (ICASA) Center (NMTech) * Quarterly threat reports being produced  Schedule: Improvements to both the analyst process and GUI Interface, 4Q 2009; Transition maintenance and development to

26

Drain Tank Information for Developing Design Basis of the Preliminary Design  

Science Conference Proceedings (OSTI)

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.

Ferrada, Juan J [ORNL

2012-02-01T23:59:59.000Z

27

Drain Tank Information for Developing Design Basis of the Preliminary Design  

Science Conference Proceedings (OSTI)

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.

Ferrada, Juan J [ORNL

2011-01-01T23:59:59.000Z

28

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

SciTech Connect

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.

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

2011-10-05T23:59:59.000Z

29

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

SciTech Connect

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.

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

2011-10-05T23:59:59.000Z

30

A Report to the Secretary of Energy, Beyond Design Basis Event Pilot Evaluations  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Beyond Design Basis Event Beyond Design Basis Event Pilot Evaluations Results and Recommendations for Improvements to Enhance Nuclear Safety at Department of Energy Nuclear Facilities Office of Nuclear Safety Office of Health, Safety and Security U.S. Department of Energy January 2013 Beyond Design Basis Event Pilot Evaluations TABLE OF CONTENTS Executive Summary i Acronyms iv 1.0 Introduction and Purpose 1 2.0 Background 2 3.0 Pilot Evaluations of Safety Analysis, NPH, and Emergency Management Guidance 2 4.0 Insights Gained from NRC and the Nuclear Community 11 5.0 Summary of Results and Recommendations 12 6.0 Conclusions 14 Appendix A - Pilot Evaluation Team Members 15 Beyond Design Basis Event Pilot Evaluations * i

31

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE M&O Contractor Perspectives on Beyond Design Basis Event DOE M&O Contractor Perspectives on Beyond Design Basis Event Analysis and Response DOE M&O Contractor Perspectives on Beyond Design Basis Event Analysis and Response September 20, 2013 Presenter: Ron Crone, Director Research Reactors Division UT-Battelle, LLC Oak Ridge National Laboratory HFIR serves a broad range of science and technology communities and will need to operate to at least 2040 until replacement capabiltiies are available DOE M&O Contractor Perspectives on Beyond Design Basis Event Analysis and Response More Documents & Publications Independent Oversight Review, Oak Ridge National Laboratory - January 2013 Preliminary Notice of Violation, Lockheed Martin Energy Research Corporation - EA-98-13 EIS-0373: Draft Environmental Impact Statement, Summary

32

The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)  

SciTech Connect

The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration.

NONE

1994-12-01T23:59:59.000Z

33

Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Bulletin 2011-01, Events Beyond Design Safety Basis Analysis Bulletin 2011-01, Events Beyond Design Safety Basis Analysis Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis PURPOSE This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. BACKGROUND On March 11 , 2011 , the Fukushima Daiichi nuclear power station in Japan was damaged by a magnitude 9.0 earthquake and the subsequent tsunami. While there is still a lot to be learned from the accident · about the adequacy of design specifications and the equipment failure modes, reports from the Nuclear Regulatory Commission (NRC) have identified some key aspects of the operational emergency at the Fukushima Daiichi nuclear power station.

34

Report to the Secretary of Energy on Beyond Design Basis Event Pilot  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Facilities, January 2013 Facilities, January 2013 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 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. BDBE_Report_final.pdf More Documents & Publications Report to the Secretary of Energy on Beyond Design Basis Event Pilot

35

Operating Experience Level 1 - Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

OE-1: 2013-01 April 2013 OE-1: 2013-01 April 2013 Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events PURPOSE: The purpose of this Operating Experience (OE) document is to (1) provide results from U.S. Department of Energy (DOE), including the National Nuclear Security Administration , initiatives related to beyond design basis events (BDBEs) , and (2) provide direction for enhancing capabilities for mitigating BDBEs at DOE sites . BACKGROUND: After the March 2011 Fukushima Daiich i nuclear plant accident in Japan , DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to BDBEs. These initiatives included issuing Safety Bulletin 2011-01 , Events Beyond Design Safety Basis Analysis, conducting pilots to refine possible

36

Report to the Secretary of Energy on Beyond Design Basis Event Pilot  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Facilities, January 2013 Facilities, January 2013 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 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. BDBE_Report_final.pdf More Documents & Publications Report to the Secretary of Energy on Beyond Design Basis Event Pilot

37

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

SciTech Connect

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.

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

2011-11-01T23:59:59.000Z

38

Report to the Secretary of Energy on Beyond Design Basis Event Pilot  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Facilities Facilities 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 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. Based on recommendations in the August 2011 report, DOE embarked on a project to develop and refine guidance that supports improvements in DOE's processes for analyzing and

39

Report to the Secretary of Energy on Beyond Design Basis Event Pilot  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Facilities Facilities 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 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. Based on recommendations in the August 2011 report, DOE embarked on a project to develop and refine guidance that supports improvements in DOE's processes for analyzing and

40

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

Science Conference Proceedings (OSTI)

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.

Agrawal, A.K.

1983-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

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

SciTech Connect

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.

Simecka, W.B. [USDOE Nevada Field Office, Las Vegas, NV (United States); Grant, T.A.; Voegele, M.D. [Science Applications International Corp., Las Vegas, NV (United States); Cline, K.M. [Woodward-Clyde Federal Services, Washington, DC (United States)

1992-12-31T23:59:59.000Z

42

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

SciTech Connect

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.

Braverman, J.I.; Morante, R.

2010-07-18T23:59:59.000Z

43

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

SciTech Connect

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.

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

2000-03-01T23:59:59.000Z

44

Review of Requirements and Capabilities For Analyzing and Responding to Beyond Design Basis Events  

NLE Websites -- All DOE Office Websites (Extended Search)

to the to the Secretary of Energy Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events Office of Nuclear Safety Office of Health, Safety and Security U.S. Department of Energy August 2011 2011 Safety Bulletin Report TABLE OF CONTENTS Acronyms i Executive Summary ii 1. Introduction 1 2. Report Overview 1 3. Overview of DOE Nuclear Facilities and Operations 2 4. Analysis of Safety Bulletin Submittals 2 5. Review of DOE and Commercial Nuclear Power Industry Requirements and 5 Guidance for BDBEs 6. Results from the Nuclear Safety Workshop 9 7. Summary of Insights and Opportunities for Improvement 10 8. Summary of Recommendations 12 9. Conclusions 14

45

Review of Requirements and Capabilities For Analyzing and Responding to Beyond Design Basis Events  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Review of Requirements Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events Office of Nuclear Safety Office of Health, Safety and Security U.S. Department of Energy August 2011 2011 Safety Bulletin Report TABLE OF CONTENTS Acronyms i Executive Summary ii 1. Introduction 1 2. Report Overview 1 3. Overview of DOE Nuclear Facilities and Operations 2 4. Analysis of Safety Bulletin Submittals 2 5. Review of DOE and Commercial Nuclear Power Industry Requirements and 5 Guidance for BDBEs 6. Results from the Nuclear Safety Workshop 9 7. Summary of Insights and Opportunities for Improvement 10 8. Summary of Recommendations 12 9. Conclusions 14 Appendix A - DOE's Nuclear Safety Approach 15

46

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

SciTech Connect

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.

Bergman, W. [Lawrence Livermore National Lab., CA (United States); First, M.W. [Harvard School of Public Health, Boston, MA (United States); Anderson, W.L. [Consultant, LaPlata, MD (United States); Gilbert, H. [Consultant, McLean, VA (United States); Jacox, J.W. [Consultant, Columbus, OH (United States)

1994-12-01T23:59:59.000Z

47

Approach to developing a ground-motion design basis for facilities important to safety at Yucca Mountain  

SciTech Connect

The Department of Energy has proposed a methodology for developing a ground-motion design basis for prospective facilities at Yucca Mountain that are important to safety. The methodology utilizes a quasi-deterministic construct that is designed to provide a conservative, robust, and reproducible estimate of ground motion that has a one-in-ten chance of occurring during the preclosure period. This estimate is intended to define a ground-motion level for which the seismic design would ensure minimal disruption to operations; engineering analyses to ensure safe performance in the unlikely event that the design basis is exceeded are a part of the proposed methodology. 8 refs.

King, J.L.

1990-04-01T23:59:59.000Z

48

Cyber threat metrics.  

SciTech Connect

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.

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

2012-03-01T23:59:59.000Z

49

SRS BEDROCK PROBABILISTIC SEISMIC HAZARD ANALYSIS (PSHA) DESIGN BASIS JUSTIFICATION (U)  

SciTech Connect

This represents an assessment of the available Savannah River Site (SRS) hard-rock probabilistic seismic hazard assessments (PSHAs), including PSHAs recently completed, for incorporation in the SRS seismic hazard update. The prior assessment of the SRS seismic design basis (WSRC, 1997) incorporated the results from two PSHAs that were published in 1988 and 1993. Because of the vintage of these studies, an assessment is necessary to establish the value of these PSHAs considering more recently collected data affecting seismic hazards and the availability of more recent PSHAs. This task is consistent with the Department of Energy (DOE) order, DOE O 420.1B and DOE guidance document DOE G 420.1-2. Following DOE guidance, the National Map Hazard was reviewed and incorporated in this assessment. In addition to the National Map hazard, alternative ground motion attenuation models (GMAMs) are used with the National Map source model to produce alternate hazard assessments for the SRS. These hazard assessments are the basis for the updated hard-rock hazard recommendation made in this report. The development and comparison of hazard based on the National Map models and PSHAs completed using alternate GMAMs provides increased confidence in this hazard recommendation. The alternate GMAMs are the EPRI (2004), USGS (2002) and a regional specific model (Silva et al., 2004). Weights of 0.6, 0.3 and 0.1 are recommended for EPRI (2004), USGS (2002) and Silva et al. (2004) respectively. This weighting gives cluster weights of .39, .29, .15, .17 for the 1-corner, 2-corner, hybrid, and Greens-function models, respectively. This assessment is judged to be conservative as compared to WSRC (1997) and incorporates the range of prevailing expert opinion pertinent to the development of seismic hazard at the SRS. The corresponding SRS hard-rock uniform hazard spectra are greater than the design spectra developed in WSRC (1997) that were based on the LLNL (1993) and EPRI (1988) PSHAs. The primary reasons for this difference is the greater activity rate used in contemporary models for the Charleston source zone and proper incorporation of uncertainty and randomness in GMAMs.

(NOEMAIL), R

2005-12-14T23:59:59.000Z

50

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

NLE Websites -- All DOE Office Websites (Extended Search)

Basis Event Pilot Evaluations Results and Recommendations for Improvements to Enhance Nuclear Safety at Department of Energy Nuclear Facilities Office of Nuclear Safety Office...

51

Fusion Engineering and Design 80 (2006) 2562 Physics basis for the advanced tokamak fusion  

E-Print Network (OSTI)

2005 Abstract The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power.V. All rights reserved. Keywords: Reactor studies; Fusion power plant; Advanced tokamak; Physics basis 1

52

MEMORANDUM FOR DISTRIBUTION - Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

September 16, 2011 September 16, 2011 MEMORANDUM FOR DISTRIBUTION FROM: SUBJECT: DANIEL B. PONEMA Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events Following 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. These actions focused on learning how DOE can better prepare to manage potential beyond design basis events. A summary of these actions and the resulting insights, and recommended opportunities and actions to improve nuclear safety at DOE> are included in the attached report. I have directed the Office of Health, Safety and Security (HSS) to work with DOE's Nuclear Safety and Security Coordinating Council, and the Program and Field Offices of

53

MEMORANDUM FOR DISTRIBUTION - Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events  

NLE Websites -- All DOE Office Websites (Extended Search)

September 16, 2011 September 16, 2011 MEMORANDUM FOR DISTRIBUTION FROM: SUBJECT: DANIEL B. PONEMA Report on Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events Following 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. These actions focused on learning how DOE can better prepare to manage potential beyond design basis events. A summary of these actions and the resulting insights, and recommended opportunities and actions to improve nuclear safety at DOE> are included in the attached report. I have directed the Office of Health, Safety and Security (HSS) to work with DOE's Nuclear Safety and Security Coordinating Council, and the Program and Field Offices of

54

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Savannah River Site Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development May 2011 August 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope and Methodology ......................................................................................................................... 2 4.0 Results .................................................................................................................................................... 3

55

The Cyber Threat to National Critical Infrastructures: Beyond Theory  

Science Conference Proceedings (OSTI)

Adversary threats to critical infrastructures have always existed during times of conflict, but threat scenarios now include peacetime attacks from anonymous computer hackers. Current events, including examples from Israel and Estonia, prove that a certain ... Keywords: Estonia, business continuity and disaster recover planning, critical, cyber, infrastructure, security architecture and design, telecommunications and network security threat

Kenneth Geers

2009-01-01T23:59:59.000Z

56

Physics basis for an axicell design for the end plugs of MFTF-B  

SciTech Connect

The primary motivation for conversion of MFTF-B to an axicell configuration lies in its engineering promise as a reactor geometry based on circular high-magnetic-field coils. In comparing this configuration to the previous A-cell geometry, we find a number of differences that might significantly affect the physics performance. The purpose of the present document is to examine those features and to assess their impact on the performance of the axicell, as compared to the A-cell configuration, for MFTF-B. In so doing, we address only those issues thought to be affected by the change in geometry and refer to the original report Physics Basis for MFTF-B, for discussion of those issues thought not to be affected. In Sec. 1, we summarize these physics issues. In Sec. 2, we describe operating scenarios in the new configuration. In the Appendices, we discuss those physics issues that require more detailed treatment.

Baldwin, D.E.; Logan, B.G. (eds.)

1982-04-21T23:59:59.000Z

57

Categorizing Threat Building and Using a Generic Threat Matrix | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Categorizing Threat Building and Using a Generic Threat Matrix Categorizing Threat Building and Using a Generic Threat Matrix Categorizing Threat Building and Using a Generic Threat Matrix The key piece of knowledge necessary for building defenses capable of withstanding or surviving cyber and kinetic attacks is an understanding of the capabilities posed by threats to a government, function, or system. With the number of threats continuing to increase, it is no longer feasible to enumerate the capabilities of all known threats and then build defenses based on those threats that are considered, at the time, to be the most relevant. Exacerbating the problem for critical infrastructure entities is the fact that the majority of detailed threat information for higher-level threats is held in classified status and is not available for general

58

Guidelines for Determining Design Basis Ground Motions: Volumes 1-5  

Science Conference Proceedings (OSTI)

Procedures currently used to assess the nature of earthquake ground motion in Eastern North America introduce considerable uncertainty to the design parameters of nuclear power plants and other critical facilities. This report examines that issue in-depth and provides an engineering model and guideline for selecting a site and assessing its seismic suitability.

1993-12-23T23:59:59.000Z

59

Guidelines for Determining Design Basis Ground Motions: Volumes 1-5  

Science Conference Proceedings (OSTI)

Procedures currently used to assess the nature of earthquake ground motion in Eastern North America introduce considerable uncertainty to the design parameters of nuclear power plants and other critical facilities. This report examines that issue in-depth and provides an engineering model and guideline for selecting a site and assessing its seismic suitability.

1993-12-01T23:59:59.000Z

60

Exploratory Shaft Seismic Design Basis Working Group report; Yucca Mountain Project  

SciTech Connect

This report was prepared for the Yucca Mountain Project (YMP), which is managed by the US Department of Energy. The participants in the YMP are investigating the suitability of a site at Yucca Mountain, Nevada, for construction of a repository for high-level radioactive waste. An exploratory shaft facility (ESF) will be constructed to permit site characterization. The major components of the ESF are two shafts that will be used to provide access to the underground test areas for men, utilities, and ventilation. If a repository is constructed at the site, the exploratory shafts will be converted for use as intake ventilation shafts. In the context of both underground nuclear explosions (conducted at the nearby Nevada Test Site) and earthquakes, the report contains discussions of faulting potential at the site, control motions at depth, material properties of the different rock layers relevant to seismic design, the strain tensor for each of the waveforms along the shaft liners, and the method for combining the different strain components along the shaft liners. The report also describes analytic methods, assumptions used to ensure conservatism, and uncertainties in the data. The analyses show that none of the shafts` structures, systems, or components are important to public radiological safety; therefore, the shafts need only be designed to ensure worker safety, and the report recommends seismic design parameters appropriate for this purpose. 31 refs., 5 figs., 6 tabs.

Subramanian, C.V. [Sandia National Labs., Albuquerque, NM (USA); King, J.L. [Science Applications International Corp., Las Vegas, NV (USA); Perkins, D.M. [Geological Survey, Denver, CO (USA); Mudd, R.W. [Fenix and Scisson, Inc., Tulsa, OK (USA); Richardson, A.M. [Parsons, Brinckerhoff, Quade and Douglas, Inc., San Francisco, CA (USA); Calovini, J.C. [Holmes and Narver, Inc., Las Vegas, NV (USA); Van Eeckhout, E. [Los Alamos National Lab., NM (USA); Emerson, D.O. [Lawrence Livermore National Lab., CA (USA)

1990-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Design basis and requirements for 241-SY modular exhauster mechanical installation  

SciTech Connect

A new ventilation system is being installed to serve as the K-1 primary exhauster. The existing K-1 primary exhauster will then become the backup. This ventilation system services waste tanks 241-SY-101, 102 and 103. The nominal flow rate through the ventilation system is 1,000 cfm. The new ventilation system will contain a moisture eliminator, a heater, a prefilter, two stages of HEPA filtration, an exhaust fan, a stack and stack sampling system. The purpose of this document is to serve as the design and functional requirements for the mechanical installation of the new 241-SY modular exhauster. The mechanical installation will include modifying the existing ductwork (i.e., installing a ``T`` to connect the new exhauster to the existing system), modifying the existing condensate drain lines to accommodate the new lines associated with the new exhauster, a maintenance platform near the stack of the new exhauster, guy wires and guy wire footings to support the stack of the new exhauster, as well as other miscellaneous tasks associated with the mechanical installation design effort.

Kriskovich, J.R.

1994-11-10T23:59:59.000Z

62

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

SciTech Connect

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.

Not Available

1993-03-18T23:59:59.000Z

63

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

SciTech Connect

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.

Not Available

1993-03-18T23:59:59.000Z

64

Pretreatment of neutralized cladding removal waste sludge: Results of the second design basis experiment  

SciTech Connect

For several years, the Pacific Northwest Laboratory (PNL) has been investigating methods to pretreat Hanford neutralized cladding removal waste (NCRW) sludge. In the past, Zircaloy-clad metallic U fuel was chemically decladded using the Zirflex process; NCRW sludge was formed when the decladding solution was neutralized for storage in carbon-steel tanks. This sludge, which is currently stored in Tanks 103-AW and 105-AW on the Hanford Site, primarily consists of insoluble Zr hydroxides and/or oxides and NaF. Significant quantities of Al, La, U, as well as other insoluble minor constituents are present in the sludge, along with sodium and potassium nitrates, nitrites, and hydroxides in the interstitial liquid. The sludge contains about 2,000 nCi of transuranic (TRU) material per gram of dry sludge, and mixed fission products. Therefore, the sludge must be handled as high-level waste (HLW). The NCRW sludge must be pretreated before treatment (e.g., vitrification) and disposal, so that the overall cost of disposal can be minimized. The NCRW pretreatment flowsheet was designed to achieve the following objectives: (a) to separate Am and Pu from the major sludge constituents (Na, Zr). (b) to separate Am and Pu from U. (c) to concentrate Am and Pu in a small volume for immobilization in borosilicate glass, based on Hanford Waste Vitrification Plant (HWVP). The flowsheet involves: (1) sludge washing, (2) sludge dissolution, (3) extraction of U with tributyl phosphate (TBP), and (4) extraction of TRUs with octyl(phenyl)-N,N-diisobutlycarbamoylmethyl-phosphine oxide (CMPO). As presented in the flowsheet, the NCRW sludge is first washed with 0.I M NaOH to remove interstitial liquid and soluble salts from the sludge including sodium and potassium fluorides, carbonates, hydroxides, nitrates, and nitrites. The washed sludge is then subjected to two dissolution steps to achieve near complete dissolution of Zr.

Lumetta, G.J.

1994-05-01T23:59:59.000Z

65

Development of Design Basis Earthquake Parameters for TMI-2 Independent Spent Fuel Storage Installation at the INEEL  

SciTech Connect

Probabilistically-based Design Basis Earthquake (DBE) ground motion parameters have been developed for the TMI-2 Independent Spent Fuel Storage Installation (ISFSI) located at the Idaho Nuclear Technology and Engineering Center (INTEC), Idaho National Engineering and Environmental Laboratory. The probabilistic seismic hazard at INTEC has been recomputed using ground motion attenuation relationships more appropriate for extensional tectonic regimes. The empirical attenuation relationships used in this analysis were adjusted for extensional tectonic regimes as part of the Yucca Mountain Project. Seismic hazard curves and uniform hazard spectra for rock produced using the revised attenuation relationships result in lower ground motions when compared to the results of the 1996 INEEL site-wide seismic hazard evaluation. The DBE ground motions for rock and soil have been developed to be applicable to the TMI-2 ISFSI and the entire INTEC site by incorporating variations in the rock and soil properties over the INTEC area. The DBE rock and soil ground motions presented in the report are recommended for use in developing final design earthquake parameters. Peer reviewers of this report support this recommendation. Because the Nuclear Regulatory Commission regulations have recently evolved to incorporate probabilistically-based seismic design for independent fuel storage facilities, a deterministic Maximum Credible Earthquake analysis performed for INTEC earlier in this study is also presented in this report.

URS Greiner Woodward Clyde Federal Services; Geomatrix Consultants; Pacific Engineering and Analysis; S. M. Payne (INEEL POC)

1999-11-01T23:59:59.000Z

66

Global Threat Reduction Initiative  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

comprehensive 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 efforts result in threat reduction by improving security on the bomb material remaining at civilian sites - each vulnerable building that is protected reduces the risk until a permanent threat reduction solution can be implemented.

67

Insider Threat.pptx  

NLE Websites -- All DOE Office Websites (Extended Search)

Mitigating the Insider Threat Mitigating the Insider Threat (and Other Security Issues) Roger G. Johnston, Ph.D., CPP Vulnerability Assessment Team Argonne National Laboratory http://www.ne.anl.gov/capabilities/vat Argonne National Laboratory ~$738 million annual budget 1500 acres, 3400 employees, 4400 facility users, 1500 students R&D and technical assistance for government & industry Sponsors * DHS * DoD * DOS * IAEA * Euratom * DOE/NNSA * private companies * intelligence agencies * public interest organizations The VAT has done detailed vulnerability assessments on hundreds of different security devices, systems, & programs. Vulnerability Assessment Team (VAT) The greatest of faults, I should say, is to be conscious of none.

68

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

Science Conference Proceedings (OSTI)

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).

Payne, Suzette

2008-08-01T23:59:59.000Z

69

Calculation of particulate dispersion in a design-basis tornadic storm from the Battelle Memorial Institute, Columbus, Ohio  

SciTech Connect

A three-dimensional numerical model is used to calculate ground-level air concentration and deposition (due to precipitation scavenging) after a hypothetical tornado strike at the Battelle Memorial Institute at Columbus, Ohio. Plutonium particles less than 20 ..mu..m in diameter are assumed to be lifted into the tornadic storm cell by the vortex. The rotational characteristics of the tornadic storm are embedded within the larger mesoscale flow of the storm system. The design-basis translational wind value is based on probabilities associated with existing records of tornado strikes in the vicinity of the plant site. Turbulence exchange coefficients are based on empirical values deduced from experimental data in severe storms and from theoretical assumptions obtained from the literature. The method of moments is used to incorporate subgrid-scale resolution of the concentration within a grid cell volume.

Pepper, D.W.

1980-10-01T23:59:59.000Z

70

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

SciTech Connect

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.

Walston, S; Rowland, M; Campbell, K

2011-07-27T23:59:59.000Z

71

Software Addresses Terrorist Building Threats  

Science Conference Proceedings (OSTI)

... guard against terrorist threats to their facilities. ... Its essential components are risk assessment, identification ... strategies to reduce facility vulnerability. ...

2013-04-23T23:59:59.000Z

72

Threat Analysis Framework | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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...

73

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

SciTech Connect

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.

Bergman, W. [Lawrence Livermore National Lab., CA (United States); First, M.W. [Harvard School of Public Health, Boston, MA (United States); Anderson, W.L. [Anderson (W.L.), LaPlata, MD (United States); Gilbert, H. [Gilbert (H.), McLean, VA (United States); Jacox, J.W. [Jacox (J.W.), Columbus, OH (United States)

1995-02-01T23:59:59.000Z

74

Proliferation: Threat and response  

Science Conference Proceedings (OSTI)

The May 1997 Report of the Quadrennial Defense Review (QDR) concluded that the threat or use of nuclear, biological, or chemical (NBC) weapons is a likely condition of future warfare and could occur in the early stages of war to disrupt US operations and logistics. These weapons may be delivered by ballistic missiles, cruise missiles, aircraft, special operations forces, or other means. In many of the world`s regions where the United States is likely to deploy forces--including Northeast Asia and the Middle East--potential adversaries have chemical and/or biological weapons and the missile systems to deliver them, and actively seek nuclear weapons. Potential adversaries may seek to counter American conventional military superiority using less expensive and more attainable, asymmetrical means, including NBC weapons. To meet this challenge, as well as the possibility that NBC weapons might also be used in some smaller-scale contingencies, US forces must be properly trained and equipped to operate effectively and decisively in the face of NBC attacks. The first section of this report details the proliferation of NBC weapons and the threat it poses to US interests and forces.

NONE

1997-11-01T23:59:59.000Z

75

Facebook: Threats to Privacy  

E-Print Network (OSTI)

End-users share a wide variety of information on Facebook, but a discussion of the privacy implications of doing so has yet to emerge. We examined how Facebook affects privacy, and found serious flaws in the system. Privacy on Facebook is undermined by three principal factors: users disclose too much, Facebook does not take adequate steps to protect user privacy, and third parties are actively seeking out end-user information using Facebook. We based our end-user findings on a survey of MIT students and statistical analysis of Facebook data from MIT, Harvard, NYU, and the University of Oklahoma. We analyzed the Facebook system in terms of Fair Information Practices as recommended by the Federal Trade Commission. In light of the information available and the system that protects it, we used a threat model to analyze specific privacy risks. Specifically, university administrators are using Facebook for disciplinary purposes, firms are using it for marketing purposes, and intruders are exploiting security holes. For each threat, we analyze the efficacy of the current protection, and where solutions are inadequate, we make recommendations on how to address the issue.

Harvey Jones; Jos Hiram Soltren

2005-01-01T23:59:59.000Z

76

Global Threat Reduction Initiative  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nonproliferation Nonproliferation U.S. DEPARTMENT OF ENERGY 1 The Current Status of Gap and U.S.-Origin Nuclear Fuel Removals 2011 Jeff Galan, Deputy Project Manager U.S.-Origin Nuclear Remove Program National Nuclear Security Administration Global Threat Reduction Initiative Defense Nuclear Nonproliferation U.S. DEPARTMENT OF ENERGY 2 GTRI Mission and Goals GTRI is: A part of President Obama's 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

77

An analysis of security threats to mobile IPv6  

Science Conference Proceedings (OSTI)

In parallel with the design of IPv6, several protocol extensions for mobility support of IPv6 nodes have been proposed and these continue to evolve. However, a variety of security threats arise and these have to be taken in to account in the design of ... Keywords: CGA, MIPv6, binding update attacks, care-of address tests, cryptographically generated addresses, flooding attacks, home tests, internet protocol, mobile IPv6, replay attacks, return routability, security threats, triangular routing

Michael Durr; Ray Hunt

2008-09-01T23:59:59.000Z

78

Insider Threat - Material Control and Accountability Mitigation  

Science Conference Proceedings (OSTI)

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.

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

2011-01-01T23:59:59.000Z

79

Electric Utility Rate Design Study: embedded generation costs on a time-of-day basis for Iowa Southern Utilities Company  

SciTech Connect

This report develops a method for determining average embedded generation costs on a time-of-day basis and describes the application of the method to Iowa Southern Utilities. These costs are not allocated to customer classes. Since average embedded costs are composed of the running (or variable) costs and the capital costs, the analysis examines each of these separately. Running costs on a time-of-day basis are determined through the use of a generation dispatch model that reports the loadings by generating unit and the running costs of meeting the load. These costs are reported on an hour-by-hour basis. The dispatch model takes into account the operating characteristics of each unit and the major engineering constraints on a system; e.g., must-run units, minimum up and down time, startup cost. After reviewing several suggested capital-cost allocation procedures, a method is developed that allocates capital costs on a time-of-day basis by using a recontracting-for-capacity procedure that allows capacity to vary by hour for each month. The method results in allocations to customers who benefit from its use. An important and distinguishing feature of this method is that it allows calculation of the costs before rating periods are chosen.

1980-01-01T23:59:59.000Z

80

Bio-threat microparticle simulants  

SciTech Connect

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.

Farquar, George Roy; Leif, Roald N

2012-10-23T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Understanding cyber threats and vulnerabilities  

Science Conference Proceedings (OSTI)

This chapter reviews current and anticipated cyber-related threats to the Critical Information Infrastructure (CII) and Critical Infrastructures (CI). The potential impact of cyber-terrorism to CII and CI has been coined many times since the term was ... Keywords: actor, critical infrastructure, cyber crime, cyber terrorism, cyber threat, cyber vulnerabilities

Eric Luiijf

2012-01-01T23:59:59.000Z

82

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

NLE Websites -- All DOE Office Websites (Extended Search)

Appraisal of the Appraisal of the Uranium Processing Facility Safety Basis Preliminary Safety Design Report Process at the Y-12 National Security Complex May 2011 May 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 2

83

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Appraisal of the Appraisal of the Uranium Processing Facility Safety Basis Preliminary Safety Design Report Process at the Y-12 National Security Complex May 2011 May 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 2

84

EPR Severe Accident Threats and Mitigation  

SciTech Connect

Despite the extremely low EPR core melt frequency, an improved defence-in-depth approach is applied in order to comply with the EPR safety target: no stringent countermeasures should be necessary outside the immediate plant vicinity like evacuation, relocation or food control other than the first harvest in case of a severe accident. Design provisions eliminate energetic events and maintain the containment integrity and leak-tightness during the entire course of the accident. Based on scenarios that cover a broad range of physical phenomena and which provide a sound envelope of boundary conditions associated with each containment challenge, a selection of representative loads has been done, for which mitigation measures have to cope with. This paper presents the main critical threats and the approach used to mitigate those threats. (authors)

Azarian, G. [Framatome ANP SAS, Tour Areva, Place de la Coupole 92084 Paris la Defense (France); Kursawe, H.M.; Nie, M.; Fischer, M.; Eyink, J. [Framatome ANP GmbH, Freyeslebenstrasse, 1, D-91058 Erlangen (Germany); Stoudt, R.H. [Framatome ANP Inc. - 3315 Old Forest Rd, Lynchburgh, VA 24501 (United States)

2004-07-01T23:59:59.000Z

85

Nuclear Radiological Threat Task Force Established | National...  

National Nuclear Security Administration (NNSA)

Force Established Nuclear Radiological Threat Task Force Established November 03, 2003 Washington, DC Nuclear Radiological Threat Task Force Established NNSA's Administrator...

86

Containment Versus Confinement for High-Temperature Gas Reactors: Regulatory, Design Basis, Siting, and Cost/Economic Considerations  

Science Conference Proceedings (OSTI)

This report provides the results of an investigation pertaining to the use of the confinement that has been proposed for the high temperature and very high temperature gas reactors (HTGR, VHTR). No comprehensive study of this question has been published since 1985. All power reactor designs to go into commercial service in the United States were light water reactors (LWR), except for Fort St. Vrain (FSV) and Peach Bottom Unit 1, which were steam cycle helium gas cooled reactors. All designs use a leak-ti...

2005-05-04T23:59:59.000Z

87

CoalFleet User Design Basis Specification for Coal-Based Integrated Gasification Combined Cycle (IGCC) Power Plants  

Science Conference Proceedings (OSTI)

The Duke Edwardsport integrated gasification combined-cycle (IGCC) power plant started up in 2012, and Mississippi Powers Kemper County IGCC plant is in construction. The capital cost of these initial commercial scale IGCC plants is high. The industry needs specifications that encourage greater standardization in IGCC design in order to bring down the investment cost for the next generation of plants. Standardization also supports repeatable, reliable performance and reduces the time and cost ...

2012-12-12T23:59:59.000Z

88

Behavioral analysis of botnets for threat intelligence  

Science Conference Proceedings (OSTI)

This paper examines the behavioral patterns of fast-flux botnets for threat intelligence. The Threat Intelligence infrastructure, which we have specifically developed for fast-flux botnet detection and monitoring, enables this analysis. Cyber criminals ... Keywords: Advanced persistent threat, Botnet, Bulletproof hosting, Cyber threat intelligence, Fast-flux, Malware, Phishing

Alper Caglayan; Mike Toothaker; Dan Drapeau; Dustin Burke; Gerry Eaton

2012-12-01T23:59:59.000Z

89

Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project  

SciTech Connect

This project characterizes typical two-phase stratified flow conditions in advanced water reactor horizontal pipe sections, following activation of passive cooling systems. It provides (1) a means to educate nuclear engineering students regarding the importance of two-phase stratified flow in passive cooling systems to the safety of advanced reactor systems and (2) describes the experimental apparatus and process to measure key parameters essential to consider when designing passive emergency core cooling flow paths that may encounter this flow regime. Based on data collected, the state of analysis capabilities can be determined regarding stratified flow in advanced reactor systems and the best paths forward can be identified to ensure that the nuclear industry can properly characterize two-phase stratified flow in passive emergency core cooling systems.

Brian G. Williams; Jim C. P. Liou; Hiral Kadakia; Bill Phoenix; Richard R. Schultz

2007-02-27T23:59:59.000Z

90

Threats analysis for e-learning  

Science Conference Proceedings (OSTI)

The purpose of this paper is to investigate and define the information security threats within an e-learning environment. A threat analysis has been conducted for each application in the managed learning environment (MLE) system used in the ... Keywords: MLEs, Microsoft, application systems, e-learning, electronic learning, host vulnerabilities, information security, managed learning environments, network vulnerability, online learning, potential threats, risk management, risk matrix, security strategies, technology enhanced learning, threat matrix, threats analysis, user awareness

Najwa Hayaati Mohd Alwi; Ip-Shing Fan

2010-10-01T23:59:59.000Z

91

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

SciTech Connect

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}.

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

2011-09-01T23:59:59.000Z

92

Hostile intelligence threat: US technology  

Science Conference Proceedings (OSTI)

This publication outlines the hostile intelligence threat to U.S. industry and Western technology, including the operational capabilities of hostile intelligence services and their scientific and technological (S T) targets. Current intelligence strategies used against the United States are described and sources of information providing countermeasures guidance are listed. Points of contact for security and counterintelligence assistance are also included.

Whitman, D.

1988-11-01T23:59:59.000Z

93

California Santa Cruz THREAT MANAGEMENT  

E-Print Network (OSTI)

University of California Santa Cruz THREAT MANAGEMENT Personal Safety Handbook UCSC Police www2 Department Safety Handbook - 15 - #12;Any supervisor, manager, or other person in authority who receives the key to maintenance or delivery people. Don't hide a key outdoors; burglars know all the hiding places

California at Santa Cruz, University of

94

Global Threat Reduction Initiative | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Threat Reduction Initiative | National Nuclear Security Threat Reduction Initiative | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Global Threat Reduction Initiative Home > About Us > Our Programs > Nonproliferation > Global Threat Reduction Initiative Global Threat Reduction Initiative The mission of the Global Threat Reduction Initiative (GTRI) is to reduce

95

Global Threat Reduction Initiative | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Threat Reduction Initiative | National Nuclear Security Threat Reduction Initiative | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Global Threat Reduction Initiative Home > About Us > Our Programs > Nonproliferation > Global Threat Reduction Initiative Global Threat Reduction Initiative The mission of the Global Threat Reduction Initiative (GTRI) is to reduce

96

Safety Basis Report  

SciTech Connect

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.

R.J. Garrett

2002-01-14T23:59:59.000Z

97

Nuclear Radiological Threat Task Force Established | National...  

NLE Websites -- All DOE Office Websites (Extended Search)

Radiological Threat Task Force Established | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

98

The New Nuclear Threat John Deutch  

E-Print Network (OSTI)

), although experts agree that Israel, Pakistan and South Africa also have a nuclear weapons capabilityThe New Nuclear Threat John Deutch FOREIGN AFFAIRS Volume 71 · Number 4 Foreign AffairsThe contents. Deutch THE NEW NUCLEAR THREAT he threat of nuclear weapons spread across the world has displaced the fear

Deutch, John

99

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

SciTech Connect

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.

George A. Beitel

2004-02-01T23:59:59.000Z

100

An approach to estimating radiological risk of offsite release from a design basis earthquake for the Process Experimental Pilot Plant (PREPP)  

SciTech Connect

In compliance with Department of Energy (DOE) Order 6430.1A, a seismic analysis was performed on DOE's Process Experimental Pilot Plant (PREPP), a facility for processing low-level and transuranic (TRU) waste. Because no hazard curves were available for the Idaho National Engineering Laboratory (INEL), DOE guidelines were used to estimate the frequency for the specified design-basis earthquake (DBE). A dynamic structural analysis of the building was performed, using the DBE parameters, followed by a probabilistic risk assessment (PRA). For the PRA, a functional organization of the facility equipment was effected so that top events for a representative event tree model could be determined. Building response spectra (calculated from the structural analysis), in conjunction with generic fragility data, were used to generate fragility curves for the PREPP equipment. Using these curves, failure probabilities for each top event were calculated. These probabilities were integrated into the event tree model, and accident sequences and respective probabilities were calculated through quantification. By combining the sequences failure probabilities with a transport analysis of the estimated airborne source term from a DBE, onsite and offsite consequences were calculated. The results of the comprehensive analysis substantiated the ability of the PREPP facility to withstand a DBE with negligible consequence (i.e., estimated release was within personnel and environmental dose guidelines). 57 refs., 19 figs., 20 tabs.

Lucero, V.; Meale, B.M.; Reny, D.A.; Brown, A.N.

1990-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

SNS backscattering spectrometer, BASIS  

Science Conference Proceedings (OSTI)

We describe the design and current performance of the backscattering silicon spectrometer (BASIS), a time-of-flight backscattering spectrometer built at the spallation neutron source (SNS) of the Oak Ridge National Laboratory (ORNL). BASIS is the first silicon-based backscattering spectrometer installed at a spallation neutron source. In addition to high intensity, it offers a high-energy resolution of about 3.5 {mu}eV and a large and variable energy transfer range. These ensure an excellent overlap with the dynamic ranges accessible at other inelastic spectrometers at the SNS.

Mamontov, Eugene [ORNL; Herwig, Kenneth W [ORNL

2011-01-01T23:59:59.000Z

102

Countering the Nuclear Terrorist Threat  

SciTech Connect

The nuclear/radioactive threat to homeland security posed by terrorists can be broken into four categories. Of highest concern is the use of an improvised nuclear device (IND). An IND, as its name implies, is a nuclear explosive device. It produces nuclear yield, and this nuclear yield has catastrophic effects. An IND is the ultimate terrorist weapon, and terrorist groups are actively attempting to acquire nuclear weapons. Detonation of an IND could dwarf the devastation of the September 11 attack on the World Trade Center. Dealing with the aftermath of an IND would be horrific. Rescue efforts and cleanup would be hazardous and difficult. Workers would have to wear full protection suits and self-contained breathing apparatus. Because of the residual radioactivity, in certain locations they could only work short times before acquiring their ''lifetime'' dose. As with the Chernobyl event, some rescue workers might well expose themselves to lethal doses of radiation, adding to the casualty toll. Enormous volumes of contaminated debris would have to be removed and disposed. If a terrorist group decides not to pursue an actual nuclear device, it might well turn to Radiological Dispersal Devices (RDDs) or ''dirty bombs'' as they are often called. RDDs spread radioactivity but they do not generate nuclear yield. The fabrication of an RDD requires radioactive material and a dispersal mechanism. Radioactive materials are used all over the world for medical, industrial, and research applications. Standards for safe handling and accountability of radioactive material vary around the world. Stories in the press suggest inadequate controls on radiological materials in parts of the world. The effects of an RDD vary widely, and are measured in terms of contamination area, health effects to the exposed population, and economic consequences. Even a negligible, but measurable, exposure would exploit the general public's fear of things radioactive and would have significant psychological consequences. The greatest impact of a small release would probably be economic, associated with cleanup and restoration of the contaminated area. Another category of threat is the attack on a facility, either a power reactor or sabotage of a large radiation source. In general these facilities are hard targets (structurally), and damage and contamination are localized. The final category of threat is the use of radioactive materials to deliver a radiation dose to individuals. This type of attack is again localized and does not readily fall into the category of a weapon of mass destruction.

Vantine, H C

2002-10-04T23:59:59.000Z

103

Decontamination of Biological Threats in Water Supplies  

Science Conference Proceedings (OSTI)

Decontamination of Biological Threats in Water Supplies. ... The availability of safe pure drinking water in the United States is taken for granted. ...

2012-10-01T23:59:59.000Z

104

A unified framework for trajectory planning, threat assessment, and semi-autonomous control of passenger vehicles  

E-Print Network (OSTI)

This thesis describes the design of an active safety framework that performs trajectory planning, threat assessment, and semi-autonomous control of passenger vehicles in hazard avoidance scenarios. The vehicle navigation ...

Anderson, Sterling J., Ph. D. Massachusetts Institute of Technology

2009-01-01T23:59:59.000Z

105

Manager, International Chemical Threat Reduction Department, Sandia  

NLE Websites -- All DOE Office Websites (Extended Search)

International Chemical Threat Reduction Department, Sandia International Chemical Threat Reduction Department, Sandia National Laboratories | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Who We Are > In The Spotlight > Nancy Jackson Manager, International Chemical Threat Reduction Department, Sandia National Laboratories

106

Manager, International Chemical Threat Reduction Department, Sandia  

National Nuclear Security Administration (NNSA)

International Chemical Threat Reduction Department, Sandia International Chemical Threat Reduction Department, Sandia National Laboratories | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Who We Are > In The Spotlight > Nancy Jackson Manager, International Chemical Threat Reduction Department, Sandia National Laboratories

107

THE BIOTERRORISM THREAT: TECHNOLOGICAL AND POLITICAL CONSIDERATIONS  

SciTech Connect

Bioterrorism--along with biowarfare, from which it may not always be distinguishable in practice--will be a feature of the strategic landscape in the 21st century and is high on the US national security agenda. Bioterrorism poses a potential threat to the US population, agriculture, interests, friends and allies, and military forces (asymmetric threats). Yet these possibilities have not been widely pursued or realized by terrorists. The perceived threat is far worse than anything experienced to date, and is largely technologically driven.

J. F. PILAT

2000-03-01T23:59:59.000Z

108

Microsoft Word - Categorizing Threat Oct10-final.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

threats, all in an unclassified venue for use by critical infrastructure providers and utility owners. One of the primary activities necessary to move classified threat information...

109

The rise of "china threat" arguments  

E-Print Network (OSTI)

The study seeks to explain the rise of "China threat" arguments in the United States and Japan in the 1990s by using three theories of states behavior- realism, organization theory, and democratic peace theory. The rise ...

Ueki, Chikako

2006-01-01T23:59:59.000Z

110

Dual generalized Bernstein basis  

Science Conference Proceedings (OSTI)

The generalized Bernstein basis in the space @P"n of polynomials of degree at most n, being an extension of the q-Bernstein basis introduced by Philips [Bernstein polynomials based on the q-integers, Ann. Numer. Math. 4 (1997) 511-518], is given by the ... Keywords: Bernstein basis, Big q-Jacobi polynomials, Discrete Bernstein basis, Dual basis, Generalized Bernstein basis, Little q-Jacobi polynomials, Shifted Jacobi polynomials, q -Bernstein basis

Stanis?aw Lewanowicz; Pawe? Wo?ny

2006-02-01T23:59:59.000Z

111

Bio-Terrorism Threat and Casualty Prevention  

SciTech Connect

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.

NOEL,WILLIAM P.

2000-01-01T23:59:59.000Z

112

The possibility of fuel cycle design for ABC/ATW complex with molten fuel on LiF-BeF2 basis  

SciTech Connect

The experience gained in the field of the development of molten salt reactors (MSR) can be made a basis of chemical processing of the ABC/ATW liquid fuel. The following combination of two processing principles are proposed for the ABC/ATW fuel (LiF-BeF2-PuF3,(4)-MAFn): -continious removal of radioactive gases, volatile impurities and 'noble fission products'; -portion-by-portion electrochemical processing with removal of rare earth elements and some other fission products at an autonomous plant. After processing the fuel salt is brought back to the blanket of the ABC/ATW complex. The analysis of information previously published in different countries allows for a safe assumption that the ABC/ATW fuel cycle with liquid fuel salt is feasible and can be demonstrated experimentally.

Naumov, V. S.; Bychkov, A. V. [Federal Scientific Center of Russia Research Institute of Atomic Reactors (RIAR) Russia, Dimitrovgrad 433510 (Russian Federation)

1995-09-15T23:59:59.000Z

113

Left-Wing Extremism: The Current Threat  

SciTech Connect

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.

Karl A. Seger

2001-04-30T23:59:59.000Z

114

Bio-Terrorism Threat and Casualty Prevention  

SciTech Connect

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.

NOEL,WILLIAM P.

2000-01-01T23:59:59.000Z

115

IBM Internet Security Systems Threat Insight Monthly  

E-Print Network (OSTI)

. http://docs.info.apple.com/article.html?artnum=303411 BEA Systems - 2007 Daylight Savings Time ChangesIBM Internet Security Systems X-Force ® Threat Insight Monthly www.iss.netwww.iss.net February 2007 Shellcode Heuristics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 The 2007 Daylight

116

Use of the TRUEX process for the pretreatment of neutralized cladding removal waste (NCRW) sludge: Results of a design basis experiment  

SciTech Connect

This report presents the results of an experiment designed to demonstrate the feasibility of a sludge dissolution/solvent extraction process to separate transuranic elements from the bulk components of Hanford neutralized cladding removal waste (NCRW) sludge. Such a separation would allow the bulk of the waste to be disposed of as low-level waste, which is much less costly than geologic disposal as would be required for the waste in its current form. The results indicate that the proposed process is well suited to meet the desired objectives. A composite sample of NCRW sludge taken from Tank 103-AW in 1986 was dissolved in nitric acid at room temperature. Dissolution of bulk components and all radionuclides was {ge}95% complete; thus, {le}5% of the bulk components will require geologic disposal. The TRUEX (TRansUranium EXtraction) solvent extraction process gave very good separation of the transuranic from the bulk components of the waste.

Swanson, J L

1991-07-01T23:59:59.000Z

117

lattice basis - CECM  

E-Print Network (OSTI)

Discover an identity using lattice basis reduction. Find integers a and b such that a*Zeta(50)+b*Pi^50 = 0 using lattice basis reduction . First try using quadruple...

118

NIST Official Testifies on Threat Detection Science for National ...  

Science Conference Proceedings (OSTI)

NIST Official Testifies on Threat Detection Science for National Security. From NIST Tech Beat: July 25, 2012. ...

2012-07-25T23:59:59.000Z

119

GTRI: Reducing Nuclear Threats | National Nuclear Security Administrat...  

NLE Websites -- All DOE Office Websites (Extended Search)

Reducing Nuclear Threats | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

120

Office of Global Threat Reduction | National Nuclear Security...  

NLE Websites -- All DOE Office Websites (Extended Search)

Global Threat Reduction | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Nonproliferation, Nuclear Security, and the Insider Threat  

SciTech Connect

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.

Balatsky, Galya I. [Los Alamos National Laboratory; Duggan, Ruth [SNL

2012-07-12T23:59:59.000Z

122

The Atlantic Forest of South America: Biodiversity Status, Threats, and Outlook  

E-Print Network (OSTI)

Status, Threats, and Outlook By Carlos Galindo-Leal andStatus, Threats, and Outlook. (Center for Appliedstatus, threats, and outlook. The book begins with a

Sayre, Don

2003-01-01T23:59:59.000Z

123

NNSA Launches Global Threat Reduction Initiative | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Global Threat Reduction Initiative | National Nuclear Global Threat Reduction Initiative | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > NNSA Launches Global Threat Reduction Initiative NNSA Launches Global Threat Reduction Initiative May 26, 2004 Vienna, Austria NNSA Launches Global Threat Reduction Initiative

124

Office of Nuclear Threat Science | National Nuclear Security Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Threat Science | National Nuclear Security Administration Nuclear Threat Science | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Office of Nuclear Threat Science Home > About Us > Our Programs > Counterterrorism and Counterproliferation > Office of Nuclear Threat Science Office of Nuclear Threat Science

125

Office of Nuclear Threat Science | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Threat Science | National Nuclear Security Administration Threat Science | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Office of Nuclear Threat Science Home > About Us > Our Programs > Counterterrorism and Counterproliferation > Office of Nuclear Threat Science Office of Nuclear Threat Science

126

NNSA Launches Global Threat Reduction Initiative | National Nuclear  

National Nuclear Security Administration (NNSA)

Global Threat Reduction Initiative | National Nuclear Global Threat Reduction Initiative | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > NNSA Launches Global Threat Reduction Initiative NNSA Launches Global Threat Reduction Initiative May 26, 2004 Vienna, Austria NNSA Launches Global Threat Reduction Initiative

127

Dynamic Customer Energy Systems Design Basis  

Science Conference Proceedings (OSTI)

Developing a common communications language for integrating consumer appliances as well as heating, ventilation, and air conditioning (HVAC) equipment is a precondition for massively scaling dynamic customer energy systems capable of demand response and other new functions. This report assesses the status of work on creating such a language and makes recommendations for integrating, extending and harmonizing these efforts.

2008-01-14T23:59:59.000Z

128

3.System Design Basis 2) MODELING  

E-Print Network (OSTI)

-0012) Vendor Prints 2) All equipments are modelled using the standard HYSYS unit operation models. 3) Butane BOG compressors with butane storage system is modelled for this report. 4) Modelling have been streams and out streams specifications for the butane storage tanks(T-1/2/3/4) with Butane BOG compressor

Hong, Deog Ki

129

Microsoft Word - design_basis_sienicki.doc  

NLE Websites -- All DOE Office Websites (Extended Search)

SAM Developed Following the accident at Chornobyl in the Soviet Union in 1986, Severe Accident Management (SAM) was developed for all nuclear power plants in the U.S. in an...

130

Nuclear Facility Safety Basis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Basis Safety Basis FUNCTIONAL AREA GOAL: A fully compliant Nuclear Facility Safety Basis. Program is implemented and maintained across the site. REQUIREMENTS:  10 CFR 830 Subpart B Guidance:  DOE STD 3009  DOE STD 1104  DOE STD  DOE G 421.1-2 Implementation Guide For Use in Developing Documented Safety Analyses To Meet Subpart B Of 10 CFR 830  DOE G 423.1-1 Implementation Guide For Use In Developing Technical Safety Requirements  DOE G 424.1-1 Implementation Guide For Use In Addressing Unreviewed Safety Question Requirements Performance Objective 1: Contractor Program Documentation The site contractor has developed an up-to-date, comprehensive, compliant, documented nuclear facility safety basis and associated implementing mechanisms and procedures for all required nuclear facilities and activities (10 CFR

131

JM to Develop DOE O 470.X, Insider Threat Program  

Directives, Delegations, and Requirements

The Order establishes top-level responsibilities and requirements for DOE's Insider Threat Program, which is intended to deter, detect, and mitigate insider ...

2013-10-17T23:59:59.000Z

132

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

133

Responding to WMD Terrorism Threats: The Role of Insurance Markets  

E-Print Network (OSTI)

Threat: Lessons From Nuclear Reactor Accidents A nuclearbomb. 2) An attack on a nuclear reactor, also with the goalHowever, approximately 443 nuclear reactors exist worldwide,

Jaffee, Dwight M.; Russell, Thomas

2007-01-01T23:59:59.000Z

134

Insider Threat to Nuclear and Radiological Materials: Fact Sheet...  

NLE Websites -- All DOE Office Websites (Extended Search)

Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the...

135

Design  

NLE Websites -- All DOE Office Websites (Extended Search)

Design Design of a Multithreaded Barnes-Hut Algorithm for Multicore Clusters Technical Report Junchao Zhang and Babak Behzad Department of Computer Science, University of Illinois at Urbana-Champaign {jczhang, bbehza2}@illinois.edu Marc Snir Department of Computer Science, University of Illinois at Urbana-Champaign and MCS Division, Argonne National Laboratory snir@anl.gov Abstract We describe in this paper an implementation of the Barnes-Hut al- gorithm on multicore clusters. Based on a partitioned global ad- dress space (PGAS) library, the design integrates intranode mul- tithreading and internode one-sided communication, exemplifying a PGAS + X programming style. Within a node, the computation is decomposed into tasks (subtasks), and multitasking is used to hide network latency. We study the tradeoffs between locality in private caches and locality in shared caches

136

Using Author Topic to detect insider threats from email traffic  

Science Conference Proceedings (OSTI)

One means of preventing insider theft is by stopping potential insiders from becoming actual thieves. This article discusses an approach to assist managers in identifying potential insider threats. By using the Author Topic [Rosen-Zvi Michal, Griffiths ... Keywords: Author Topic (AT), Datamining, Insider threat, Large data set, Social networks

James S. Okolica; Gilbert L. Peterson; Robert F. Mills

2007-09-01T23:59:59.000Z

137

Global Threat Reduction Initiative | Y-12 National Security Complex  

NLE Websites -- All DOE Office Websites (Extended Search)

Global Threat Reduction Global Threat Reduction ... Global Threat Reduction Initiative The Global Threat Reduction Initiative's Alarm Response Training provides training in the area of response for radiological events and provides an opportunity for the security forces, health and safety personnel, and other responsible parties such as the supporting local law enforcement to develop, discuss, and exercise their own tactics, techniques, procedures, and protocols when responding to a theft and/or sabotage event involving radioactive materials of significance. This voluntary program is free, and all expenses (travel, meals, etc.), other than the trainee's training time, will be paid by the GTRI Domestic Threat Reduction Program. Facilities participating in the Domestic Security Program are scheduled for

138

GTRI: Reducing Nuclear Threats | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Reducing Nuclear Threats | National Nuclear Security Administration Reducing Nuclear Threats | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > GTRI: Reducing Nuclear Threats Fact Sheet GTRI: Reducing Nuclear Threats Apr 12, 2013 Mission In 2004, NNSA established the Global Threat Reduction Initiative (GTRI) in the Office of Defense Nuclear Nonproliferation to, as quickly as possible,

139

Before the House Subcommittee on Emerging Threats, Cyber Security and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Emerging Threats, Cyber Security Emerging Threats, Cyber Security and Science and Technology Committee on Homeland Security Before the House Subcommittee on Emerging Threats, Cyber Security and Science and Technology Committee on Homeland Security Before the House Subcommittee on Emerging Threats, Cyber Security and Science and Technology Committee on Homeland Security By: Patricia Hoffman, Acting Assistant Secretary for Electricity Delivery and Energy Reliability 7-21-09_Final_Testimony_Hoffman.pdf More Documents & Publications 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, Before the House Science and Technology Subcommittee on Energy and

140

Nuclear Radiological Threat Task Force Established | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Radiological Threat Task Force Established | National Nuclear Radiological Threat Task Force Established | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Nuclear Radiological Threat Task Force Established Nuclear Radiological Threat Task Force Established November 03, 2003 Washington, DC Nuclear Radiological Threat Task Force Established

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Radioactive Waste Management Basis  

SciTech Connect

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.

Perkins, B K

2009-06-03T23:59:59.000Z

142

Global threat reduction initiative Russian nuclear material removal progress  

SciTech Connect

In December 1999 representatives from the United States, the Russian Federation, and the International Atomic Energy Agency (IAEA) started discussing a program to return to Russia Soviet- or Russian-supplied highly enriched uranium (HEU) fuel stored at the Russian-designed research reactors outside Russia. Trilateral discussions among the United States, Russian Federation, and the International Atomic Energy Agency (IAEA) have identified more than 20 research reactors in 17 countries that have Soviet- or Russian-supplied HEU fuel. The Global Threat Reduction Initiative's Russian Research Reactor Fuel Return Program is an important aspect of the U.S. Government's commitment to cooperate with the other nations to prevent the proliferation of nuclear weapons and weapons-usable proliferation-attractive nuclear materials. To date, 496 kilograms of Russian-origin HEU have been shipped to Russia from Serbia, Latvia, Libya, Uzbekistan, Romania, Bulgaria, Poland, Germany, and the Czech Republic. The pilot spent fuel shipment from Uzbekistan to Russia was completed in April 2006. (author)

Cummins, Kelly [DOE/NNSA (United States); Bolshinsky, Igor [INL/NNSA (United States)

2008-07-15T23:59:59.000Z

143

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

National Nuclear Security Administration (NNSA)

Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Insider Threat to Nuclear and Radiological Materials: ... Fact Sheet Insider Threat to Nuclear and Radiological Materials: Fact Sheet

144

V-220: Juniper Security Threat Response Manager Lets Remote Authenticated  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0: Juniper Security Threat Response Manager Lets Remote 0: Juniper Security Threat Response Manager Lets Remote Authenticated Users Execute Arbitrary Commands V-220: Juniper Security Threat Response Manager Lets Remote Authenticated Users Execute Arbitrary Commands August 17, 2013 - 4:01am Addthis PROBLEM: A remote authenticated user can execute arbitrary commands on the target system. PLATFORM: 2010.0, 2012.0, 2012.1, 2013.1 ABSTRACT: A vulnerability was reported in Juniper Security Threat Response Manager (STRM) REFERENCE LINKS: SecurityTracker Alert ID: 1028921 CVE-2013-2970 IMPACT ASSESSMENT: High DISCUSSION: A remote authenticated user can inject commands to execute arbitrary operating system commands with the privileges of the target web service. This can be exploited to gain shell access on the target device.

145

The optimization of situational awareness for insider threat detection  

Science Conference Proceedings (OSTI)

In recent years, organizations ranging from defense and other government institutions to commercial enterprises, research labs, etc., have witnessed an increasing amount of sophisticated insider attacks that manage to bypass existing security controls. ... Keywords: data exfiltration, insider threat

Kenneth Brancik; Gabriel Ghinita

2011-02-01T23:59:59.000Z

146

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

National Nuclear Security Administration (NNSA)

food items and household goods, that was donated to local food banks for direct distribution to those in need in the D.C. area. NNSA's Global Threat Reduction Initiative...

147

EM threat analysis for wireless systems.  

SciTech Connect

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.

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)

2006-06-01T23:59:59.000Z

148

NNSA's Global Threat Reduction Initiative food face-off | National  

NLE Websites -- All DOE Office Websites (Extended Search)

food face-off | National food face-off | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > NNSA's Global Threat Reduction Initiative food face-off NNSA's Global Threat Reduction Initiative food face-off Posted By Office of Public Affairs NNSA's Global Threat Reduction Initiative holds a Feds Feeds Family face-off

149

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Protecting the Nation's Electric Grid from Cyber Threats Protecting the Nation's Electric Grid from Cyber Threats Protecting the Nation's Electric Grid from Cyber Threats January 11, 2012 - 11:28am Addthis A smarter, modernized, and more secure grid will be pivotal to the United States’ world leadership in a clean energy future. | Photo courtesy of National Renewable Energy Laboratory. A smarter, modernized, and more secure grid will be pivotal to the United States' world leadership in a clean energy future. | Photo courtesy of National Renewable Energy Laboratory. Howard A. Schmidt White House Cybersecurity Coordinator Secretary Steven Chu: "Establishing a comprehensive cybersecurity approach will give utility companies and grid operators another important tool to improve the grid's ability to respond to cybersecurity risks."

150

NNSA's Global Threat Reduction Initiative launches mobile app | National  

National Nuclear Security Administration (NNSA)

launches mobile app | National launches mobile app | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > NNSA's Global Threat Reduction Initiative launches mobile app NNSA's Global Threat Reduction Initiative launches mobile app Posted By Office of Public Affairs NNSA's Global Threat Reduction Initiative (GTRI) recently launched a

151

What is an Asset-Based Threat Profile?...............................................................4  

E-Print Network (OSTI)

Threats to information technology are ever increasing and many organizations are spending much money and time in attempting to fix security problems. Before one can think about remediation, assets worth protecting and knowing what to protect those assets from must be defined. OCTAVE characterizes a self-directed methodology for defining an organizations assets and the assets risks. Critical to OCTAVE are the tools and processes toward developing assetbased threat profiles. The threat profile includes network risks, also known as vulnerabilities that often times analysis team members are not qualified to assess. Vulnerability assessment tools aid the OCTAVE analysis team to determine exactly what network-aware technological risks face any certain asset and often times help to further define the asset itself. By applying the results of a vulnerability assessment to an OCTAVE Risk Profile, many unanswered questions pertaining to the asset and its risks are fulfilled in an autonomous and

Andrew Storms

2003-01-01T23:59:59.000Z

152

NNSA's Global Threat Reduction Initiative Receives 2010 Distinguished  

NLE Websites -- All DOE Office Websites (Extended Search)

Receives 2010 Distinguished Receives 2010 Distinguished Project Award from PMI | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > NNSA's Global Threat Reduction Initiative Receives 2010 ... Press Release NNSA's Global Threat Reduction Initiative Receives 2010 Distinguished

153

A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats  

Science Conference Proceedings (OSTI)

This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the range of possibilities. Once an object is generated, its radiation signature is calculated using a 1-dimensional deterministic transport code. Objects that do not make sense based on physics principles or other constraints are rejected. Thus, the model can be used to generate a population of spectral signatures that spans a large space, including smuggled nuclear material and nuclear weapons.

Nelson, K; Sokkappa, P

2008-10-29T23:59:59.000Z

154

Ontological semantic technology for detecting insider threat and social engineering  

Science Conference Proceedings (OSTI)

This paper describes a computational system for detecting unintentional inferences in casual unsolicited and unrestricted verbal output of individuals, potentially responsible for leaked classified information to people with unauthorized access. Uses ... Keywords: default override, insider threat, natural language information assurance and security, ontological semantic technology, social engineering, unintended inference

Victor Raskin; Julia M. Taylor; Christian F. Hempelmann

2010-09-01T23:59:59.000Z

155

Review: TCP/IP security threats and attack methods  

Science Conference Proceedings (OSTI)

The TCP/IP protocol suite is vulnerable to a variety of attacks ranging from password sniffing to denial of service. Software to carry out most of these attacks is freely available on the Internet. These vulnerabilities-unless carefully controlled-can ... Keywords: IP spoofing, Ping O' Death, SYN flooding, TCP sequence number attack, TCP session hijacking, TCP/IP service threats

B. Harris; R. Hunt

1999-06-01T23:59:59.000Z

156

Security and privacy threats in IoT architectures  

Science Conference Proceedings (OSTI)

In this paper, we describe developments towards the Internet of Things (IoT) and discuss architecture visions for the IoT. Our emphasis is to analyze the known and new threats for the security, privacy and trust (SPT) at different levels of architecture. ... Keywords: IoT architecture, energy consumption, future internet, privacy, security, trust

Denis Kozlov; Jari Veijalainen; Yasir Ali

2012-02-01T23:59:59.000Z

157

Sensor Resource Management driven by threat projection and priorities  

Science Conference Proceedings (OSTI)

This paper extends previous Sensor Resource Management (SRM) work by addressing information flow from sensor inputs to SRM, through four levels of the US DoD's Joint Directors of Laboratories (JDL) sensor fusion model. The method flexibly adapts to several ... Keywords: Prioritization, Radar, Sensor Resource Management, Situation Calculus, Threat projection

Joseph Anderson; Lang Hong

2008-04-01T23:59:59.000Z

158

Climate Threat to the Planet:* Implications for Energy Policy  

E-Print Network (OSTI)

Climate Threat to the Planet:* Implications for Energy Policy and Intergenerational Justice Jim Policy-Related Statements are Personal Opinion I changed the title of my talk. Global warming has implications for energy policy and intergenerational justice. The propriety of a scientist discussing

Hansen, James E.

159

Climate Threat to the Planet * Implications for Energy Policy  

E-Print Network (OSTI)

Climate Threat to the Planet * Implications for Energy Policy Jim Hansen 3 June 2008 PACON International Honolulu, Hawaii *Any statements relating to policy are personal opinion #12;Global Warming Status Definitions 1. Tipping Level - Climate forcing (greenhouse gas amount) reaches a point such that no additional

Hansen, James E.

160

Forecasting Lightning Threat Using Cloud-Resolving Model Simulations  

Science Conference Proceedings (OSTI)

Two new approaches are proposed and developed for making time- and space-dependent, quantitative short-term forecasts of lightning threats, and a blend of these approaches is devised that capitalizes on the strengths of each. The new methods are ...

Eugene W. McCaul Jr.; Steven J. Goodman; Katherine M. LaCasse; Daniel J. Cecil

2009-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Mixtures of truncated basis functions  

Science Conference Proceedings (OSTI)

In this paper we propose a framework, called mixtures of truncated basis functions (MoTBFs), for representing general hybrid Bayesian networks. The proposed framework generalizes both the mixture of truncated exponentials (MTEs) framework and the Mixture ... Keywords: Approximations, Hybrid Bayesian networks, Inference, Mixtures of truncated basis functions, Mixtures of truncated exponentials

Helge Langseth; Thomas D. Nielsen; Rafael Rum?; Antonio Salmern

2012-02-01T23:59:59.000Z

162

DDE Design Status Report Nov 2011  

Science Conference Proceedings (OSTI)

The National Nuclear Security Agency Global Threat Reduction Initiative employs the Reduced Enrichment for Research and Test Reactors (RERTR) Fuel Development program to facilitate maturation of Low Enriched Uranium (LEU) fuel technology in order to enable conversion of High Power Research Reactors (HPRR) to LEU fuels. The RERTR Fuel Development program has overseen design, fabrication, irradiation, and examination of numerous tests on small to medium sized specimens containing LEU fuels. To enable the three nearest term HPRR conversions, including the Massachusetts Institutes of Technology Reactor (MITR), University of Missouri Research Reactor (MURR), and National Bureau of Standard Reactor (NBSR), the FD pillar is currently focused on qualification of the 'Base Monolithic Design'. The Base Monolithic Design consists of uranium-10 wt% molybdenum alloy (U-10Mo) in the form of a monolithic foil, with thin zirconium interlayers, clad in aluminum by hot isostatic press. The licensing basis of the aforementioned HPRR's restricts them from testing lead test elements of their respective LEU fuel element designs. In order to provide the equivalent of a lead test assembly, one Design Demonstration Experiment (DDE) is planned for each of the three NRC licensed reactors.

N.E. Woolstenhulme; R.B. Nielson

2011-11-01T23:59:59.000Z

163

Mobility changes anonymity: new passive threats in mobile ad hoc networks  

E-Print Network (OSTI)

Mobility Changes Anonymity: New Passive Threats in Mobile AdThese new aspects are all introduced by mobility and leftThese new threats are all introduced by mobility and are

Hong, Xiaoyan; Kong, Jiejun; Gerla, Mario

2006-01-01T23:59:59.000Z

164

A threat-rigidity analysis of the Apache Software Foundation's response to reported server security issues  

E-Print Network (OSTI)

There exists a broad body of literature documenting organizational responses to competitive threats, including those responses which fit into the threat-rigidity hypothesis. The purpose of this thesis is to investigate how ...

Shapira, Yoav

2006-01-01T23:59:59.000Z

165

NNSA's Global Threat Reduction Initiative Completes First Plutonium  

NLE Websites -- All DOE Office Websites (Extended Search)

Completes First Plutonium Completes First Plutonium Shipment | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > NNSA's Global Threat Reduction Initiative Completes First ... NNSA's Global Threat Reduction Initiative Completes First Plutonium Shipment Posted By NNSA Public Affairs NNSA Blog The United States and Sweden announced today at the 2012 Nuclear Security

166

NNSA's Global Threat Reduction Initiative Completes First Plutonium  

National Nuclear Security Administration (NNSA)

Completes First Plutonium Completes First Plutonium Shipment | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > NNSA's Global Threat Reduction Initiative Completes First ... NNSA's Global Threat Reduction Initiative Completes First Plutonium Shipment Posted By NNSA Public Affairs NNSA Blog The United States and Sweden announced today at the 2012 Nuclear Security

167

Optimal ratio between phase basis and bit basis in QKD  

E-Print Network (OSTI)

In the original BB84 protocol, we use the bit basis and the phase basis with the equal probability. Lo et al (J. of Cryptology, 18, 133-165 (2005)) proposed to modify the ratio between two bases for increasing the final key generation rate in the asymptotic setting. In the present letter, in order to treat this problem the non-asymptotic setting, we optimize the ratio between the two bases with exponential constraints for Eve's information distinguishability and the final error probability.

Hayashi, Masahito

2008-01-01T23:59:59.000Z

168

Facility worker technical basis document  

SciTech Connect

This report documents the technical basis for facility worker safety to support the Tank Farms Documented Safety Analysis and described the criteria and methodology for allocating controls to hazardous conditions with significant facility worker consequences and presents the results of the allocation.

EVANS, C.B.

2003-03-21T23:59:59.000Z

169

FACILITY WORKER TECHNICAL BASIS DOCUMENT  

Science Conference Proceedings (OSTI)

This technical basis document was developed to support RPP-13033, ''Tank Farms Documented Safety Analysis (DSA). It describes the criteria and methodology for allocating controls to hazardous conditions with significant facility worker (FW) consequence and presents the results of the allocation. The criteria and methodology for identifying controls that address FW safety are in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''.

SHULTZ, M.V.

2005-03-31T23:59:59.000Z

170

Hanford Generic Interim Safety Basis  

SciTech Connect

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.

Lavender, J.C.

1994-09-09T23:59:59.000Z

171

TCAP Aluminium Dissolution Flowsheet Basis  

Science Conference Proceedings (OSTI)

The Actinide Technology Section has proposed the use of an nitric acid HNO3 and potassium fluoride KF flowsheet for stripping palladium Pd from palladium-coated kieselguhr Pd/K and removing aluminum (Al) metal foam from the TCAP coils. The basis for the HNO3-KF flowsheet is drawn from many sources. A brief review of the sources will be presented. The basic flowsheet involves three process steps, each with its own chemistry.

PIERCE, ROBERTA.

2004-03-01T23:59:59.000Z

172

Neutron Interrogation System For Underwater Threat Detection And Identification  

Science Conference Proceedings (OSTI)

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.

Barzilov, Alexander P.; Novikov, Ivan S.; Womble, Phil C. [Department of Physics and Astronomy, Western Kentucky University, 1906 College Heights Blvd, 11077 Bowling Green, KY 42101 (United States)

2009-03-10T23:59:59.000Z

173

Anomaly Detection in Multiple Scale for Insider Threat Analysis  

Science Conference Proceedings (OSTI)

We propose a method to quantify malicious insider activity with statistical and graph-based analysis aided with semantic scoring rules. Different types of personal activities or interactions are monitored to form a set of directed weighted graphs. The semantic scoring rules assign higher scores for the events more significant and suspicious. Then we build personal activity profiles in the form of score tables. Profiles are created in multiple scales where the low level profiles are aggregated toward more stable higherlevel profiles within the subject or object hierarchy. Further, the profiles are created in different time scales such as day, week, or month. During operation, the insider s current activity profile is compared to the historical profiles to produce an anomaly score. For each subject with a high anomaly score, a subgraph of connected subjects is extracted to look for any related score movement. Finally the subjects are ranked by their anomaly scores to help the analysts focus on high-scored subjects. The threat-ranking component supports the interaction between the User Dashboard and the Insider Threat Knowledge Base portal. The portal includes a repository for historical results, i.e., adjudicated cases containing all of the information first presented to the user and including any additional insights to help the analysts. In this paper we show the framework of the proposed system and the operational algorithms.

Kim, Yoohwan [ORNL; Sheldon, Frederick T [ORNL; Hively, Lee M [ORNL

2012-01-01T23:59:59.000Z

174

Molecular Design Basis for Hydrogen Storage in Clathrate Hydrates  

DOE Green Energy (OSTI)

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

John, Vijay T [Tulane University; McPherson, Gary L [Tulane University; Ashbaugh, Hank [Tulane University; Johnes, Camille Y [Columbia University

2013-06-28T23:59:59.000Z

175

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

Science Conference Proceedings (OSTI)

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.

Primm, Trent [ORNL; Guida, Tracey [University of Pittsburgh

2010-02-01T23:59:59.000Z

176

Because It's Not There: Verbal Visuality and the Threat of Graphics in Interactive Fiction  

E-Print Network (OSTI)

of the power of computer graphics, text still has access tothat are unavailable in graphics including visual effects.Visuality and the Threat of Graphics in Interactive Fiction

Kashtan, Aaron

2009-01-01T23:59:59.000Z

177

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

NLE Websites -- All DOE Office Websites (Extended Search)

fear and confusion as officials grapple with the added complexity of a radiological emergency response. To help agencies prepare to manage such a threat, ORISE assisted the...

178

Authorization basis supporting documentation for plutonium finishing plant  

Science Conference Proceedings (OSTI)

The identification and definition of the authorization basis for the Plutonium Finishing Plant (PFP) facility and operations are essential for compliance to DOE Order 5480.21, Unreviewed Safety Questions. The authorization basis, as defined in the Order, consists of those aspects of the facility design basis, i.e., the structures, systems and components (SSCS) and the operational requirements that are considered to be important to the safety of operations and are relied upon by DOE to authorize operation of the facility. These facility design features and their function in various accident scenarios are described in WHC-SD-CP-SAR-021, Plutonium Finishing Plant Final Safety Analysis Report (FSAR), Chapter 9, `Accident Analysis.` Figure 1 depicts the relationship of the Authorization Basis to its components and other information contained in safety documentation supporting the Authorization Basis. The PFP SSCs that are important to safety, collectively referred to as the `Safety Envelope` are discussed in various chapters of the FSAR and in WHC-SD-CP-OSR-010, Plutonium Finishing Plant Operational Safety Requirements. Other documents such as Criticality Safety Evaluation Reports (CSERS) address and support some portions of the Authorization Basis and Safety Envelope.

King, J.P., Fluor Daniel Hanford

1997-03-05T23:59:59.000Z

179

BASIS Equipment | ORNL Neutron Sciences  

NLE Websites -- All DOE Office Websites (Extended Search)

Equipment Equipment BASIS Schematic Schematic of the SNS Backscattering Spectrometer. Helium dewer cooling a sample Helium dewer cooling a sample (bird's eye view). The heart of the work in a typical experiment is setting up the sample in the desired environment. A typical neutron sample ranging from a millimeter to a few centimeters is placed in a specialized cylindrical can and sealed. For liquids, the backscattering instrument often uses an annular can, created by placing a smaller can within a larger can and inserting the liquid sample between the two cans. This picture shows a helium dewer cooling the environment encompassing the sample can, which has been lowered into the beam from the top of the scattering tank. Crystals Crystals. The backscattering spectrometer is defined by the reflection of specific

180

Internal dosimetry technical basis manual  

Science Conference Proceedings (OSTI)

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.

Not Available

1990-12-20T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Cluster Analysis-Based Approaches for Geospatiotemporal Data Mining of Massive Data Sets for Identification of Forest Threats  

SciTech Connect

We investigate methods for geospatiotemporal data mining of multi-year land surface phenology data (250 m2 Normalized Difference Vegetation Index (NDVI) values derived from the Moderate Resolution Imaging Spectrometer (MODIS) in this study) for the conterminous United States (CONUS) as part of an early warning system for detecting threats to forest ecosystems. The approaches explored here are based on k-means cluster analysis of this massive data set, which provides a basis for defining the bounds of the expected or normal phenological patterns that indicate healthy vegetation at a given geographic location. We briefly describe the computational approaches we have used to make cluster analysis of such massive data sets feasible, describe approaches we have explored for distinguishing between normal and abnormal phenology, and present some examples in which we have applied these approaches to identify various forest disturbances in the CONUS.

Mills, Richard T [ORNL; Hoffman, Forrest M [ORNL; Kumar, Jitendra [ORNL; HargroveJr., William Walter [USDA Forest Service

2011-01-01T23:59:59.000Z

182

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

DOE Data Explorer (OSTI)

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)

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

183

A methodology and supporting techniques for the quantitative assessment of insider threats  

Science Conference Proceedings (OSTI)

Security is a major challenge for today's companies, especially ICT ones which manages large scale cyber-critical systems. Amongst the multitude of attacks and threats to which a system is potentially exposed, there are insiders attackers i.e., users ... Keywords: attack path, insider threats, risk assessment, security

Nicola Nostro, Andrea Ceccarelli, Andrea Bondavalli, Francesco Brancati

2013-09-01T23:59:59.000Z

184

An evaluation of potential solar radio emission power threat on GPS and GLONASS performance  

Science Conference Proceedings (OSTI)

The L-band solar radio emission has recently been regarded as a potential threat to stable GPS and GLONASS performance. However, the threat has not been completely investigated or assessed so far. We evaluate in detail the occurrence of GPS/GLONASS signal ... Keywords: GLONASS performance, GPS, Solar flares, Solar radio emission

Vladislav V. Demyanov; Edward L. Afraimovich; Shuanggen Jin

2012-10-01T23:59:59.000Z

185

A behavioral theory of insider-threat risks: A system dynamics approach  

Science Conference Proceedings (OSTI)

The authors describe a behavioral theory of the dynamics of insider-threat risks. Drawing on data related to information technology security violations and on a case study created to explain the dynamics observed in that data, the authors constructed ... Keywords: Insider threat, behavioral theory, judgment and decision making, policy analysis, risk, security modeling, signal detection theory, system dynamics modeling

Ignacio J. Martinez-Moyano; Eliot Rich; Stephen Conrad; David F. Andersen; Thomas R. Stewart

2008-04-01T23:59:59.000Z

186

Existing reactor expansion study basis  

SciTech Connect

The latest HAPO Five Year Program review, HW-59633, forecasts substantial increases in Pu production from the eight existing Hanford reactors over the next several years. These production increases would be attained by a combination of several methods which include increased reactor power levels resulting from higher process water flow rates and coolant bulk outlet temperatures, improved time operated efficiency, higher conversion ratios, and reduced transient reactivity losses. In order to provide a realistic basis for budgeting to meet these or other increased production goals, it is necessary that a study program be undertaken to determine in general terms the plant changes required to support these forecasted levels, to evaluate the economic and technical feasibility of achieving the process conditions, and to present an integrated program for achieving these objectives. This study program will necessarily consider the interrelated effects of a number of various facets of reactor and water plant process conditions, operational requirements, and proposed development programs. The purpose of this document is to present a plan for the execution of the proposed study. Included in this outline are a review of the basic study considerations, problem assignments and schedules, and manpower and cost estimates for the performance of the study.

Heacock, H.W.

1959-06-24T23:59:59.000Z

187

Advanced Fuel Cycle Cost Basis  

SciTech Connect

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 modules23 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.

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

2008-03-01T23:59:59.000Z

188

Advanced Fuel Cycle Cost Basis  

SciTech Connect

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 modules24 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.

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

2007-04-01T23:59:59.000Z

189

Advanced Fuel Cycle Cost Basis  

SciTech Connect

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 modules23 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.

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

2009-12-01T23:59:59.000Z

190

Basis of conversion factors for energy equivalents  

Science Conference Proceedings (OSTI)

... Basis of conversion factors for energy equivalents Conversion factors for energy equivalents are derived from the following relations: ...

191

Insider Threat - Material Control and Accountability Mitigation (Presentation)  

SciTech Connect

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.

Powell, Danny H [ORNL; Elwood Jr, Robert H [ORNL

2011-01-01T23:59:59.000Z

192

Generalized multiscale radial basis function networks  

Science Conference Proceedings (OSTI)

A novel modelling framework is proposed for constructing parsimonious and flexible multiscale radial basis function networks (RBF). Unlike a conventional standard single scale RBF network, where all the basis functions have a common kernel width, the ... Keywords: Model term selection, Neural networks, Nonlinear system identification, Orthogonal least squares, Radial basis functions

Stephen A. Billings; Hua-Liang Wei; Michael A. Balikhin

2007-12-01T23:59:59.000Z

193

Integrating Safeguards and Security with Safety into Design  

Science Conference Proceedings (OSTI)

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

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

2009-05-01T23:59:59.000Z

194

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Detection and Analysis of Threats 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 traffic. But existing IDS, often not tailored to the control environment, typically offer limited attack response capability and frequently produce false alarms or fail to alert. Without carefully deployed monitoring, these devices can produce an overwhelming number of alarms

195

Microsoft Forefront Threat Management Gateway (TMG) Administrator's Companion, 1st edition  

Science Conference Proceedings (OSTI)

Get your Web security, network perimeter security, and application layer security gateway up and running smoothly. This indispensible, single-volume reference details the features and capabilities of Microsoft Forefront Threat Management Gateway (TMG). ...

Jim Harrison; Yuri Diogenes; Mohit Saxena

2010-02-01T23:59:59.000Z

196

Consequences of Sprawl: Threats to California's Natural Environment and Human Health  

E-Print Network (OSTI)

threats both on land and at sea. Aquatic pollution. Degradeddeterminants of ozone pollution. Land use patterns affectLand Management37 Align Infrastructure Investment with Long-Term Objectives..38 Promote Pollution

Goldman, Todd

2001-01-01T23:59:59.000Z

197

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Global Threat Reduction 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 (Mo-99) is used in the production of technetium-99m (Tc-99m), the most commonly used medical radioisotope in the world. The United States accounts for approximately half of the global demand for Mo-99 at approximately 6,000 units per week. Because Mo-99's short half-life of 66 hours prevents it from being stockpiled, consistent

198

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

NLE Websites -- All DOE Office Websites (Extended Search)

Detecting Nuclear Threats Detecting Nuclear Threats Stories of Discovery & Innovation Detecting Nuclear Threats Enlarge Photo Photo: Denise Applewhite The MINDS device was invented by a team of engineers at the Princeton Plasma Physics Laboratory, including, from left: Kenny Silber, Henry Carnevale, Charles Gentile, Dana Mastrovito, and Bill Davis. Enlarge Photo 03.28.11 Detecting Nuclear Threats Plasma physics challenge yields portable nuclear detector for homeland security. In 1999, faced with the task of decommissioning the legendary Tokamak Fusion Test Reactor (TFTR), officials at the U.S. Department of Energy's Princeton Plasma Physics Laboratory (PPPL) realized they needed something that didn't yet exist-a non-destructive, real time device to detect certain "hot" elements lacing the inner vessel of the doughnut-

199

Toward High-Resolution, Rapid, Probabilistic Forecasting of the Inundation Threat from Landfalling Hurricanes  

Science Conference Proceedings (OSTI)

State-of-the-art coupled hydrodynamic and wave models can predict the inundation threat from an approaching hurricane with high resolution and accuracy. However, these models are not highly efficient and often cannot be run sufficiently fast to ...

Andrew J. Condon; Y. Peter Sheng; Vladimir A. Paramygin

2013-04-01T23:59:59.000Z

200

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

SciTech Connect

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.

Cohen, Israel Dov; Mengesha, Wondwosen

2011-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

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

Science Conference Proceedings (OSTI)

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

Moose, Steve

2010-03-25T23:59:59.000Z

202

Proximity breeds danger: emerging threats in metro-area wireless networks  

Science Conference Proceedings (OSTI)

The growing popularity of wireless networks and mobile devices is starting to attract unwanted attention especially as potential targets for malicious activities reach critical mass. In this study, we try to quantify the threat from large-scale distributed ...

P. Akritidis; W. Y. Chin; V. T. Lam; S. Sidiroglou; K. G. Anagnostakis

2007-08-01T23:59:59.000Z

203

INL FCF Basis Review Follow-up  

NLE Websites -- All DOE Office Websites (Extended Search)

2: Evaluation Basis Earthquake Event The second Significant Issue related to the EBE event and included several elements, including input parameters to the analysis,...

204

Lawrence Livermore National Laborotory Safety Basis Assessment...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and implementation of safety basis documentation and execution of the unreviewed safety question (USQ) process. SCOPE The scope of this assessment includes the plans,...

205

Lawrence Livermore National Laborotory Safety Basis Assessment...  

NLE Websites -- All DOE Office Websites (Extended Search)

of the safety basis for LLNL nuclear facilities. It describes the method for categorizing nuclear facilities and summarizes the resulting requirements for the contents of the DSA....

206

Facility Representative Program: Nuclear Safety Basis Fundamentals...  

NLE Websites -- All DOE Office Websites (Extended Search)

Qualification Information Qualification Standards DOE Order Self-Study Modules DOE Fundamentals Handbooks Nuclear Safety Basis Self-Study Guide Energy Online Courses Available...

207

Detection and Analysis of Threats to the Energy Sector: DATES  

Science Conference Proceedings (OSTI)

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.

Alfonso Valdes

2010-03-31T23:59:59.000Z

208

Application of Target Value Design to Energy Efficiency Investments  

E-Print Network (OSTI)

the original basis of design, fan wall system, withoutreflect the single fan vane axial design for the aira unique AHU design using a vane axial fan. Following a

Lee, Hyun Woo

2012-01-01T23:59:59.000Z

209

Burnup Credit Technical Basis for Spent-Fuel Burnup Verification  

Science Conference Proceedings (OSTI)

Present regulatory practices provide as much burnup credit flexibility as can be currently expected. Further progress is achievable by incorporating the negative reactivity effects of a subset of neutron-absorbing fission-product isotopes, and by optimizing the procedural approach for establishing the burnup characteristics of the spent fuel to be loaded in burnup-credit-designed storage and transportation systems. This report describes progress toward developing a technical basis for a cost-effective bu...

2003-12-02T23:59:59.000Z

210

Informing design decisions : an approach to corporate building design  

E-Print Network (OSTI)

This thesis is an investigation into design methodologies. How do we, as designers, prepare ourselves for decision making and evaluate our assumptions and decisions? The intent is to employ this information as a basis for ...

Maxwell, Marc A

1985-01-01T23:59:59.000Z

211

Grey-box radial basis function modelling  

Science Conference Proceedings (OSTI)

A fundamental principle in data modelling is to incorporate available a priori information regarding the underlying data generating mechanism into the modelling process. We adopt this principle and consider grey-box radial basis function (RBF) modelling ... Keywords: Black-box model, Boundary value constraint, Data modelling, Grey-box model, Orthogonal least squares algorithm, Radial basis function network, Symmetry

Sheng Chen; Xia Hong; Chris J. Harris

2011-05-01T23:59:59.000Z

212

NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 NSS 18.3 Verification of Authorization Basis Documentation 12/8/03 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 Notice 411.1-1B, the authorization basis consists of those aspects of the facility design basis and operational requirements relied upon by DOE to authorize operation. These aspects are considered to be important to the safety of the facility operations. The authorization basis is described in documents such as the facility safety analysis report and other documented safety analyses; hazard classification documents, and the Technical Safety Requirements,

213

Property:ExplorationBasis | Open Energy Information  

Open Energy Info (EERE)

ExplorationBasis ExplorationBasis Jump to: navigation, search Property Name ExplorationBasis Property Type 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 electrical generation capacity, etc.) Subproperties This property has the following 1 subproperty: M Mercury Vapor At Salt Wells Area (Henkle, Et Al., 2005) Pages using the property "ExplorationBasis" Showing 25 pages using this property. (previous 25) (next 25) 2 2-M Probe Survey At Coso Geothermal Area (1977) + Compare directly shallow temperature results with standard geothermal exploration techniques. 2-M Probe Survey At Coso Geothermal Area (1979) + Correct previously analyzed 2-m probe data

214

Microsoft Word - Final Cover.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

National Nuclear Security National Nuclear Security Administration's Implementation of the 2003 Design Basis Threat DOE/IG-0705 October 2005 SPECIAL REPORT ON THE NATIONAL NUCLEAR SECURITY ADMINISTRATION'S IMPLEMENTATION OF THE 2003 DESIGN BASIS THREAT TABLE OF CONTENTS Implementation of the Design Basis Threat Details of Finding ...........................................................................................1 Recommendations...........................................................................................9 Comments .....................................................................................................10 Appendices 1. Objective, Scope, and Methodology........................................................11

215

Fully complex-valued radial basis function networks: Orthogonal least squares regression and classification  

Science Conference Proceedings (OSTI)

We consider a fully complex-valued radial basis function (RBF) network for regression and classification applications. For regression problems, the locally regularised orthogonal least squares (LROLS) algorithm aided with the D-optimality experimental ... Keywords: Classification, Complex-valued radial basis function network, D-optimality experimental design, Fisher ratio of class separability measure, Orthogonal least squares algorithm, Regression

S. Chen; X. Hong; C. J. Harris; L. Hanzo

2008-10-01T23:59:59.000Z

216

Multiscale finite element methods for high-contrast problems using local spectral basis functions  

Science Conference Proceedings (OSTI)

In this paper we study multiscale finite element methods (MsFEMs) using spectral multiscale basis functions that are designed for high-contrast problems. Multiscale basis functions are constructed using eigenvectors of a carefully selected local spectral ... Keywords: High contrast, Multiscale finite element, Porous media, Spectral

Yalchin Efendiev; Juan Galvis; Xiao-Hui Wu

2011-02-01T23:59:59.000Z

217

Parallel algorithms for identifying convex and non-convex basis polygons in an image  

Science Conference Proceedings (OSTI)

In this paper, we propose two novel parallel algorithms for identifying all the basis polygons in an image formed by n straight line segments each of which is represented by its two end points. The first algorithm is designed to tackle the simple situation ... Keywords: Basis polygon, Edge traversal, Parallel algorithm

Arijit Laha; Amitava Sen; Bhabani P. Sinha

2005-03-01T23:59:59.000Z

218

An application of radial basis function networks in operation of home appliances  

Science Conference Proceedings (OSTI)

Neural networks (NN) have made a great impact in modeling and synthesizing non-linear mapping of input-output space. In this paper, we describe the design and testing of a particular class of NN, radial basis function networks, for dryness prediction ... Keywords: appliance engineering, dryness prediction, radial basis function networks

Yu-To Chen

2000-12-01T23:59:59.000Z

219

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

SciTech Connect

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.

Merkle, Peter Benedict

2006-03-01T23:59:59.000Z

220

Basis for UCNI | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Basis for UCNI Basis for 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, specifies additional policies and requirements concerning the Department of Energy (DOE) UCNI program. UCNI General Guideline, GG-5, is a record of decisions made by the Director, OC, as to what general subject areas are UCNI. Note: GG-5 may only be used by the Director, OC, to make determinations as to whether

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Basis for UCNI | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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...

222

Fossil Maintenance Basis Optimization: Challenges and Strategies  

Science Conference Proceedings (OSTI)

This report covers many of the process challenges and strategies that were encountered and deployed during the implementation and execution of a preventive maintenance basis optimization (MBO) process at fossil generating stations. This MBO process was executed by several Electric Power Research Institutemember (EPRI-member) companies on a fleetwide basis as part of the members' plant reliability optimization (PRO) efforts. The PRO process covers many of the preventive maintenance (PM) programs at multip...

2010-05-27T23:59:59.000Z

223

Safety Basis Criteria & Review Approach Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Basis Criteria & Review Approach Documents Safety Basis Criteria & Review Approach Documents Safety Basis Criteria & Review Approach Documents Documents Available for Download CRAD, Safety Basis - Idaho MF-628 Drum Treatment Facility CRAD, Safety Basis - Idaho Accelerated Retrieval Project Phase II CRAD, Safety Basis - Los Alamos National Laboratory TA 55 SST Facility CRAD, Safety Basis - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Safety Basis - Y-12 Enriched Uranium Operations Oxide Conversion Facility

224

UNCLASSIFIED Texas Gang Threat Assessment 2012 Texas Gang Threat Assessment 2012 A State Intelligence Estimate Produced by the Texas Fusion Center  

E-Print Network (OSTI)

The key analytic judgments of this assessment are: Gangs continue to represent a significant public safety threat to the State of Texas, and are responsible for a disproportionate amount of crime in our communities. Of incarcerated members of Tier 1 and Tier 2 gangs, more than half are serving a sentence for a violent crime, including robbery (25 percent), homicide (14 percent), and assault/terroristic threat (12 percent). The Tier 1 gangs in Texas are Tango Blast (estimated at 10,000 members), Texas Syndicate (4,500 members), Barrio Azteca (3,500 members), and Texas Mexican Mafia (6,000 members). These organizations pose the greatest gang threat to Texas due to their relationships with Mexican cartels, large membership numbers, high levels of transnational criminal activity, and organizational effectiveness. Mexican cartels continue to use gangs in Texas as they smuggle drugs, people, weapons, and cash across the border. Members of Tier 1 gangs have been recruited by the cartels to carry out acts of violence in both Texas and Mexico. The relationships between gangs and cartels have evolved over the past year, due in part to volatility and changes in cartel

unknown authors

2013-01-01T23:59:59.000Z

225

Surveillance Guide - NSS 18.3 Verification of Authorization Basis Documentation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

VERIFICATION OF AUTHORIZATION BASIS DOCUMENTATION VERIFICATION OF AUTHORIZATION BASIS DOCUMENTATION 1.0 Objective 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 Notice 411.1-1B, the authorization basis consists of those aspects of the facility design basis and operational requirements relied upon by DOE to authorize operation. These aspects are considered to be important to the safety of the facility operations. The authorization basis is described in documents such as the facility safety analysis report and other documented safety analyses; hazard classification documents, and the Technical Safety Requirements, DOE- issued safety evaluation reports, and facility-specific commitments made in

226

Cold vacuum drying facility design requirements  

SciTech Connect

This release of the Design Requirements Document is a complete restructuring and rewrite to the document previously prepared and released for project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility.

Irwin, J.J.

1997-09-24T23:59:59.000Z

227

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

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 PNNLs 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 PNNLs Electronic Records & Information Capture Architecture (ERICA) database.

Rathbone, Bruce A.

2005-02-25T23:59:59.000Z

228

Basis for OUO | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Classification » Official Use Only Information » Services » Classification » Official Use Only Information » Basis for OUO Basis for OUO What documents contain the policy foundation for the OUO program? DOE O 471.3 Admin Chg 1, Identifying and Protecting Official Use Only Information. DOE M 471.3-1 Admin Chg 1, Manual for Identifying and Protecting Official Use Only Information. Training & Reference Materials Basis for OUO OUO Review Requirement Access to OUO Protection of OUO Questions about Making OUO Determinations - OUO and the FOIA Exemptions How is a Document Containing OUO Marked? Controlled Unclassified Information and E.O. 13556 Resources for OUO Enforcement Guidance Oversight Reporting Security Classification Classification Training Institute Official Use Only Information Unclassified Controlled Nuclear Information (UCNI)

229

INL FCF Basis Review Follow-up  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

, 2011 , 2011 Independent Review Report Idaho National Laboratory Fuel Conditioning Facility Safety Basis Review Follow-up PURPOSE The purpose of this follow-up review was to verify how and to what extent Idaho National Laboratory (INL) addressed the Significant Issues that were identified in the April 2010 Independent Oversight report on the INL Fuel Conditioning Facility (FCF) safety basis review, as well as the consideration given to the recommendations that were made. Significant Issues were defined in that report as problems or concerns that affected the validity of the FCF safety basis documentation. The Office of Health, Safety and Security (HSS) fulfilled this objective by reviewing the draft Safety Analysis Report (SAR) for the FCF,

230

Virtual environments for nuclear power plant design  

SciTech Connect

In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP).

Brown-VanHoozer, S.A.; Singleterry, R.C. Jr.; King, R.W. [and others

1996-03-01T23:59:59.000Z

231

RNEDE: Resilient Network Design Environment  

SciTech Connect

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.

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

2010-08-01T23:59:59.000Z

232

General pattern of global system conflicts and global threats of the 21st century  

Science Conference Proceedings (OSTI)

Data on global conflicts took place from 750 B.C. up to now are analyzed and their general pattern is revealed. An attempt is made to foresee the next global conflict called the conflict of the 21st century. Its nature and main characteristics are analyzed. ... Keywords: Fibonacci sequence, cluster analysis, global system conflicts, global threats, scenarios

M. Z. Zgurovsky

2007-09-01T23:59:59.000Z

233

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

SciTech Connect

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.

Silva, Consuelo Juanita

2006-12-01T23:59:59.000Z

234

Original Research Chlorine Gas: An Evolving Hazardous Material Threat and Unconventional Weapon  

E-Print Network (OSTI)

Chlorine gas represents a hazardous material threat from industrial accidents and as a terrorist weapon. This review will summarize recent events involving chlorine disasters and its use by terrorists, discuss pre-hospital considerations and suggest strategies for the initial management for acute chlorine exposure events. [West J Emerg Med. 2010; 11(2):151-156.

Robert Jones Md; Brandon Wills Do; Christopher Kang Md

2009-01-01T23:59:59.000Z

235

ICMPV6 Vulnerability: The Importance of Threat Model and SF-ICMP6  

Science Conference Proceedings (OSTI)

Handling Internet Control Message Protocol version 6 ICMPv6 vulnerabilities is among the challenges in securing the IPv6 deployment. Since ICMPv6 messages are crucial in IPv6 communications, this paper discusses the discovery of ICMPv6 vulnerabilities ... Keywords: ICMPv6 Policy, ICMPv6 Related Attacks, ICMPv6 Security, ICMPv6 Threat Model, Selective Filtering

Abidah Hj Mat Taib, Wan Nor Ashiqin Wan Ali, Nurul Sharidah Shaari

2013-04-01T23:59:59.000Z

236

Security Issues in Cloud Computing: A Survey of Risks, Threats and Vulnerabilities  

Science Conference Proceedings (OSTI)

Cloud Computing CC is revolutionizing the methodology by which IT services are being utilized. It is being introduced and marketed with many attractive promises that are enticing to many companies and managers, such as reduced capital costs and relief ... Keywords: Cloud Computing, Risks, Security, Threats, Vulnerabilities

Kamal Dahbur; Bassil Mohammad; Ahmad Bisher Tarakji

2011-07-01T23:59:59.000Z

237

Coupled-channel continuum eigenchannel basis  

E-Print Network (OSTI)

The goal of this paper is to calculate bound, resonant and scattering states in the coupled-channel formalism without relying on the boundary conditions at large distances. The coupled-channel solution is expanded in eigenchannel bases i.e. in eigenfunctions of diagonal Hamiltonians. Each eigenchannel basis may includes discrete and discretized continuum (real or complex energy) single particle states. The coupled-channel solutions are computed through diagonalization in these bases. The method is applied to a few two-channel problems. The exact bound spectrum of the Poeschl-Teller potential is well described by a basis of real energy continuum states. For the deuteron with the Reid potential the experimental energy and the $S$ and $D$ wave functions content are reproduced in the asymptotic limit of the energy cutoff. For the Noro-Taylor potential, beside the exact bound state energies the resonant state energy is also well reproduced by using the complex energy Berggren basis. It is found that the expansion of the coupled-channel wave functions in these eigenchannel bases require less computational effort than the use of any other basis. The solutions are stable and converge as the energy cutoff increases.

R. M. Id Betan

2013-11-18T23:59:59.000Z

238

Multivariate statistical analysis of the influence of global threats on the security of countries of the world  

Science Conference Proceedings (OSTI)

Methods of multivariate statistical analysis are applied to the investigation of the influence of global threats on the security of countries and regions of the world. The use of the principal component analysis method made it possible to reveal three ... Keywords: Minkowsky norm, cluster analysis, correlation analysis, global threat, principal component analysis., stable development

T. N. Pomerantseva; A. A. Boldak

2010-03-01T23:59:59.000Z

239

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

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 PNNLs 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 PNNLs 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.

Rathbone, Bruce A.

2009-08-28T23:59:59.000Z

240

Radioactive Waste Management BasisApril 2006  

Science Conference Proceedings (OSTI)

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.

Perkins, B K

2011-08-31T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Bessel-Zernike Discrete Variable Representation Basis  

SciTech Connect

The connection between the Bessel discrete variable basis expansion and a specific form of an orthogonal set of Jacobi polynomials is demonstrated. These so-called Zernike polynomials provide alternative series expansions of suitable functions over the unit interval. Expressing a Bessel function in a Zernike expansion provides a straightforward method of generating series identities. Furthermore, the Zernike polynomials may also be used to efficiently evaluate the Hankel transform for rapidly decaying functions or functions with finite support.

Cerjan, C J

2005-10-24T23:59:59.000Z

242

Structural Basis for Activation of Cholera Toxin  

NLE Websites -- All DOE Office Websites (Extended Search)

Structural Basis for Activation 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 (CTA1) triggers a series of events culminating in the massive efflux of electrolytes and water into the intestinal cavity, causing the watery diarrhea characteristic of cholera that can lead to severe dehydration and death. Crystal structures of the CTA1 subunit in complex with its activator molecule (ARF6) reveal that binding of the ARF6 "switch" elicits dramatic changes in CTA1 loop regions, exposing the toxin's active site. The extensive CTA1-ARF6 interface mimics recognition of ARF6's normal cellular protein partners, which suggests that the toxin has evolved to exploit the molecular switch's promiscuous binding properties.

243

Business Case Slide 16: High-Volume: Casks - Basis  

NLE Websites -- All DOE Office Websites (Extended Search)

Basis Previous Slide Next Slide Table of Contents High-Volume: Casks - Basis Basis Storage casks with high-density shielding can be directly loaded in reactor pools Eliminates a...

244

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

NLE Websites -- All DOE Office Websites (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...

245

The Molecular Basis for Water Taste in Drosophila  

E-Print Network (OSTI)

odorant receptors: a molecular basis for odor recognition.J. , Weissman, J. , Julius, D. Molecular basis of infraredDarnell, J. (2000). Molecular Cell Biology, 4th edition.

Cameron, Peter

2010-01-01T23:59:59.000Z

246

Online Monitoring Technical Basis and Analysis Framework for...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators-Interim Report for FY 2013 Online Monitoring Technical Basis and Analysis Framework for...

247

Experimental Progress Report--Modernizing the Fission Basis  

Science Conference Proceedings (OSTI)

In 2010 a proposal (Modernizing the Fission Basis) was prepared to 'resolve long standing differences between LANL and LLNL associated with the correct fission basis for analysis of nuclear test data'. Collaboration between LANL/LLNL/TUNL has been formed to implement this program by performing high precision measurements of neutron induced fission product yields as a function of incident neutron energy. This new program benefits from successful previous efforts utilizing mono-energetic neutrons undertaken by this collaboration. The first preliminary experiment in this new program was performed between July 24-31, 2011 at TUNL and had 2 main objectives: (1) demonstrating the capability to measure characteristic {gamma}-rays from specific fission products; (2) studying background effects from room scattered neutrons. In addition, a new dual fission ionization chamber has been designed and manufactured. The production design of the chamber is shown in the picture below. The first feasibility experiment to test this chamber is scheduled at the TUNL Tandem Laboratory from September 19-25, 2011. The dual fission chamber design will allow simultaneous exposure of absolute fission fragment emission rate detectors and the thick fission activation foils, positioned between the two chambers. This document formalizes the earlier experimental report demonstrating the experimental capability to make accurate (fission product yields of the 239Pu(n,f) reaction (induced by quasimonoenergetic neutrons). A second experiment (9/2011) introduced an compact double-sided fission chamber into the experimental arrangement, and so the relative number of incident neutrons striking the sample foil at each bombarding energy is limited only by statistics. (The number of incident neutrons often limits the experimental accuracy.) Fission chamber operation was so exceptional that 2 more chambers have been fabricated; thus fission foils of different isotopes may be left in place with sample changes. The scope of the measurements is both greatly expanded and the results become vetted. Experiment 2 is not reported here. A continuing experiment has been proposed for February 2012.

Macri, R A

2012-02-17T23:59:59.000Z

248

Microsoft Word - Threat Analysis Framework Sept07_comments-final.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5792 5792 Unlimited Release September 2007 Threat Analysis Framework David P. Duggan and John T. Michalski Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04-94AL85000. Approved for public release; further dissemination unlimited. Threat Analysis Framework 2 Issued by Sandia National Laboratories, operated for the United States Department of Energy by Sandia Corporation. NOTICE: This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government, nor any agency

249

NNSA's Global Threat Reduction Initiative Removes More Than One Ton of  

NLE Websites -- All DOE Office Websites (Extended Search)

Removes More Than One Ton of Removes More Than One Ton of Food | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > NNSA's Global Threat Reduction Initiative Removes More ... NNSA's Global Threat Reduction Initiative Removes More Than One Ton of Food Posted By Office of Public Affairs Contributing to DOE/NNSA's efforts to support the Office of Personnel

250

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

Science Conference Proceedings (OSTI)

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.

Hauschild, Veronique [U.S. Army Public Health Command] [U.S. Army Public Health Command; Watson, Annetta Paule [ORNL] [ORNL

2013-01-01T23:59:59.000Z

251

A Novel Scheme for Encoding and Watermark Embedding in VLSI Physical Design for IP Protection  

Science Conference Proceedings (OSTI)

The emerging trend of design reuse in VLSI circuits poses the threat of theft and misappropriation of intellectual property (IP) of the design. Protection of design IP is a matter of prime concern today. Here we propose a scheme SECURE IP, which tackles ...

Debasri Saha; Parthasarathi Dasgupta; Susmita Sur-Kolay; Samar Sen-Sarma

2007-03-01T23:59:59.000Z

252

Global Threat  

NLE Websites -- All DOE Office Websites (Extended Search)

dual application of splitting the atom, U.S. policy towards civilian use of highly enriched uranium (HEU) has historically exhibited contradictory traits. During these early...

253

Central waste complex interim safety basis  

Science Conference Proceedings (OSTI)

This interim safety basis provides the necessary information to conclude that hazards at the Central Waste Complex are controlled and that current and planned activities at the CWC can be conducted safely. CWC is a multi-facility complex within the Solid Waste Management Complex that receives and stores most of the solid wastes generated and received at the Hanford Site. The solid wastes that will be handled at CWC include both currently stored and newly generated low-level waste, low-level mixed waste, contact-handled transuranic, and contact-handled TRU mixed waste.

Cain, F.G.

1995-05-15T23:59:59.000Z

254

Technical basis for internal dosimetry at Hanford  

SciTech Connect

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01T23:59:59.000Z

255

Technical basis for internal dosimetry at Hanford  

SciTech Connect

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01T23:59:59.000Z

256

The Effects of Slack Resources and Environmental Threat on Product Exploration and Exploitation  

E-Print Network (OSTI)

In a U.S. sample of nonprofit professional theaters, we examine how slack resources interact with environmental threat appraisal to influence product exploration and exploitation. We find systematic variation depending on the extent to which a resource is rare and absorbed in operations, and the extent of perceived environmental threats. Absorbed, generic resources are associated with increased exploitation and decreased exploration. Unabsorbed resources, both generic and rare, result in higher exploration and lower exploitation, but only when perceived environmental threat is high. Overall, results reveal pragmatic decision making balancing the benefits of superior strategic position against the risks of jeopardizing viability. The overall strategic emphasis of an organization is reflected in investments of resources in activities and processes that promote exploration or exploitation (Siggelkow & Levinthal, 2003). Exploration creates novel competencies that enable ongoing innovation and generally results in superior longterm returns (Geroski, Machin, & Van Reenen, 1993). These benefits are balanced by the higher level of risk inherent in exploratory activities, which require significant investments with uncertain payoffs (Gupta, Smith, & Shalley, 2006). Exploitation creates value through existing or minimally modified competencies that sustain longterm viability following successful exploration. Successful exploitation provides a buffer from the shocks of exploration and entails less risk than

Glenn B. Voss; Zannie Giraud Voss

2008-01-01T23:59:59.000Z

257

Coupling measurement and lightning threat assessment report for Pantex Cell 12-44-1  

SciTech Connect

This report is the first of a series that will quantify the lightning threat to the Pantex Plant where high-risk operations occur. More information can be found in the report written by the Lightning Protection Team [1] and Sandia National Laboratory documents. Low-power RF coupling measurements were completed on Cell 12-44-1 in May 1998. These measurements quantify the voltage and current levels that could leak into the cell from possible lightning strike points. Cell 1 is representative of the most ?leaky? class of cells at Pantex because the floor was not intentionally electrically connected to the walls. From the measurement data, linear models were developed. These transfer functions allow us to calculate the effect in the cell from the much higher power lightning threat. Two types of coupling paths were characterized: (1) external ventilation stack to cell interior and (2) cell ceiling to other cell elements. For the maximum lightning threat [2], an estimate of the maximum cell-to-floor voltage is 150 kV. The extrapolated voltage levels at normal working heights are lower. The potential between the air duct and the electro-static ground is estimated to be 4 kV. A secondary goal was to compare results with Sandia as a quality control check. While the estimated maximum ceiling-to-floor voltages are similar, the comparison was limited by high-frequency resonances on the drive wire.

Anderson, R; Ong, M

1998-09-01T23:59:59.000Z

258

Coupling measurement and lightning threat assessment report for Pantex Cell 12-44-1  

SciTech Connect

This report is the first of a series that will quantify the lightning threat to the Pantex Plant where high-risk operations occur. More information can be found in the report written by the Lightning Protection Team [1] and Sandia National Laboratory documents. Low-power RF coupling measurements were completed on Cell 12-44-1 in May 1998. These measurements quantify the voltage and current levels that could leak into the cell from possible lightning strike points. Cell 1 is representative of the most leaky class of cells at Pantex because the floor was not intentionally electrically connected to the walls. From the measurement data, linear models were developed. These transfer functions allow us to calculate the effect in the cell from the much higher power lightning threat. Two types of coupling paths were characterized: (1) external ventilation stack to cell interior and (2) cell ceiling to other cell elements. For the maximum lightning threat [2], an estimate of the maximum cell-to-floor voltage is 150 kV. The extrapolated voltage levels at normal working heights are lower. The potential between the air duct and the electro-static ground is estimated to be 4 kV. A secondary goal was to compare results with Sandia as a quality control check. While the estimated maximum ceiling-to-floor voltages are similar, the comparison was limited by high-frequency resonances on the drive wire.

Anderson, R; Ong, M.

1998-09-01T23:59:59.000Z

259

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

SciTech Connect

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

Barhen, Jacob [ORNL; Imam, Neena [ORNL

2009-01-01T23:59:59.000Z

260

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Audit and Inspections 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 Administration" BACKGROUND The National Nuclear Security Administration's (NNSA) Office of Defense Nuclear Nonproliferation established the Global Threat Reduction Initiative (GTRI) in May 2004, as a vital part of the efforts to combat nuclear and radiological terrorism. GTRI's mission is to reduce

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Natural phenomena hazards design and evaluation criteria for Department of Energy Facilities  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) has issued an Order 420.1 which establishes policy for its facilities in the event of natural phenomena hazards (NPH) along with associated NPH mitigation requirements. This DOE Standard gives design and evaluation criteria for NPH effects as guidance for implementing the NPH mitigation requirements of DOE Order 420.1 and the associated implementation Guides. These are intended to be consistent design and evaluation criteria for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of these criteria is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. These criteria apply to the design of new facilities and the evaluation of existing facilities. They may also be used for modification and upgrading of existing facilities as appropriate. The design and evaluation criteria presented herein control the level of conservatism introduced in the design/evaluation process such that earthquake, wind, and flood hazards are treated on a consistent basis. These criteria also employ a graded approach to ensure that the level of conservatism and rigor in design/evaluation is appropriate for facility characteristics such as importance, hazards to people on and off site, and threat to the environment. For each natural phenomena hazard covered, these criteria consist of the following: Performance Categories and target performance goals as specified in the DOE Order 420.1 NPH Implementation Guide, and DOE-STD-1 021; specified probability levels from which natural phenomena hazard loading on structures, equipment, and systems is developed; and design and evaluation procedures to evaluate response to NPH loads and criteria to assess whether or not computed response is permissible.

NONE

1996-01-01T23:59:59.000Z

262

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

SciTech Connect

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.

NONE

1993-12-31T23:59:59.000Z

263

Structural Basis for Activation of Cholera Toxin  

NLE Websites -- All DOE Office Websites (Extended Search)

Structural Basis for Activation of Cholera Toxin Print 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 electrolytes and water into the intestinal cavity, causing the watery diarrhea characteristic of cholera that can lead to severe dehydration and death. Crystal structures of the CTA1 subunit in complex with its activator molecule (ARF6) reveal that binding of the ARF6 "switch" elicits dramatic changes in CTA1 loop regions, exposing the toxin's active site. The extensive CTA1-ARF6 interface mimics recognition of ARF6's normal cellular protein partners, which suggests that the toxin has evolved to exploit the molecular switch's promiscuous binding properties.

264

Structural Basis for Activation of Cholera Toxin  

NLE Websites -- All DOE Office Websites (Extended Search)

Structural Basis for Activation of Cholera Toxin Print 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 electrolytes and water into the intestinal cavity, causing the watery diarrhea characteristic of cholera that can lead to severe dehydration and death. Crystal structures of the CTA1 subunit in complex with its activator molecule (ARF6) reveal that binding of the ARF6 "switch" elicits dramatic changes in CTA1 loop regions, exposing the toxin's active site. The extensive CTA1-ARF6 interface mimics recognition of ARF6's normal cellular protein partners, which suggests that the toxin has evolved to exploit the molecular switch's promiscuous binding properties.

265

Structural Basis for Activation of Cholera Toxin  

NLE Websites -- All DOE Office Websites (Extended Search)

Structural Basis for Activation of Cholera Toxin Print 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 electrolytes and water into the intestinal cavity, causing the watery diarrhea characteristic of cholera that can lead to severe dehydration and death. Crystal structures of the CTA1 subunit in complex with its activator molecule (ARF6) reveal that binding of the ARF6 "switch" elicits dramatic changes in CTA1 loop regions, exposing the toxin's active site. The extensive CTA1-ARF6 interface mimics recognition of ARF6's normal cellular protein partners, which suggests that the toxin has evolved to exploit the molecular switch's promiscuous binding properties.

266

Determining the Flight Icing Threat to Aircraft with Single-Layer Cloud Parameters Derived from Operational Satellite Data  

Science Conference Proceedings (OSTI)

An algorithm is developed to determine the flight icing threat to aircraft utilizing quantitative information on clouds derived from meteorological satellite data as input. Algorithm inputs include the satellite-derived cloud-top temperature, ...

William L. Smith Jr.; Patrick Minnis; Cecilia Fleeger; Douglas Spangenberg; Rabindra Palikonda; Louis Nguyen

2012-10-01T23:59:59.000Z

267

What are the security threats to further development of nuclear power plants in the U.S.? .  

E-Print Network (OSTI)

??What are the security threats to further development of nuclear power plants in the U.S.? The U.S. stands alone today in terms of the vast (more)

Nottestad, Tammie L.

2010-01-01T23:59:59.000Z

268

Radioactive Waste Management BasisSept 2001  

SciTech Connect

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 RWMB 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 meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Goodwin, S S

2011-08-31T23:59:59.000Z

269

Los Alamos National Laboratory Fission Basis  

Science Conference Proceedings (OSTI)

This report is an overview of two main publications that provide a comprehensive review of the Los Alamos National Laboratory (LANL) Fission Basis. The first is the experimental paper, {sup F}ission Product Data Measured at Los Alamos for Fission Spectrum and Thermal Neutrons on {sup 239}Pu, {sup 235}U, {sup 238}U, [Selby, H. D., et al., Nucl. Data Sheets, Vol. 111 2010, pp. 2891-2922] and the second is the theoretical paper, Fission Product Yields from Fission Spectrum n+ {sup 239}Pu for ENDF/B-VII.1, [Chadwick, M. B., et al., Nucl. Data Sheets, Vol. 111, 2010, pp. 2923-2964]. One important note is that none of this work would have been possible without the great documentation of the experimental details and results by G.W. Knobeloch, G. Butler, C.I. Browne, B. Erdal, B. Bayhurst, R. Prestwood, V. Armijo, J. Hasty and many others. (authors)

Keksis, A.L.; Chadwick, M.B.; Selby, H.D.; Mac Innes, M.R.; Barr, D.W.; Meade, R.A.; Burns, C.J.; Wallstrom, T.C. [Los Alamos National Laboratory, NM 87545 (United States)

2011-07-01T23:59:59.000Z

270

Position paper: Seismic design criteria  

SciTech Connect

The purpose of this paper is to document the seismic design criteria to be used on the Title 11 design of the underground double-shell waste storage tanks and appurtenant facilities of the Multi-Function Waste Tank Facility (MWTF) project, and to provide the history and methodologies for determining the recommended Design Basis Earthquake (DBE) Peak Ground Acceleration (PGA) anchors for site-specific seismic response spectra curves. Response spectra curves for use in design are provided in Appendix A.

Farnworth, S.K.

1995-05-22T23:59:59.000Z

271

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

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 Hanfords 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 PNNLs 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.

Rathbone, Bruce A.

2010-04-01T23:59:59.000Z

272

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

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 Hanfords 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 PNNLs 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.

Rathbone, Bruce A.

2011-04-04T23:59:59.000Z

273

Safety basis academy summary of project implementation from 2007-2009  

Science Conference Proceedings (OSTI)

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.

Johnston, Julie A [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

274

CRAD, Review of Safety Basis Development - January 31, 2013 | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

January 31, 2013 January 31, 2013 CRAD, Review of Safety Basis Development - January 31, 2013 January 31, 2013 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) The review will consider selected aspects of the development of safety basis for the Salt Waste Processing Facility (SWPF) to assess the extent to which safety is integrated into the design of the SWPF in accordance with DOE directives; in particular, DOE Order 420.1 B, DOE-STD-1189, and DOE-STD3009. The review will focus on a few selected safety systems, such as the Process Vessel Ventilation System (PVVS) and the Air Dilution System (ADS), and associated supporting/interfacing systems. CRAD, Review of Safety Basis Development - January 31, 2013

275

Managing Locational Basis Risk in a Nodal Power Market: A PJM Case Study  

Science Conference Proceedings (OSTI)

The physics of power flows in a congested transmission network can lead to dramatic differences in the value of electric power at different network locations. These cost differences have led a number of market designers to establish systems by which electricity prices vary by location. This report presents a case study demonstrating the effectiveness of an EPRI approach for designing hedges of locational basis risk due to transmission congestion when firm transmission rights (FTRs) are not available.

2001-12-03T23:59:59.000Z

276

Materials Reliability Program (MRP-149, Revision 1) Fatigue Licensing Basis Monitoring Guideline  

Science Conference Proceedings (OSTI)

All nuclear plants are required to operate their mechanical systems within the parameters defined by fatigue design basis requirements, analyses and assumptions. This monitoring guideline is part of the Electric Power Research Institutes (EPRIs) comprehensive and integrated Fatigue Management approach designed to prevent and/or manage cracking of components due to fatigue.BackgroundThis document provides guidance for utility engineers to implement a fatigue ...

2013-12-23T23:59:59.000Z

277

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

Science Conference Proceedings (OSTI)

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.

Duren, Mike [Sypris Electronics, LLC; Aldridge, Hal [ORNL; Abercrombie, Robert K [ORNL; Sheldon, Frederick T [ORNL

2013-01-01T23:59:59.000Z

278

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

SciTech Connect

The U.S. Department of Energys 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.

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

2009-10-07T23:59:59.000Z

279

Climate Change 2001: The Scientific Basis  

Office of Scientific and Technical Information (OSTI)

Climate Change 2001: Climate Change 2001: Working Group I: The Scientific Basis Get Javascript Other reports in this collection 4. Atmospheric Chemistry and Greenhouse Gases Contents Executive Summary 4.1 Introduction 4.1.1 Sources of Greenhouse Gases 4.1.2 Atmospheric Chemistry and Feedbacks 4.1.3 Trace Gas Budgets and Trends 4.1.4 Atmospheric Lifetimes and Time-Scales 4.2 Trace Gases: Current Observations, Trends and Budgets 4.2.1 Non-CO2 Kyoto Gases 4.2.1.1 Methane (CH4) 4.2.1.2 Nitrous oxide (N2O) 4.2.1.3 Hydrofluorocarbons (HFCs) 4.2.1.4 Perfluorocarbons (PFCs) and sulphur hexafluoride (SF6) 4.2.2 Montreal Protocol Gases and Stratospheric Ozone (O3) 4.2.3 Reactive Gases 4.2.3.1 Carbon monoxide (CO) and hydrogen (H2) 4.2.3.2 Volatile organic compounds (VOC) 4.2.3.3 Nitrogen oxides (NOx)

280

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

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 PNNLs 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 PNNLs 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.

Rathbone, Bruce A.

2007-03-12T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Experimental Progress Report--Modernizing the Fission Basis  

SciTech Connect

In 2010 a proposal (Modernizing the Fission Basis) was prepared to 'resolve long standing differences between LANL and LLNL associated with the correct fission basis for analysis of nuclear test data'. Collaboration between LANL/LLNL/TUNL has been formed to implement this program by performing high precision measurements of neutron induced fission product yields as a function of incident neutron energy. This new program benefits from successful previous efforts utilizing mono-energetic neutrons undertaken by this collaboration. The first preliminary experiment in this new program was performed between July 24-31, 2011 at TUNL and had 2 main objectives: (1) demonstrating the capability to measure characteristic {gamma}-rays from specific fission products; (2) studying background effects from room scattered neutrons. In addition, a new dual fission ionization chamber has been designed and manufactured. The production design of the chamber is shown in the picture below. The first feasibility experiment to test this chamber is scheduled at the TUNL Tandem Laboratory from September 19-25, 2011. The dual fission chamber design will allow simultaneous exposure of absolute fission fragment emission rate detectors and the thick fission activation foils, positioned between the two chambers. This document formalizes the earlier experimental report demonstrating the experimental capability to make accurate (< 2 %) precision gamma-ray spectroscopic measurements of the excitation function of high fission product yields of the 239Pu(n,f) reaction (induced by quasimonoenergetic neutrons). A second experiment (9/2011) introduced an compact double-sided fission chamber into the experimental arrangement, and so the relative number of incident neutrons striking the sample foil at each bombarding energy is limited only by statistics. (The number of incident neutrons often limits the experimental accuracy.) Fission chamber operation was so exceptional that 2 more chambers have been fabricated; thus fission foils of different isotopes may be left in place with sample changes. The scope of the measurements is both greatly expanded and the results become vetted. Experiment 2 is not reported here. A continuing experiment has been proposed for February 2012.

Macri, R A

2012-02-17T23:59:59.000Z

282

Technical Basis for U. S. Department of Energy Nuclear Safety...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1, 711 Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1,...

283

Business Case Slide 27: High-Value: Semiconductors - Basis for...  

NLE Websites -- All DOE Office Websites (Extended Search)

Semiconductors - Basis for Use Basis for use DUO2 has good electronic properties for semi-conductor applications Have made and tested a diode and transistor which appear superior...

284

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

SciTech Connect

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.

Stickney, R.G.

1998-04-29T23:59:59.000Z

285

Project Hanford nuclear facilities list and authorization basis information  

SciTech Connect

Rev. 4 documents and updates the Nuclear Facilities list and associated Authorization Basis (AB) information for applicable Project Hanford facilities.

EVANS, C.B.

1999-03-03T23:59:59.000Z

286

A Cautionary Tale of Two Basis Sets and Graphene  

Science Conference Proceedings (OSTI)

Density functional theory is a leading approach for simulating materials. However, the basis set used in calculations can directly affect our understanding of a material. By comparing two basis sets for graphene, this highlights an important subtle point ... Keywords: Density functional theory, basis set, graphene, electronic structure, computational materials science, scientific computing

Derek Stewart

2012-03-01T23:59:59.000Z

287

Skew-Radial Basis Function Expansions for Empirical Modeling  

Science Conference Proceedings (OSTI)

We propose a skew-radial basis function (sRBF) expansion for the empirical model fitting problem. sRBFs employ a standard radial term, which is now made asymmetric by modulating, or skewing it with another function. The additional parameters in the skewing ... Keywords: data fitting, data interpolation, function approximation, manifold learning, radial basis function, skew-radial basis function

Arta A. Jamshidi; Michael J. Kirby

2009-11-01T23:59:59.000Z

288

Minimal Realizations of Linear Systems: The "Shortest Basis" Approach  

E-Print Network (OSTI)

Given a discrete-time linear system C, a shortest basis for C is a set of linearly independent generators for C with the least possible lengths. A basis B is a shortest basis if and only if it has the predictable span ...

Forney, G. David, Jr.

289

FATIGUE DESIGN CURVES FOR  

Office of Scientific and Technical Information (OSTI)

FATIGUE DESIGN CURVES FATIGUE DESIGN CURVES FOR 6061-T6 ALUMINUM* G . T . Yahr Engineering Technology Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37831-8051 ABSTRACT A request has been made to the ASME Boiler and Pressure Vessel Committee that 6061-T6 aluminum be approved for use in the construction of Class 1 welded nuclear vessels so it can be used for the pressure vessel of the Advanced Neutron Source research reactor. Fatigue design curves with and without mean stress effects have been proposed. A knock-down factor of two is applied to the design curve for evaluation of welds. The basis of the curves is explained. The fatigue design curves are compared to fatigue data from base metal and weldments. DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States

290

Meta-design: design for designers  

Science Conference Proceedings (OSTI)

One fundamental challenge for the design of the interactive systems of the future is to invent and design environments and cultures in which humans can express themselves and engage in personally meaningful activities. Unfortunately, a large number of ... Keywords: consumer and designer mindsets, designing out of the box, domain-oriented design environments, evolutionary growth, impact of new media on design, open evolvable systems, open source, reseeding model, seeding, underdesigned systems

Gerhard Fischer; Eric Scharff

2000-08-01T23:59:59.000Z

291

A time-of-flight backscattering spectrometer at the Spallation Neutron Source, BASIS  

Science Conference Proceedings (OSTI)

We describe the design and current performance of the backscattering silicon spectrometer (BASIS), a time-of-flight backscattering spectrometer built at the spallation neutron source (SNS) of the Oak Ridge National Laboratory (ORNL). BASIS is the first silicon-based backscattering spectrometer installed at a spallation neutron source. In addition to high intensity, it offers a high-energy resolution of about 3.5 {mu}eV and a large and variable energy transfer range. These ensure an excellent overlap with the dynamic ranges accessible at other inelastic spectrometers at the SNS.

Mamontov, E.; Herwig, K. W. [Neutron Scattering Science Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States)

2011-08-15T23:59:59.000Z

292

Positive design  

Science Conference Proceedings (OSTI)

This article is focused on the changes needed in design to create positive solutions for all involved in design processes. It draws upon the rich discussion and discourse from a conference focused on positive design involving managers, designers, and ...

Jurgen Faust

2009-09-01T23:59:59.000Z

293

Hanford External Dosimetry Technical Basis Manual PNL-MA-842  

SciTech Connect

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 PNNLs 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 PNNLs 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.

Rathbone, Bruce A.

2010-01-01T23:59:59.000Z

294

Propane Market Outlook Assessment of Key Market Trends, Threats, and Opportunities Facing  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

0 0 Propane Market Outlook Assessment of Key Market Trends, Threats, and Opportunities Facing the Propane Industry Through 2020 P r e s e n T e d B y : Declining Sales in the Recent Past and Near-Term Future After peaking in 2003, nationwide propane consumption fell by more than 10 percent through 2006. Although propane demand rebounded somewhat in 2007 and 2008 due to colder weather, propane demand appears to have declined again in 2009. The collapse of the new housing market, combined with decreases in fuel use per customer resulting from efficiency upgrades in homes and equipment, resulted in a decline in residential propane sales. The recession also reduced demand in the industrial and commercial sectors. Colder weather in the last half of 2009 and in January

295

Responding to the threat of global warming: Options for the Pacific and Asia  

SciTech Connect

During the past few years, global climate change has rapidly been transformed from an esoteric topic of interest mainly to scientists to one of worldwide concern to policymakers, the business communities, the media, and the general public. In response to this heightened interest, a number of high-level international meetings dealing with this issue have been held in the past two years. With growing recognition that the global climate change phenomenon would result in different regional (and local) effects, a workshop was organized by Argonne National Laboratory and the East-West Center to assess the likely consequences of this threat and the possible remediation options available to the countries of the Pacific Asia. This paper summarizes the deliberations and conclusion of the workshop, which was held at the East-West center in Honolulu, Hawaii, from June 21--27, 1989. 35 refs., 4 figs.

Bhatti, N.; Streets, D.G.; Siddiqi, T.A. (Argonne National Lab., IL (USA); Environment and Policy Inst., Honolulu, HI (USA))

1989-01-01T23:59:59.000Z

296

Does nitrate deposition following astrophysical ionizing radiation events pose an additional threat to amphibians?  

E-Print Network (OSTI)

It is known that amphibians are especially susceptible to the combination of heightened UVB radiation and increased nitrate concentrations. Various astrophysical events have been suggested as sources of ionizing radiation that could pose a threat to life on Earth, through destruction of the ozone layer and subsequent increase in UVB, followed by deposition of nitrate. In this study, we investigate whether the nitrate deposition following an ionizing event is sufficiently large to cause an additional stress beyond that of the heightened UVB previously considered. We have converted predicted nitrate depositions to concentration values, utilizing data from the New York State Department of Environmental Conservation Acid Rain Monitoring Network web site. Our results show that the increase in nitrate concentration in bodies of water following the most intense ionization event likely in the last billion years would not be sufficient to cause a serious additional stress on amphibian populations and may actually provide some benefit by acting as fertilizer.

Brian C. Thomas; Michelle D. Honeyman

2008-04-22T23:59:59.000Z

297

Amphibian nitrate stress as an additional terrestrial threat from astrophysical ionizing radiation events?  

E-Print Network (OSTI)

As diversity in amphibian species declines, the search for causes has intensified. Work in this area has shown that amphibians are especially susceptible to the combination of heightened UVB radiation and increased nitrate concentrations. Various astrophysical events have been suggested as sources of ionizing radiation that could pose a threat to life on Earth, through destruction of the ozone layer and subsequent increase in UVB, followed by deposition of nitrate. In this study, we investigate whether the nitrate deposition following an ionizing event is sufficiently large to cause an additional stress beyond that of the heightened UVB previously considered. We have converted predicted nitrate depositions to concentration values, utilizing data from the New York State Department of Environmental Conservation Acid Rain Monitoring Network web site. Our results show that the increase in nitrate concentration in bodies of water following the most intense ionization event likely in the last billion years would no...

Thomas, Brian C

2008-01-01T23:59:59.000Z

298

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Basis for Identification of Disposal Options for R and D for Spent 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 barrier, and the waste. Salt, clay/shale, and granitic rocks represent a reasonable cross-section of behavior. Granitic rocks are also the primary basement rock to consider for deep borehole disposal. UFD is developing generic system analysis capability and general experimental data related to mined geologic disposal in the three

299

Technical Basis for Assessing Uranium Bioremediation Performance  

SciTech Connect

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.

PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL NGuessan

2008-04-01T23:59:59.000Z

300

Applications of Systems Engineering to the Research, Design,...  

NLE Websites -- All DOE Office Websites (Extended Search)

will take place. It also provides a basis for forming team structures and a vehicle for subsequent communication and interaction on refining and implementing the design...

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

SRS FTF Section 3116 Basis for Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

FTF Section 3116 Basis for Determination FTF Section 3116 Basis for Determination SRS FTF Section 3116 Basis for Determination 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-level waste if the Secretary of Energy, in consultation with the NRC, determines that the criteria in NDAA Section 3116(a) are met. This FTF 3116 Basis Document shows that those criteria are satisfied, to support a determination that the Secretary may make pursuant to NDAA Section 3116. This FTF 3116 Basis Document concerns the stabilized residuals in waste tanks and ancillary structures, those waste tanks, and the ancillary structures (including integral equipment) at the SRS FTF at the time of closure.

302

Groebner Basis Conversion with FGLM - CECM - Simon Fraser ...  

E-Print Network (OSTI)

Groebner Basis Conversion with FGLM. Roman Pearce, MITACS project. Simon Fraser University. The FGLM algorithm of Faugere, Gianni, Lazard and Mora,...

303

Evaluation of Authorization Basis Management Systems and Processes...  

NLE Websites -- All DOE Office Websites (Extended Search)

related to authorization basis was identified in the 1996 Office of Oversight safety management evaluation of the Pantex Plant. The Defense Nuclear Facilities Safety Board (DNFSB)...

304

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Safety Basis - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix C to...

305

Review of Safety Basis Development for the Savannah River Site...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Department of Energy Subject: Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility - Inspection Criteria, Approach, and Line: HS: Rev:...

306

Microsoft Word - Final_SRS_FTF_WD_Basis_March_2012  

NLE Websites -- All DOE Office Websites (Extended Search)

TED Total Effective Dose TEDE Total Effective Dose Equivalent TER Technical Evaluation Report TNX Training and Experimental Test Facility U.S. United States Basis for Section...

307

CRAD, Review of Safety Basis Development- May 6, 2013  

Energy.gov (U.S. Department of Energy (DOE))

Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility (HSS CRAD 45-59, Rev. 0)

308

Independent Oversight Review of Hanford Tank Farms Safety Basis...  

NLE Websites -- All DOE Office Websites (Extended Search)

Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades November 2011 Office of Safety and Emergency Management Evaluations Office of...

309

Evolutionary Design Systems and Generative Processes  

Science Conference Proceedings (OSTI)

Design tools that aim not only to analyse and evaluate, but also to generate and explore alternative design proposals are now under development. An evolutionary paradigm is presented as a basis for creating such tools. First, the evolutionary paradigm ... Keywords: design, environment, evolution, generative, search

Patrick Janssen; John Frazer; Tang Ming-xi

2002-01-01T23:59:59.000Z

310

The Sensitivity of the Number of Correctly Forecasted Events to the Threat Score:A Practical Application  

Science Conference Proceedings (OSTI)

The sensitivity (S) of the number of correctly forecast events (hits) to changes in threat score is explored. An emphasis is placed on the practical utility of S for end users of operational systems who may need to further assess a system's ...

Joby L. Hilliker

2004-06-01T23:59:59.000Z

311

Slide 1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Northwest National Laboratory "Implications of Design Basis Threat on Critical Infrastructure and Homeland Security" Note * The context of this presentation doe not represent...

312

Page not found | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Implementation of the 2003 Design Basis Threat http:energy.govigdownloadsspecial-report-ig-0705 Article National Coal Council Meeting Remarks As Prepared By Deputy Energy...

313

Audit Report: IG-0749 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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...

314

Alex opened the meeting and asked for introductions by the Group  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

(SSA), will be developing transportation assessments following various on-going intelligence reviews. John answered questions and explained that the NRC Design Basis Threat...

315

Prediction of Critical Desalination Parameters Using Radial Basis Functions Networks  

Science Conference Proceedings (OSTI)

Prediction of critical desalination parameters (recovery and salt rejection) of two distinct processes based on real operational data is presented. The proposed method utilizes the radial basis function network using data clustering and histogram equalization. ... Keywords: neural network, radial basis, reverse osmosis

Mutaz M. Jafar; Ali Zilouchian

2002-06-01T23:59:59.000Z

316

FHR Generic Design Criteria  

SciTech Connect

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.

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

2012-06-15T23:59:59.000Z

317

FHR Generic Design Criteria  

Science Conference Proceedings (OSTI)

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.

Flanagan, George F [ORNL; Holcomb, David Eugene [ORNL; Cetiner, Mustafa Sacit [ORNL

2012-06-01T23:59:59.000Z

318

CRAD, Facility Safety - Nuclear Facility Safety Basis | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis 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. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Facility Safety - Nuclear Facility Safety Basis More Documents & Publications CRAD, Facility Safety - Unreviewed Safety Question Requirements Site Visit Report, Livermore Site Office - February 2011 FAQS Job Task Analyses - Nuclear Safety Specialist

319

CRAD, Safety Basis - Los Alamos National Laboratory Waste Characterization,  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Basis - Los Alamos National Laboratory Waste Basis - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility CRAD, Safety Basis - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility 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. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Safety Basis - Los Alamos National Laboratory Waste Characterization,

320

Exploring continuum structures with a pseudo-state basis  

SciTech Connect

The ability of a recently developed square-integrable discrete basis to represent the properties of the continuum of a two-body system is investigated. The basis is obtained performing a simple analytic local scale transformation to the harmonic oscillator basis. Scattering phase-shifts and the electric transition probabilities B(E1) and B(E2) have been evaluated for several potentials using the proposed basis. Both quantities are found to be in excellent agreement with the exact values calculated from the true scattering states. The basis has been applied to describe the projectile continuum in the {sup 6}He scattering by {sup 12}C and {sup 208}Pb targets at 240 MeV/nucleon and the {sup 11}Be scattering by {sup 12}C at 67 MeV/nucleon. The calculated breakup differential cross sections are found to be in very good agreement with the available experimental data for these reactions.

Lay, J. A.; Moro, A. M.; Arias, J. M.; Gomez-Camacho, J. [Departamento de FAMN, Facultad de Fisica, Universidad de Sevilla, Apdo. 1065, E-41080 Sevilla (Spain); Departamento de FAMN, Facultad de Fisica, Universidad de Sevilla, Apdo. 1065, E-41080 Sevilla, Spain and Centro Nacional de Aceleradores, Avda. Thomas A. Edison, E-41092, Sevilla (Spain)

2010-08-15T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

U.S. Department of U.S. Department of Energy Office of Independent Oversight Criteria Review and Approach Document 1.0 PURPOSE Within the Office of Independent Oversight, the Office of Environment, Safety and Health (ES&H) Evaluations' mission is to assess the effectiveness of environment, safety, and health systems and practices used by line and contractor organizations in implementing Integrated Safety Management and to provide clear, concise, and independent evaluations of performance in protecting our workers, the public, and the environment from the hazards associated with Department of Energy (DOE) activities and sites. A key to success is the rigor and comprehensiveness of our process; and as with any process, we continually strive to improve and provide additional value and insight to field operations. Integral to this is our commitment to

322

Engineering work plan and design basis for 241-SY ventilation improvements  

DOE Green Energy (OSTI)

There are three tanks in the 241-SY tank farm. Tank 241-SY101 and 241-SY-103 are flammable gas watch list tanks. Tank 241-SY-102 is included in the ventilation improvement process in an effort to further control air flow in the tank farm. This tank farm has only one outlet ventilation port for all three tanks. Flammable gas is released (may be steady and/or periodic) from the waste in the primary tank vapor space. The gas is removed from the tank by an active ventilation system. However, maintaining consistent measurable flow through the tank can be problematic due to the poor control capabilities of existing equipment. Low flow through the tank could allow flammable gas to build up in the tank and possibly exceed the lower flammability limit (LFL), prevent the most rapid removal of flammable gas from the tank after a sudden gas release, and/or cause high vacuum alarms to sound. Using the inlet and outlet down stream butterfly valves performs the current method of controlling flow in tank farm 241-SY. A filter station is installed on the inlet of each tank, but controlling air flow with its 12 inch butterfly valve is difficult. There is also in-leakage through pump and valve pits. Butterfly valves on the downstream side of each tank could also be used to control air flow. However, their large size and the relatively low air velocity make this control method also ineffective. The proposed method of optimizing tank air flow and pressure control capability is to install an air flow controller on the inlet of each existing filter station in SY farm, and seal as best as practical all other air leakage paths. Such air flow controllers have been installed on 241-AN and 241-AW tanks (see drawing H-2-85647).

Andersen, J.A.

1997-05-19T23:59:59.000Z

323

MATERIAL-FLOW DATA STRUCTURES AS A BASIS FOR ENERGY INFORMATION SYSTEM DESIGN  

E-Print Network (OSTI)

materials, petroleum products, are traced from their sourcepetroleum model:(a)- Storage; (b)- Transportation; (c)- Source; (petroleum products, volume of oil (or product) storage and voltme in transit, geographic source

Krishnan, V.V.

2013-01-01T23:59:59.000Z

324

MATERIAL-FLOW DATA STRUCTURES AS A BASIS FOR ENERGY INFORMATION SYSTEM DESIGN  

E-Print Network (OSTI)

control theory [2] Between crude oil production or productAs Figure 1 shows, total crude oil available for domesticproduced crude and the crude oil imported from abroad minus

Krishnan, V.V.

2013-01-01T23:59:59.000Z

325

Fish schooling as a basis for vertical axis wind turbine farm design  

E-Print Network (OSTI)

Most wind farms consist of horizontal axis wind turbines (HAWTs) due to the high power coefficient (mechanical power output divided by the power of the free-stream air through the turbine cross-sectional area) of an isolated turbine. However when in close proximity to neighbouring turbines, HAWTs suffer from a reduced power coefficient. In contrast, previous research on vertical axis wind turbines (VAWTs) suggests that closely-spaced VAWTs may experience only small decreases (or even increases) in an individual turbine's power coefficient when placed in close proximity to neighbours, thus yielding much higher power outputs for a given area of land. A potential flow model of inter-VAWT interactions is developed to investigate the effect of changes in VAWT spatial arrangement on the array performance coefficient, which compares the expected average power coefficient of turbines in an array to a spatially-isolated turbine. A geometric arrangement based on the configuration of shed vortices in the wake of schooli...

Whittlesey, Robert W; Dabiri, John O

2010-01-01T23:59:59.000Z

326

MATERIAL-FLOW DATA STRUCTURES AS A BASIS FOR ENERGY INFORMATION SYSTEM DESIGN  

E-Print Network (OSTI)

K PIPELINE 121 W ~ GULF C " EXXON OF " 2/2/79 FIGURE 3.flows gasoline to and from Exxon facilities in New Jersey;of suppliers and customers for Exxon's New Jersey gasoline

Krishnan, V.V.

2013-01-01T23:59:59.000Z

327

MATERIAL-FLOW DATA STRUCTURES AS A BASIS FOR ENERGY INFORMATION SYSTEM DESIGN  

E-Print Network (OSTI)

control theory [2] Between crude oil production or productvalidation and error from Oil in the system is considered tounits or "packets" Each oil packet has associated with it a

Krishnan, V.V.

2013-01-01T23:59:59.000Z

328

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

Energy.gov (U.S. Department of Energy (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.

329

Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events, August 2011  

Energy.gov (U.S. Department of Energy (DOE))

The U.S. Department of Energy (DOE) has established a rigorous nuclear safety regulatory infrastructure for the protection of workers, the public, and the environment. Part of this infrastructure...

330

MATERIAL-FLOW DATA STRUCTURES AS A BASIS FOR ENERGY INFORMATION SYSTEM DESIGN  

E-Print Network (OSTI)

flows among individual refineries we have only monthly datauntil its con(>umption at the refinery inlet, and the post-from their source at the refinery outlet. Imported oil is

Krishnan, V.V.

2013-01-01T23:59:59.000Z

331

MATERIAL-FLOW DATA STRUCTURES AS A BASIS FOR ENERGY INFORMATION SYSTEM DESIGN  

E-Print Network (OSTI)

we have analyzed the U.S. petroleum supply and distributiongeneralizability. Quantized petroleum flows among restrictedan analysis of the U.S. petroleum supply and distr bution

Krishnan, V.V.

2013-01-01T23:59:59.000Z

332

Fusion Engineering and Design 38 (1997) 2757 Physics basis for a reversed shear tokamak power plant  

E-Print Network (OSTI)

fusion power plant. Analysis of plasma equilibrium and ideal MHD stability, bootstrap current and current the recirculating power fraction. The final plasma configuration for the ARIES-RS power plant obtains i of 4 frequency fast wave current drive to obtain maximum current profile flexibility, requiring 580 MW of power

California at San Diego, University of

333

Safety evaluation of MHTGR licensing basis accident scenarios  

SciTech Connect

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.

Kroeger, P.G.

1989-04-01T23:59:59.000Z

334

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

SciTech Connect

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.

Banzi, Firmi Paul (Tanzania Atomic Energy Commission Arusha, United Republic of Tanzania); Itamura, Michael Takeshi (U.S. Department of Energy National Nuclear Security Administration, Washington, DC); Robinson, Phillip W. (U.S. Department of Energy National Nuclear Security Administration, Washington, DC); Strosinski, Micheal Vernon

2010-06-01T23:59:59.000Z

335

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

SciTech Connect

A psychosocial model was developed to assess an employees 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 models assessment with computer workstation behavior to raise the efficacy of recognizing an insider crime in the making.

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

2010-09-01T23:59:59.000Z

336

Threat of a sinkhole: A reevaluation of Cavern 4, Bayou Choctaw salt dome, Louisiana  

Science Conference Proceedings (OSTI)

Cavern Lake at Bayou Choctaw salt dome resulted from the failure of Cavern 7 in 1954. Uncontrolled solutioning of this cavern through the thin caprock had set the stage for overburden to collapse into the cavern below. A similar situation developed with nearby Cavern 4, but with less dissolutioning of the caprock. Because pressure loss was already a problem and because another 800 ft diameter lake would have endangered surface operations, solutioning of Cavern 4 was stopped and the cavern abandoned in 1957 in order to protect the already-small site. In 1978 the Strategic Petroleum Reserve (SPR) acquired a number of caverns at Bayou Choctaw, including Cavern 4, and the possible repeat of the Cavern 7 failure and formation of another lake thus became an issue. The cavern dimensions were re-sonared in 1980 for comparison with 1963 and 1977 surveys. Annual surface leveling between 1982--1992 showed less subsidence occurring than the site average, and a cavern monitoring system, installed in 1984, has revealed no anomalous motion. Repeat sonar surveys in 1992 showed very little, if any, change occurred since 1980 although a small amount of uncertainty exists as a result of changing sonar techniques. We conclude that significant additional solutioning or erosion of the caprock has not occurred and that there is no increased threat to SPR operations.

Neal, J.T.; Todd, J.L.; Linn, J.K. [Sandia National Labs., Albuquerque, NM (United States); Magorian, T.R. [Magorian (Thomas R.), Amherst, NY (United States)

1993-09-01T23:59:59.000Z

337

Underwater Threat Source Localization: Processing Sensor Network TDOAs with a Terascale Optical Core Device  

Science Conference Proceedings (OSTI)

Revolutionary computing technologies are defined in terms of technological breakthroughs, which leapfrog over near-term projected advances in conventional hardware and software to produce paradigm shifts in computational science. For underwater threat source localization using information provided by a dynamical sensor network, one of the most promising computational advances builds upon the emergence of digital optical-core devices. In this article, we present initial results of sensor network calculations that focus on the concept of signal wavefront time-difference-of-arrival (TDOA). The corresponding algorithms are implemented on the EnLight processing platform recently introduced by Lenslet Laboratories. This tera-scale digital optical core processor is optimized for array operations, which it performs in a fixed-point-arithmetic architecture. Our results (i) illustrate the ability to reach the required accuracy in the TDOA computation, and (ii) demonstrate that a considerable speed-up can be achieved when using the EnLight 64a prototype processor as compared to a dual Intel XeonTM processor.

Barhen, Jacob [ORNL; Imam, Neena [ORNL

2007-01-01T23:59:59.000Z

338

The need for carbon dioxide disposal: A threat and an opportunity  

SciTech Connect

Ready energy is a cornerstone of modern society. The policies outlined at the recent Kyoto conference have put in question the largest, most readily available and most cost-effective energy resource available. Even if a doubling of atmospheric CO{sub 2} is deemed acceptable, emission reductions worldwide would have to be drastic. For 10 billion people to share equally into the 1990 emission level would allow a per capita emission of 10% of the current US level. Substantial reductions in CO{sub 2} emissions to the atmosphere are unavoidable. Uncertain is the time available to accomplish this reduction. There are also reasons to be optimistic about the future of coal and other fossil fuels. Barring a surprise technological breakthrough in alternative energies, fossil energy consumption is bound to grow. Political and economic drivers even stronger than the threat of climate change favor economic growth and therefore increased energy consumption. To resolve this apparent contradiction requires new technologies that prevent CO{sub 2} generated by combustion from entering the atmosphere. The authors will outline available technologies and show how the coal industry can adapt to them.

Lackner, K.S.; Butt, D.P.; Wendt, C.H.

1998-08-01T23:59:59.000Z

339

Microsoft Word - Final_SRS_FTF_WD_Basis_March_2012  

NLE Websites -- All DOE Office Websites (Extended Search)

2-001 2-001 Revision 0 Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site March 2012 Basis for Section 3116 Determination DOE/SRS-WD-2012-001 for Closure of F-Tank Farm Revision 0 at the Savannah River Site March 2012 Page ii REVISION SUMMARY REV. # DESCRIPTION DATE OF ISSUE 0 Initial Issue March 2012 Basis for Section 3116 Determination DOE/SRS-WD-2012-001 for Closure of F-Tank Farm Revision 0 at the Savannah River Site March 2012 Page iii TABLE OF CONTENTS Page REVISION SUMMARY ................................................................................................................................. ii LIST OF TABLES ........................................................................................................................................ vi

340

Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy  

Science Conference Proceedings (OSTI)

The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system.

TRAWINSKI, B.J.

2000-02-08T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Idaho Accelerated Retrieval Project Phase II CRAD, Safety Basis - Idaho Accelerated Retrieval Project Phase II February 2006 A section of Appendix C to DOE G 226.1-2 "Federal Line...

342

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

Energy.gov (U.S. Department of Energy (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)

343

A Theoretical Basis for Household Energy Conservation UsingProduct...  

NLE Websites -- All DOE Office Websites (Extended Search)

A Theoretical Basis for Household Energy Conservation Using Product-Integrated Feedback Speaker(s): Teddy McCalley Date: October 11, 2002 - 12:00pm Location: Bldg. 90 Seminar Host...

344

A BIM-Based Design Method for Energy-Efficient Building  

Science Conference Proceedings (OSTI)

Nowadays, global warming and high oil prices were a threat to the survival of the whole human race. One of a solution to respond to these problems is to reduce energy consumption of building. By adopting energy-saving design, the dissemination of low ... Keywords: BIM, Low Energy Building

Seunghyun Yoon; Namhee Park; Jinwon Choi

2009-08-01T23:59:59.000Z

345

Efficient Software Implementation for Finite Field Multiplication in Normal Basis  

E-Print Network (OSTI)

Abstract. Finite field arithmetic is becoming increasingly important in today's computer systems, particularly for implementing cryptographic operations. Among various arithmetic operations, finite field multiplication is of particular interest since it is a major building block for elliptic curve cryptosystems. In this paper, we present new techniques for efficient software implementation of binary field multiplication in normal basis. Our techniques are more efficient in terms of both speed and memory compared with alternative approaches. 1 Introduction Finite field arithmetic is becoming increasingly important in today's computer systems, particularly for implementing cryptographic operations. Among the more common finite fields in cryptography are odd-characteristic finite fields of degree 1 and even-characteristic finite fields of degree greater than 1. The latter is conventionally known as GF (2m) arithmetic or binary field arithmetic. GF (2m) arithmetic is further classified according to the choice of basis for representing elements of the finite field; two common choices are polynomial basis and normal basis. Fast implementation techniques for GF (2m) arithmetic have been studied intensively in the past twenty years. Among various arithmetic operations, GF (2m) multiplication has attracted most of the attention since it is a major building block for implementing elliptic curve cryptosystems. Depending on the choice of basis, the mathematical formula for a GF (2m) multiplication can be quite different, thus making major differences in practical implementation. Currently, it seems that normal basis representation (especially optimal normal basis) offers the best performance in hardware [9-11], while in software polynomial basis representation is more efficient [2, 3, 8].

Peng Ning; Yiqun Lisa Yin

2001-01-01T23:59:59.000Z

346

Technical Basis Document for PFP Area Monitoring Dosimetry Program  

Science Conference Proceedings (OSTI)

This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

COOPER, J.R.

2000-04-17T23:59:59.000Z

347

Redesign of Organizations as a Basis for Organizational Change  

Science Conference Proceedings (OSTI)

Artificial Intelligence has contributed (formal) design models and software support tools to application areas such as architecture, engineering and software design This paper explores the effectiveness of applying design models to the area of organization ...

Mark Hoogendoorn; Catholijn M. Jonker; Jan Treur

2007-01-01T23:59:59.000Z

348

Javascript Design  

Science Conference Proceedings (OSTI)

From the Publisher:JavaScript Design shows designers how to create interactive JavaScript applications for the Web. It provides detailed descriptions of:JavaScript structures, statements and objectsUsing JavaScript to create different ...

Bill B. Sanders

2001-12-01T23:59:59.000Z

349

Tilting at Modern: Elizabeth Gordon's "The Threat to the Next America"  

E-Print Network (OSTI)

a house that used passive solar heating, and which could beallowed for passive solar heating in winter: ?The architectsthem passive solar design and radiant floor heating. 33 The

Corbett, Kathleen LaMoine

2010-01-01T23:59:59.000Z

350

Experimental design  

Science Conference Proceedings (OSTI)

Maximizing data information requires careful selection, termed design, of the points at which data are observed. Experimental design is reviewed here for broad classes of data collection and analysis problems, including: fractioning techniques ... Keywords: Key Design Issues in Data Mining, Science and Technology, Statistical Fundamentals

J. P. Morgan; Xinwei Deng

2012-03-01T23:59:59.000Z

351

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

NLE Websites -- All DOE Office Websites (Extended Search)

Privacy/Security Statement Privacy/Security Statement 5th International REAC/TS Symposium: The Medical Basis for Radiation Accident Preparedness Skip site navigation and move to main content of page. Home Schedule Speakers Registration Directions and Acommodations Contact 5th International REAC/TS Symposium: The Medical Basis for Radiation Accident Preparedness Sept. 27-29, 2011 Hilton Miami Downtown Miami, Florida United States Introduction This symposium brings together international experts to discuss the advances in the diagnosis and management of radiation emergencies and illnesses. The Oak Ridge Institute for Science and Education (ORISE) designates this live activity for a maximum of 19.25 AMA PRA Category 1 Credit(s)(tm). Physicians should claim only the credit commensurate with the extent of

352

Designing Creativity  

E-Print Network (OSTI)

Is it possible to design for creativity? This is one of the most important research questions in AI and Design. This paper raises the question whether automated software agent design can be creative. Not only is the artefact dynamic in the sense that it adapts to its environment, it is also autonomous: an agent decides on its own when to be modified and by whom. An agent's functionality may evolve beyond the expectations of its designers and/or users resulting in very new, unique artefacts. Is this type of design creative? Is the process creative? The result? 1.

Frances M. T. Brazier; Niek J. E. Wijngaards

2002-01-01T23:59:59.000Z

353

Conceptual design. Final report: TFE Verification Program  

DOE Green Energy (OSTI)

This report documents the TFE Conceptual Design, which provided the design guidance for the TFE Verification program. The primary goals of this design effort were: (1) establish the conceptual design of an in-core thermionic reactor for a 2 Mw(e) space nuclear power system with a 7-year operating lifetime; (2) demonstrate scalability of the above concept over the output power range of 500 kW(e) to 5 MW(e); and (3) define the TFE which is the basis for the 2 MW (e) reactor design. This TFE specification provided the basis for the test program. These primary goals were achieved. The technical approach taking in the conceptual design effort is discussed in Section 2, and the results are discussed in Section 3. The remainder of this introduction draws a perspective on the role that this conceptual design task played in the TFE Verification Program.

Not Available

1994-03-01T23:59:59.000Z

354

Computer-aided-design of flywheels  

Science Conference Proceedings (OSTI)

We have presented in this work, a computer-aided-design software for flywheels using object-oriented programming approach of Visual Basic. The various configurations of flywheels (rimmed or solid) formed the basis for the development of the software. ... Keywords: Computer-aided-design, Flywheels, Object-oriented programming, Speed fluctuation, Stress

John A. Akpobi; Imafidon A. Lawani

2006-04-01T23:59:59.000Z

355

Computer-aided-design of flywheels  

Science Conference Proceedings (OSTI)

We have presented in this work, a computer-aided-design software for flywheels using object-oriented programming approach of Visual Basic. The various configurations of flywheels (rimmed or solid) formed the basis for the development of the software. ... Keywords: computer-aided-design, flywheels, object-oriented programming, speed fluctuation, stress

John A. Akpobi; Imafidon A. Lawani

2006-04-01T23:59:59.000Z

356

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reactor Contractor ORR Reactor Contractor ORR CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 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. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

357

BASIS: Backscattering Spectrometer at SNS | ORNL Neutron Sciences  

NLE Websites -- All DOE Office Websites (Extended Search)

Backscattering Spectrometer Backscattering Spectrometer View inside the BAIS tank View inside the BASIS tank. BASIS is a near-backscattering, crystal-analyzer spectrometer that provides very fine energy resolution, as low as 3.0 to 3.5 µeV at the elastic peak (depending on sample size). This requires a long initial guide section of 84 m from moderator to sample in order to achieve the timing resolution necessary for obtaining the desired energy resolution. BASIS provides an excellent dynamic range near the elastic peak of about plus and minus 100 µeV in the standard high-intensity operation regime, which, if needed, could be extended to plus and minus 200 µeV and beyond. The spectrometer is optimized for quasielastic scattering but provides about 0.1% resolution in energy transfers up to ~40 meV; the inelastic excitations need to be

358

Investigation of Electromagnetic Field Threat to Fuel Tank Wiring of a Transport Aircraft  

Science Conference Proceedings (OSTI)

National Transportation Safety Board investigators have questioned whether an electrical discharge in the Fuel Quantity Indication System (FQIS) may have initiated the TWA-800 center wing tank explosion. Because the FQIS was designed to be incapable ...

Ely Jay J.; Nguyen Truong X.; Dudley Kenneth L.; Scearce Stephen A.; Beck Fred B.; Deshpande Manohar D.; Cockrell C. R.

2000-03-01T23:59:59.000Z

359

A Radial Basis Function Method for Global Optimization  

Science Conference Proceedings (OSTI)

We introduce a method that aims to find the global minimum of a continuous nonconvex function on a compact subset of \\dRd. It is assumed that function evaluations are expensive and that no additional information is available. ... Keywords: Global optimization, P-algorithm, interpolation, radial basis functions

H.-M. Gutmann

2001-03-01T23:59:59.000Z

360

Hierarchical Structure for function approximation using radial basis function  

Science Conference Proceedings (OSTI)

The hierarchial network proposed (Multi-RBFNN), is composed of complete Radial Basis Function Neural Networks (RBFNNs) that are in charge of a reduced set of input variables with the property of which every Sub-RBFNN can take charge of a set of input ... Keywords: function approximation, hierarchical architectures, input variable selection, radial bases functions

A. Awad; H. Pomares; I. Rojas; L. J. Herrera; A. Guillen; O. Valenzuela

2005-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Design Specifications  

NLE Websites -- All DOE Office Websites (Extended Search)

Design Design Specifications Services Overview ECS Audio/Video Conferencing Fasterdata IPv6 Network Network Performance Tools (perfSONAR) ESnet OID Registry PGP Key Service Virtual Circuits (OSCARS) OSCARS Case Study Documentation User Manual FAQ Design Specifications Functional Specifications Notifications Publications Authorization Policy Default Attributes Message Security Clients For Developers Interfaces Links Hardware Requirements DOE Grids Service Transition Contact Us Technical Assistance: 1 800-33-ESnet (Inside the US) 1 800-333-7638 (Inside the US) 1 510-486-7600 (Globally) 1 510-486-7607 (Globally) Report Network Problems: trouble@es.net Provide Web Site Feedback: info@es.net Design Specifications OSCARS Reservation Manager - Design Specifications Year 3 Update (DRAFT) David Robertson, Chin Guok

362

Review of Safety Basis Development for the Los Alamos National...  

NLE Websites -- All DOE Office Websites (Extended Search)

surveillance requirements, administrative controls, and specific administrative controls provided and technically accurate? * Are the facility design aspects necessary to...

363

Review of Safety Basis Development for the Savannah River Site...  

NLE Websites -- All DOE Office Websites (Extended Search)

surveillance requirements, administrative controls, and specific administrative controls provided and technically accurate? * Are the facility design aspects necessary to...

364

Audit Report: IG-0749  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Energy, Science, Energy, Science, and Environment Sites' Implementation of the Design Basis Threat DOE/IG-0749 December 2006 Department of Energy Washington, DC 20585 December 14, 2006 MEMORANDUM FOR .13HEfiECREJARY 4 - Crregor . Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "'I'he Department's Energy, Science, and Environment Sites' Implenneritation of the Design Basis Threat" BACKGROUND 'Phe Department of Energy uses the "Design Basis Threat" (DBT) process to guide and manage its safeguards and security program throughout the complex. The DBT identifies the most credible threats posed by adversaries to highly sensitive and classified Departmental qssets and operations. In essence, the DBT sets the standards that site

365

REVIEW ARTICLE Ozone depletion and increased UV-B radiation: is there a real threat to photosynthesis?  

E-Print Network (OSTI)

on photosynthetic competence or light-interception. It is concluded that O depletion and the concurrent rise This critical review of recent literature questions earl-3 in UV-B irradiance is not a direct threat to photosynier predictions that photosynthetic productivity of thetic productivity of crops and natural vegetation. higher plants is vulnerable to increased ultraviolet-B (UV-B) radiation as a result of stratospheric ozone (O) 3 Key words: Biomass, development, ozone depletion, depletion. Direct UV-B-induced inhibition of photosyn- photosynthesis, ultraviolet-B. thetic competence is observed only at high UV-B irradiances and primarily involves the loss of soluble Calvin

Damian J. Allen; Salvador Nogus; Neil R. Baker

1998-01-01T23:59:59.000Z

366

Agricultural pathogen decontamination technology-reducing the threat of infectious agent spread.  

Science Conference Proceedings (OSTI)

Outbreaks of infectious agricultural diseases, whether natural occurring or introduced intentionally, could have catastrophic impacts on the U.S. economy. Examples of such agricultural pathogens include foot and mouth disease (FMD), avian influenza (AI), citrus canker, wheat and soy rust, etc. Current approaches to mitigate the spread of agricultural pathogens include quarantine, development of vaccines for animal diseases, and development of pathogen resistant crop strains in the case of plant diseases. None of these approaches is rapid, and none address the potential persistence of the pathogen in the environment, which could lead to further spread of the agent and damage after quarantine is lifted. Pathogen spread in agricultural environments commonly occurs via transfer on agricultural equipment (transportation trailers, tractors, trucks, combines, etc.), having components made from a broad range of materials (galvanized and painted steel, rubber tires, glass and Plexiglas shields, etc), and under conditions of heavy organic load (mud, soil, feces, litter, etc). A key element of stemming the spread of an outbreak is to ensure complete inactivation of the pathogens in the agricultural environment and on the equipment used in those environments. Through the combination of enhanced agricultural pathogen decontamination chemistry and a validated inactivation verification methodology, important technologies for incorporation as components of a robust response capability will be enabled. Because of the potentially devastating economic impact that could result from the spread of infectious agricultural diseases, the proposed capability components will promote critical infrastructure protection and greater border and food supply security. We investigated and developed agricultural pathogen decontamination technologies to reduce the threat of infectious-agent spread, and thus enhance agricultural biosecurity. Specifically, enhanced detergency versions of the patented Sandia decontamination chemistry were developed and tested against a few surrogate pathogens under conditions of relatively heavy organic load. Tests were conducted on surfaces commonly found in agricultural environments. Wide spectrum decontamination efficacy, low corrosivity, and biodegradability issues were addressed in developing an enhanced detergency formulation. A method for rapid assessment of loss of pathogenic activity (inactivation) was also assessed. This enhanced technology will enable rapid assessment of contamination following an intentional event, and will also be extremely useful in routine assessment of agricultural environments. The primary effort during the second year was progress towards a demonstration of both decontamination and viral inactivation technologies of Foot and Mouth virus (FMDv) using the modified SNL chemistry developed through this project. Lab studies using a surrogate virus (bovine enterovirus) were conducted using DF200, modified DF200 chemistry, and decontaminants currently recommended for use in heavily loaded organic, agricultural environments (VirkonS, 10% bleach, sodium hydroxide and citric acid). Tests using actual FMD virus will be performed at the Department of Homeland Security's Plum Island facilities in the fall of 2005. Success and the insight gained from this project will lead to enhanced response capability, which will benefit agencies such as USDA, DHS, DOD, and the agricultural industry.

Betty, Rita G.; Bieker, Jill Marie; Tucker, Mark David

2005-10-01T23:59:59.000Z

367

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

Science Conference Proceedings (OSTI)

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.

LEONARD, M.W.

2000-03-14T23:59:59.000Z

368

The detailed evaluation criteria for designation of critical information infrastructure in the field of broadcasting and communication  

Science Conference Proceedings (OSTI)

Increasing to dependency on information infrastructures involves various threats to cyber incidents. Most of nations or organizations work on protect to not only infrastructure but also information infrastructure. Korea established Critical Information ... Keywords: CII (critical information infrastructure), CIIP (CII protection), cyber incident, cyber security, designation criteria, information assets

Soontai Park; Wan S. Yi; Bong-Nam Noh

2010-02-01T23:59:59.000Z

369

Engitectural Design  

E-Print Network (OSTI)

Traditionally, Architecture and Engineering have been disciplines practiced exclusive of one another's input and collaboration. This seemingly awkward custom is due in part to tradition and to the two distinct perspectives each discipline has concerning the function of a building and it's many components. In the past, collaboration on a project generally occurred out of necessity, and can usually be attributed to a system and design integration problems. In most instances, these issues are related to the mechanical systems of building, and in a hot and humid climate the issues are magnified. Therefore, this paper will discuss the concepts and merits of a new design process called: Engitectural Design. Engitectural Design is the concept of blending the many design and aesthetic concerns of architecture with the more technical aspects of engineering, especially in the area of mechanical HVAC systems. The use of this new design procedure will reduce, if not eliminate, current problems with clearances, mechanical room size and optimal area selection. Merely incorporating the mechanical needs of a building during the schematic phase will reduce communication problems that cause the above mentioned problems, and thus optimize the system. This paper will address the mutual concerns of both professions as it pertains to materials, lighting, surface finishes, passive and active solar and the use of landscaping, focusing on the benefits of mutual agreement in a hot and humid climate. To be successful, the collaboration must begin in pre-design and continue through project completion. During initial implementation of Engitectural Design, a fm can expect each phase of a project to take longer than usual. Lack of established relationships, poor communication and professional territorial rights will exist in the beginning. However, over time a fm can expect a time reduction due to fewer revisions and the elimination of duplicated work. As it pertains to today's more advanced HVAC systems, this new cooperation and understanding of the needs within disciplines will yield a more effective and efficient operating unit for today's hot and humid environment.

Gagliardi, D. R.

1996-01-01T23:59:59.000Z

370

The use of mutation in testing experiments and its sensitivity to external threats  

Science Conference Proceedings (OSTI)

Mutation analysts has emerged as a standard approach for empirical assessment of testing techniques. The test practitioners decide about cost-effectiveness of testing strategies based on the number of mutants the testing techniques detect. Though fundamental ... Keywords: experimental design, hand-seeded faults, mutants, mutation testing, real faults, statistical analysis

Akbar Siami Namin; Sahitya Kakarla

2011-07-01T23:59:59.000Z

371

Biological Basis for Radiation Adaptive Responses that Protect Against  

NLE Websites -- All DOE Office Websites (Extended Search)

Basis for Radiation Adaptive Responses that Protect Against Basis for Radiation Adaptive Responses that Protect Against Bronchial Epithelial Cell Transformation Wenshu Chen Lovelace Respiratory Research Institute Abstract The major hypothesis in this project is that low-dose, low linear-energy-transfer (LET) radiation stimulates an adaptive response that protects cells from neoplastic transformation involving modulation of paracrine factors (e.g., cytokines), cell survival/death signaling pathways, and reprogramming of the epigenome. To test this hypothesis, a validated, sensitive in vitro transformation model and a media transfer method were used to study the mechanisms of low-LET gamma radiation activated natural protection (ANP) against chemical carcinogen-induced bronchial cell transformation. Immortalized human bronchial epithelial cell

372

Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5506-2007 5506-2007 April 2007 DOE STANDARD Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities U.S. Department of Energy Washington, D.C. 20585 AREA-SAFT DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-5506-2007 ii Available on the Department of Energy Technical Standards Program Web Site at Http://tis.eh.doe.gov/techstds/ DOE-STD-5506-2007 iii Foreword This Standard provides analytical assumptions and methods, as well as hazard controls to be used when developing Safety Basis (SB) documents for transuranic (TRU) waste facilities in the U.S. Department of Energy (DOE) Complex. It also provides supplemental technical

373

Technical Basis for DOE Policy 420.1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HS-0006 HS-0006 TECHNICAL BASIS FOR U.S. DEPARTMENT OF ENERGY NUCLEAR SAFETY POLICY, DOE POLICY 420.1 U.S. DEPARTMENT OF ENERGY OFFICE OF HEALTH, SAFETY AND SECURITY OFFICE OF NUCLEAR SAFETY JULY 2011 i Executive Summary 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. In developing the revised Policy and performing this analysis, DOE reviewed the current Nuclear

374

The reduced basis method for the electric field integral equation  

Science Conference Proceedings (OSTI)

We introduce the reduced basis method (RBM) as an efficient tool for parametrized scattering problems in computational electromagnetics for problems where field solutions are computed using a standard Boundary Element Method (BEM) for the parametrized electric field integral equation (EFIE). This combination enables an algorithmic cooperation which results in a two step procedure. The first step consists of a computationally intense assembling of the reduced basis, that needs to be effected only once. In the second step, we compute output functionals of the solution, such as the Radar Cross Section (RCS), independently of the dimension of the discretization space, for many different parameter values in a many-query context at very little cost. Parameters include the wavenumber, the angle of the incident plane wave and its polarization.

Fares, M., E-mail: fares@cerfacs.f [2 Avenue Gaspard Coriolis, 31057 Toulouse Cedex 01 (France); Hesthaven, J.S., E-mail: Jan_Hesthaven@Brown.ed [Division of Applied Mathematics, Brown University, Box F, Providence, RI 02912 (United States); Maday, Y., E-mail: maday@ann.jussieu.f [Laboratoire Jacques-Louis Lions, Universite Pierre et Marie Curie, Boite courrier 18, 75252 Paris Cedex 05 (France); Stamm, B., E-mail: stamm@math.berkeley.ed [Department of Mathematics, University of California, Berkeley, CA 94720 (United States)

2011-06-20T23:59:59.000Z

375

Engineering basis for selection of positron source material  

Science Conference Proceedings (OSTI)

This note describes the engineering basis for the selection of the positron source material. It assumes the approximate physics parameters have already been chosen (i.e. a high Z material of 6 radiation lengths thickness). As part of this study a basic heat transfer analysis of the target was performed and is discussed. It is concluded that Ta-10W is the most likely material to meet required physics parameters and not fail structurally.

Feerick, B.

1983-10-10T23:59:59.000Z

376

Evolution of Safety Basis Documentation for the Fernald Site  

SciTech Connect

The objective of the Department of Energy's (DOE) Fernald Closure Project (FCP), in suburban Cincinnati, Ohio, is to safely complete the environmental restoration of the Fernald site by 2006. Over 200 out of 220 total structures, at this DOE plant site which processed uranium ore concentrates into high-purity uranium metal products, have been safely demolished, including eight of the nine major production plants. Documented Safety Analyses (DSAs) for these facilities have gone through a process of simplification, from individual operating Safety Analysis Reports (SARs) to a single site-wide Authorization Basis containing nuclear facility Bases for Interim Operations (BIOs) to individual project Auditable Safety Records (ASRs). The final stage in DSA simplification consists of project-specific Integrated Health and Safety Plans (I-HASPs) and Nuclear Health and Safety Plans (N-HASPs) that address all aspects of safety, from the worker in the field to the safety basis requirements preserving the facility/activity hazard categorization. This paper addresses the evolution of Safety Basis Documentation (SBD), as DSAs, from production through site closure.

Brown, T.; Kohler, S.; Fisk, P.; Krach, F.; Klein, B.

2004-03-01T23:59:59.000Z

377

Appraisal of the Uranium Processing Facility Safety Basis Preliminary...  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Design Report Process at the Y-12 National Security Complex May 2011 May 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and...

378

Strategic Basis for License Application Planning for a Potential Yucca Mountain Repository  

SciTech Connect

If Yucca Mountain, Nevada is designated as the site for development of a geologic repository for disposal of spent nuclear fuel and high-level radioactive waste, the Department of Energy (DOE) must obtain Nuclear Regulatory Commission (NRC) approval first for repository construction, then for an operating license, and, eventually, for repository closure and decommissioning. The licensing criteria defined in Code of Federal Regulations, Title 10, Part 63 (10 CFR Part 63) establish the basis for these NRC decisions. Submittal of a license application (LA) to the NRC for authorization to construct a repository at the Yucca Mountain site is, at this point, only a potential future action by the DOE. The policy process defined in the Nuclear Waste Policy Act (NWPA), as amended, for recommendation and designation of Yucca Mountain as a repository site makes it difficult to predict whether or when the site might be designated. The DOE may only submit a LA to the NRC if the site designation takes effect. In spite of this uncertainty, the DOE must take prudent and appropriate action now, and over the next several years, to prepare for development and timely submittal of a LA. This is particularly true given the need for the DOE to develop, load, and certify the operation of its electronic information system to provide access to its relevant records as part of the licensing support network (LSN) in compliance with NRC requirements six months prior to LA submittal. The DOE must also develop a LA, which is a substantially different document from those developed to support a Site Recommendation (SR) decision. The LA must satisfy NRC licensing criteria and content requirements, and address the acceptance criteria defined by the NRC in its forthcoming Yucca Mountain Review Plan (YMRP). The content of the LA must be adequate to facilitate NRC acceptance and docketing for review, and the LA and its supporting documents must provide the documented basis for the NR C findings required for a construction authorization. The LA must also support a licensing proceeding before an Atomic Safety and Licensing Board panel prior to NRC action on any decision to authorize construction. The DOE has established a strategic basis for planning that is intended to provide the framework for development of an integrated plan for activities leading to preparation and submittal of a LA.

Newberry, C. M.; Brocoum, S. J.; Gamble, R. P.; Murray, R. C.; Cline, M.

2002-02-26T23:59:59.000Z

379

Architecture in the era of terror: Design and perception of security in two societies  

E-Print Network (OSTI)

This dissertation falls in the realm of environmental behavior and focuses on the role of the built environment in influencing responses to threats to personal security associated with terrorism. The research integrates pertinent knowledge from psychology, architecture and security/terrorism into a cohesive conceptual framework. Based on the conceptual framework, this work examined the effects of levels of terrorism threat (high vs. low) on people who face public buildings (city hall or shopping mall) that vary in their facade and entrance designs (solid exterior vs. glass facade with/without designed vs. temporary access control security measures). The research was conducted in two societies that are different in their experience with terrorism (Israel and Texas). The effects were measured along four dimensions: how much the issue of terrorism threat is on a person?s mind, how safe and how anxious the individual feels, and how likely he/she is to use the building. The investigation consisted of three quasi-experiments and a pretest survey and employed a computer-based web driven platform. A total of 1071 undergraduate students from College Station, Texas and Tel Aviv, Israel participated in these studies. The results illustrate the predominance of the levels of threat of terrorism in influencing all the examined security-related responses. The characteristics of buildings affected those responses to some extent. Differences between the two societies were found mainly in relation to the building-uses. Participants of the two societies responded similarly to the design elements of buildings. In conditions of low threat of terrorism participants from both societies had a higher sense of security when they were exposed to a glass facade compared to a solid concrete facade. In high terrorism threat, participants from both societies felt safer, and were more inclined to use a building with a solid facade. However, when access control security measures were visible to participants in the approach to the building (regardless of their design), both facade designs elicited a similar sense of security, while the propensity to enter the building was higher towards a glass facade. The study concludes with a discussion of the implications of the results for architectural design.

Zilbershtein, Gali

2009-05-01T23:59:59.000Z

380

Business Case Slide 8: High-Volume: Repository - Basis for Use  

NLE Websites -- All DOE Office Websites (Extended Search)

Volume: Repository - Basis for Use Basis for use DUO2 in or near cask should be a geochemical barrier Establish reducing conditions Inhibit spent fuel dissolution Keep...

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP  

SciTech Connect

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

Kessler, S

2009-04-21T23:59:59.000Z

382

Space design  

Science Conference Proceedings (OSTI)

Space stations, Moon bases and Mars bases are artificial habitats intended to support human life in extreme conditions. Their purpose is to pursue human progress and to gain knowledge and experience of the environment surrounding our planet. This research ... Keywords: Human factors, Interior design, Space habitability, Sustainability, Vision

Irene Lia Schlacht; Henrik Birke

2011-06-01T23:59:59.000Z

383

RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT  

Science Conference Proceedings (OSTI)

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.

KOZLOWSKI, S.D.

2007-05-30T23:59:59.000Z

384

Software engineering education: Rles of formal specification and design calculi  

Science Conference Proceedings (OSTI)

This paper analyses current principles of software development: from domains via requirements to design. On the basis of this analysis we outline a structure and contents of professional software engineering. From this we extract some requirements ...

Dines Bjrner; Jorge R. Cullar

1999-04-01T23:59:59.000Z

385

Reactor protection system design alternatives for sodium fast reactors  

E-Print Network (OSTI)

Historically, unprotected transients have been viewed as design basis events that can significantly challenge sodium-cooled fast reactors. The perceived potential consequences of a severe unprotected transient in a ...

DeWitte, Jacob D. (Jacob Dominic)

2011-01-01T23:59:59.000Z

386

Interim safety basis for fuel supply shutdown facility  

SciTech Connect

This ISB in conjunction with the new TSRs, will provide 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. It is concluded that the risk associated with the current operational mode of the Facility, uranium closure, clean up, and transition activities required for permanent closure, are within Risk Acceptance Guidelines. The Facility is classified as a Moderate Hazard Facility because of the potential for an unmitigated fire associated with the uranium storage buildings.

Brehm, J.R.; Deobald, T.L.; Benecke, M.W.; Remaize, J.A.

1995-05-23T23:59:59.000Z

387

Low-Cost, Robust, Threat-Aware Wireless Sensor Network for Assuring the Nation's Energy Infrastructure  

SciTech Connect

Eaton, in partnership with Oak Ridge National Laboratory and the Electric Power Research Institute (EPRI) has completed a project that applies a combination of wireless sensor network (WSN) technology, anticipatory theory, and a near-term value proposition based on diagnostics and process uptime to ensure the security and reliability of critical electrical power infrastructure. Representatives of several Eaton business units have been engaged to ensure a viable commercialization plan. Tennessee Valley Authority (TVA), American Electric Power (AEP), PEPCO, and Commonwealth Edison were recruited as partners to confirm and refine the requirements definition from the perspective of the utilities that actually operate the facilities to be protected. Those utilities have cooperated with on-site field tests as the project proceeds. Accomplishments of this project included: (1) the design, modeling, and simulation of the anticipatory wireless sensor network (A-WSN) that will be used to gather field information for the anticipatory application, (2) the design and implementation of hardware and software prototypes for laboratory and field experimentation, (3) stack and application integration, (4) develop installation and test plan, and (5) refinement of the commercialization plan.

Carols H. Rentel

2007-03-31T23:59:59.000Z

388

A New Basis of Geoscience: Whole-Earth Decompression Dynamics  

E-Print Network (OSTI)

Neither plate tectonics nor Earth expansion theory is sufficient to provide a basis for understanding geoscience. Each theory is incomplete and possesses problematic elements, but both have served as stepping stones to a more fundamental and inclusive geoscience theory that I call Whole-Earth Decompression Dynamics (WEDD). WEDD begins with and is the consequence of our planet's early formation as a Jupiter-like gas giant and permits deduction of:(1) Earth's internal composition, structure, and highly-reduced oxidation state; (2) Core formation without whole-planet melting; (3) Powerful new internal energy sources - proto-planetary energy of compression and georeactor nuclear fission energy; (4) Georeactor geomagnetic field generation; (5) Mechanism for heat emplacement at the base of the crust resulting in the crustal geothermal gradient; (6) Decompression driven geodynamics that accounts for the myriad of observations attributed to plate tectonics without requiring physically-impossible mantle convection, and; (7) A mechanism for fold-mountain formation that does not necessarily require plate collision. The latter obviates the necessity to assume supercontinent cycles. Here, I review the principles of Whole-Earth Decompression Dynamics and describe a new underlying basis for geoscience and geology.

J. Marvin Herndon

2013-07-04T23:59:59.000Z

389

Physics Basis for Advanced and Conventional Operating Modes  

E-Print Network (OSTI)

of projected Power Plant designs · Only address technological issues required for successful device operation ­ Fueling, pumping, power handling, plasma control, neutronics, materials, remote handling, and safety.13 and growth time is 43

390

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

Science Conference Proceedings (OSTI)

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.

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

2010-01-31T23:59:59.000Z

391

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

SciTech Connect

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.

Schmidt, Andrew J.; Zacher, Alan H.

2007-06-25T23:59:59.000Z

392

Mechanical Design  

SciTech Connect

The particle beam of the SXR (soft x-ray) beam line in the LCLS (Linac Coherent Light Source) has a high intensity in order to penetrate through samples at the atomic level. However, the intensity is so high that many experiments fail because of severe damage. To correct this issue, attenuators are put into the beam line to reduce this intensity to a level suitable for experimentation. Attenuation is defined as 'the gradual loss in intensity of any flux through a medium' by [1]. It is found that Beryllium and Boron Carbide can survive the intensity of the beam. At very thin films, both of these materials work very well as filters for reducing the beam intensity. Using a total of 12 filters, the first 9 being made of Beryllium and the rest made of Boron Carbide, the beam's energy range of photons can be attenuated between 800 eV and 9000 eV. The design of the filters allows attenuation for different beam intensities so that experiments can obtain different intensities from the beam if desired. The step of attenuation varies, but is relative to the thickness of the filter as a power function of 2. A relationship for this is f(n) = x{sub 0}2{sup n} where n is the step of attenuation desired and x{sub 0} is the initial thickness of the material. To allow for this desired variation, a mechanism must be designed within the test chamber. This is visualized using a 3D computer aided design modeling tool known as Solid Edge.

2010-08-25T23:59:59.000Z

393

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3011-2002 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. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161;

394

Online Monitoring Technical Basis and Analysis Framework for Large Power  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

for Large 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) research and development efforts in the Long-Term Operations (LTO) Program. The LTO Program is managed as a separate technical program operating in the Plant Technology Department of the EPRI Nuclear Power Sector with the guidance of an industry advisory Integration Committee. Because both the Department of Energy Office of Nuclear Energy and EPRI conduct research and development in technologies

395

Online Monitoring Technical Basis and Analysis Framework for Emergency  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

for 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 (EPRI's) research and development efforts in the Long-Term Operations Program. The Long-Term Operations Program is managed as a separate technical program operating in the Plant Technology Department of the EPRI Nuclear Power Sector with the guidance of an industry advisory Integration Committee. Because both the Department of Energy Office of Nuclear Energy and EPRI conduct research and development

396

High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2  

Science Conference Proceedings (OSTI)

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B. [Mitre Corp., McLean, VA (United States)

1995-06-01T23:59:59.000Z

397

Carbon Tax and 100% Dividend No Alligator Shoes! The charts for my talk (Climate Threat to the Planet: Implications for Energy Policy) on 3  

E-Print Network (OSTI)

Carbon Tax and 100% Dividend ­ No Alligator Shoes! The charts for my talk (Climate ThreatPACON_20080603.ppt The "Carbon Tax and 100% Dividend" chart warrants discussion. Tax and dividend is the policy complement that must accompany recognition of fossil carbon reservoir sizes for strategic solution of global

Hansen, James E.

398

Safety-Basis Thermal Analysis for KE Basin Sludge Transport and Storage  

DOE Green Energy (OSTI)

A series of safety-basis thermal and gas generation analyses were completed and independently reviewed to assess the thermal performance of a large diameter container (LDC) containing KE Basin sludge. The results demonstrate: (1) the sludge transport system (STS) containing a LDC can safely transport a KE basin sludge payload up to 2.0 m{sup 3} and, (2) large diameter containers with sludge payloads up to 2.0 m{sup 3} can be safely stored in a process cell at T Plant. The transport and storage analyses are based on a conservative set of assumptions, including limiting environmental conditions. Conclusions drawn from the transport and storage results were not impacted by changes in the radial gap between the cask and LDC, purge gas (i.e., either helium or nitrogen), sludge porosity, or thermal conductivity. The design of the transport cask and large diameter container can accommodate reasonable changes in these values. Both transport from KE Basin and long-term storage at T Plant are addressed for sludge payloads up to 2.0 m{sup 3}. Additional analyses determined the expected range of T Plant environmental temperatures, the hydrogen and oxygen generation rate due to the radiolysis of water, and the maximum hydrogen concentration within a process cell due to chemical reactions and the radiolysis of water. All sludge temperature and hydrogen concentration criteria for transport and storage are met. The analyses assumed a safety-basis sludge mixture defined as 60% by volume floor and 40% by volume canister sludge with 35% retained gas, and a conservative segregated (axial) distribution of metallic uranium (resulting from particulate settling) with associated safety-basis properties. The analyses recognized that the retrieval process would produce non-uniform sludge distributions. Four batch process loadings of 0.5m{sup 3} each are assumed. Each process batch loading will settle and segregate (separate) into two layers: an active layer containing all the metallic uranium which is chemically active, and a non-active layer containing uranium oxide, non-uranium material, and no metallic uranium. This is a conservative representation of operational controls designed to limit the metallic uranium concentration. The sludge layers are assumed to remain intact during transport and storage.

HEARD, F.J.; SATHYANARAYANA, J.J.

2002-09-30T23:59:59.000Z

399

Solving Basis Pursuit: Heuristic Optimality Check and Solver ...  

E-Print Network (OSTI)

Dec 21, 2012 ... 1 Institute for Analysis and Algebra, TU Braunschweig, Germany ... cope with this problem by designing the test set in such a way that the .... An alternative is based on l1-norm concentration: For a fixed ..... the solution path ? : ? x ... all deterministic pivot rules, see, e.g., [21]), reflecting the possible...

400

Scientists Model the Molecular Basis of Parkinson's Disease  

E-Print Network (OSTI)

through the Innovative and Novel Computational Impact on Theory and Experiment (IN- CITE) program-energy physics, materials science, and nuclear physics. Among these top researchers were leads from the national· of thermal-energy loss in tokomak fu- sion reactors, with implications for the design of the $10 billion

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Structural basis of substrate discrimination and integrin binding by autotaxin  

SciTech Connect

Autotaxin (ATX, also known as ectonucleotide pyrophosphatase/phosphodiesterase-2, ENPP2) is a secreted lysophospholipase D that generates the lipid mediator lysophosphatidic acid (LPA), a mitogen and chemoattractant for many cell types. ATX-LPA signaling is involved in various pathologies including tumor progression and inflammation. However, the molecular basis of substrate recognition and catalysis by ATX and the mechanism by which it interacts with target cells are unclear. Here, we present the crystal structure of ATX, alone and in complex with a small-molecule inhibitor. We have identified a hydrophobic lipid-binding pocket and mapped key residues for catalysis and selection between nucleotide and phospholipid substrates. We have shown that ATX interacts with cell-surface integrins through its N-terminal somatomedin B-like domains, using an atypical mechanism. Our results define determinants of substrate discrimination by the ENPP family, suggest how ATX promotes localized LPA signaling and suggest new approaches for targeting ATX with small-molecule therapeutic agents.

Hausmann, Jens; Kamtekar, Satwik; Christodoulou, Evangelos; Day, Jacqueline E.; Wu, Tao; Fulkerson, Zachary; Albers, Harald M.H.G.; van Meeteren, Laurens A.; Houben, Anna J.S.; van Zeijl, Leonie; Jansen, Silvia; Andries, Maria; Hall, Troii; Pegg, Lyle E.; Benson, Timothy E.; Kasiem, Mobien; Harlos, Karl; Vander Kooi, Craig W.; Smyth, Susan S.; Ovaa, Huib; Bollen, Mathieu; Morris, Andrew J.; Moolenaar, Wouter H.; Perrakis, Anastassis (Pfizer); (Leuven); (Oxford); (NCI-Netherlands); (Kentucky)

2013-09-25T23:59:59.000Z

402

Hanford Technical Basis for Multiple Dosimetry Effective Dose Methodology  

SciTech Connect

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).

Hill, Robin L.; Rathbone, Bruce A.

2010-08-01T23:59:59.000Z

403

System design description PFP thermal stabilization  

SciTech Connect

The purpose of this document is to provide a system design description and design basis for the Plutonium Finishing P1ant (PFP) Thermal Stabilization project. The sources of material for this project are residues scraped from glovebox floors and materials already stored in vault storage that need further stabilizing to meet the 3013 storage requirements. Stabilizing this material will promote long term storage and reduced worker exposure. This document addresses: function design, equipment, and safety requirements for thermal stabilization of plutonium residues and oxides.

RISENMAY, H.R.

1998-11-10T23:59:59.000Z

404

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

Science Conference Proceedings (OSTI)

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

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

2009-09-01T23:59:59.000Z

405

Business Case Slide 23: High-Value: Catalysts - Basis for Use  

NLE Websites -- All DOE Office Websites (Extended Search)

Catalysts - Basis for Use Basis for use DUO2 has previously been used as a catalyst Dissociation of volatile organic compounds and nitrogen oxides in off-gas streams Oxidation of...

406

Business Case Slide 30: High-Value: Energy Uses - Basis for Use  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Uses - Basis for Use DUO2 battery test cell at U. Kentucky DUO2 battery test cell at U. Kentucky Basis for use Capable of sustaining high temperatures Electronic properties...

407

Optimizing Radial Basis Functions by D.C. Programming and its use ...  

E-Print Network (OSTI)

Oct 6, 2009 ... the use of derivative-free models based on radial basis functions .... known, one can use a radial basis functions (RBF) model of the form m(x) =.

408

Design Scenarios: Enabling transparent parametric design spaces  

Science Conference Proceedings (OSTI)

This paper presents a novel methodology called Design Scenarios (DSs) intended for use in conceptual design of buildings. DS enables multidisciplinary design teams to streamline the requirements definition, alternative generation, analysis, and decision-making ... Keywords: Conceptual design, Design spaces, Ontology, Parametric modeling, Process mapping, Requirements modeling

Victor Gane; John Haymaker

2012-08-01T23:59:59.000Z

409

Design Reconstitution Program Plan and procedures for K Basins  

SciTech Connect

This document establishes a systematic program to establish, organize, and document the design basis and design requirement information for the K Basins where existing design information is inadequate. The Design Reconstitution Program involves identifying and retrieving design information from identified source documents; evaluating, verifying, and validating the design information; resolving discrepancies; regenerating missing critical design information; and preparing and issuing a summary document of the design information. Upon completion, the design requirements shall be evaluated with the facility as-found configuration to verify the adequacy of appropriate design requirements with the as-found configuration and to document and resolve any discovered discrepancies. Once the design requirement (design analysis, calculation, design basis) comparison is made and discrepancies resolved (dispositioned, implemented, and incorporated as required), the as-found condition of a drawing then becomes an as-built drawing that is released into the engineering release system. This as-built drawing is then the accurate accounting of the field configuration that is consistent with the design requirements (recovered through the design reconstitution program) and is used with high confidence to make valid engineering, operational, and maintenance decisions.

Laney, T.

1995-01-12T23:59:59.000Z

410

Design of Thermal Power Generation Device for Vehicle Recharging  

Science Conference Proceedings (OSTI)

With thermal power generation as the basis, vehicle heat sources (such as engine and exhaust pipe) as the carrier, and AT89C52 as the control center, this paper has designed a thermal power generation device for vehicle recharging. This device consists ... Keywords: thermal power generation, power supply for recharging, vehicle devices, design

Hong Fang

2012-07-01T23:59:59.000Z

411

Model-based optimisation of Wastewater Treatment Plants design  

Science Conference Proceedings (OSTI)

This paper presents the mathematical basis and some illustrative examples of a model-based decision-making method for the automatic calculation of optimum design parameters in modern Wastewater Treatment Plants (WWTP). The starting point of the proposed ... Keywords: Mathematical modelling, Optimum design, Wastewater Treatment Plants

A. Rivas; I. Irizar; E. Ayesa

2008-04-01T23:59:59.000Z

412

Nuclear Facility Safety Basis Fundamentals Self-Study Guide - November 2002  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oak Ridge Operations Office 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)] November 2002 Nuclear Facility Safety Basis Fundamentals Self-Study Guide TABLE OF CONTENTS Acronyms and Abbreviations ......................................................................................... iii List of Figures ....................................................................................................................iv List of Tables......................................................................................................................iv INTRODUCTION..............................................................................................................1

413

Efficient basis for the Dicke Model I: theory and convergence in energy  

E-Print Network (OSTI)

An extended bosonic coherent basis has been shown by Chen to provide numerically exact solutions of the finite-size Dicke model. The advantages in employing this basis, as compared with the photon number (Fock) basis, are exhibited to be valid for a large region of the Hamiltonian parameter space by analyzing the converged values of the ground state energy.

Miguel Angel Bastarrachea-Magnani; Jorge G. Hirsch

2013-12-06T23:59:59.000Z

414

Molecular basis for activation of G protein-coupled receptor kinases  

E-Print Network (OSTI)

Molecular basis for activation of G protein-coupled receptor kinases Cassandra A Boguth1,3 , Puja regulated by acti- vated GPCRs, but the molecular basis for this interaction is not understood. Herein, we to discriminate between active and inactive GPCRs. The molecular basis for how these protein families can identify

Rosenberg, Noah

415

Optimized local basis set for Kohn-Sham density functional theory  

Science Conference Proceedings (OSTI)

We develop a technique for generating a set of optimized local basis functions to solve models in the Kohn-Sham density functional theory for both insulating and metallic systems. The optimized local basis functions are obtained by solving a minimization ... Keywords: Discontinuous Galerkin, Electronic structure, GMRES, Kohn-Sham density functional theory, Molecular dynamics, Optimized local basis set, Preconditioning, Pulay force, Trace minimization

Lin Lin; Jianfeng Lu; Lexing Ying; Weinan E

2012-05-01T23:59:59.000Z

416

Solar Design Standards for State Buildings | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Solar Design Standards for State Buildings Solar Design Standards for State Buildings Solar Design Standards for State Buildings < Back Eligibility Construction Schools State Government Savings Category Heating & Cooling Home Weatherization Construction Commercial Weatherization Commercial Heating & Cooling Design & Remodeling Solar Lighting Windows, Doors, & Skylights Heating Buying & Making Electricity Water Heating Program Info State Arizona Program Type Energy Standards for Public Buildings Provider Arizona Department of Commerce Arizona law requires that new state building projects over six thousand square feet follow prescribed solar design standards. Solar improvements should be evaluated on the basis of life cycle costs. Affected buildings include buildings designed and constructed by the department of

417

Basis for the US Modern Grid Strategy - A Changing World  

NLE Websites -- All DOE Office Websites (Extended Search)

Importance of Smart Grid to Our Nation's Energy Future 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. Department of Energy estimates that 70% of the transmission lines and transformers are over 25 years old and 60% of the circuit breakers are over 30 years old (Lightner, DOE, Jan 2005). The nation's electricity grid is under increasing stress and is being asked to perform functions that it

418

Technical Basis of Scaling Relationships for the Pretreatment Engineering Platform  

Science Conference Proceedings (OSTI)

Pacific Northwest National Laboratory has been tasked by Bechtel National Inc. (BNI) on the River Protection Project-Waste Treatment Plant (RPP-WTP) project to perform research and development activities. The Pretreatment Engineering Platform (PEP) is being designed and constructed as part of a plan to respond to an issue raised by the WTP External Flowsheet Review Team (EFRT) entitled Undemonstrated Leaching Processes and numbered M12. The PEP replicates the WTP leaching process using prototypic equipment and control strategies. The approach for scaling PEP performance data to predict WTP performance is critical to the successful resolution of the EFRT issue. This report describes the recommended PEP scaling approach, PEP data interpretation and provides recommendations on test conduct and data requirements.

Kuhn, William L.; Arm, Stuart T.; Huckaby, James L.; Kurath, Dean E.; Rassat, Scot D.

2008-07-15T23:59:59.000Z

419

ATW neutronics design studies.  

SciTech Connect

The Accelerator Transmutation of Waste (ATW) concept has been proposed as a transuranics (TRU) (and long-lived fission product) incinerator for processing the 87,000 metric tonnes of Light Water Reactor used fuel which will have been generated by the time the currently deployed fleet of commercial reactors in the US reach the end of their licensed lifetime. The ATW is proposed to separate the uranium from the transuranics and fission products in the LWR used fuel, to fission the transuranics, to send the LWR and ATW generated fission products to the geologic repository and to send the uranium to either a low level waste disposal site or to save it for future use. The heat liberated in fissioning the transuranics would be converted to electricity and sold to partially offset the cost of ATW construction and operations. Options for incineration of long-lived fission products are under evaluation. A six-year science-based program of ATW trade and system studies was initiated in the US FY 2000 to achieve two main purposes: (1) ''to evaluate ATW within the framework of nonproliferation, waste management, and economic considerations,'' and (2) ''to evaluate the efficacy of the numerous technical options for ATW system configuration.'' This paper summarizes the results from neutronics and thermal/hydraulics trade studies which were completed at Argonne National Laboratory during the first year of the program. Core designs were developed for Pb-Bi cooled and Na cooled 840 MW{sub th} fast spectrum transmuter designs employing recycle. Additionally, neutronics analyses were performed at Argonne for a He cooled 600 MW{sub th} hybrid thermal and fast core design proposed by General Atomics Co. which runs critical for 3/4 and subcritical for 1/4 of its four year once-thin burn cycle. The mass flows and the ultimate loss of transuranic isotopes to the waste stream per unit of heat generated during transmutation have been calculated on a consistent basis and are compared. (Long-lived fission product incineration has not been considered in the studies reported here.)

Wade, D. C.; Yang, W. S.; Khalil, H.

2000-11-10T23:59:59.000Z

420

The Evolving Virus Threat  

Science Conference Proceedings (OSTI)

... The message subject might say try this cool game, it's fun! 3 ... Furthermore, the availablility of powerful PCs in virtually every household has lowered ...

2000-11-03T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Asians Resist Nuclear Threat  

E-Print Network (OSTI)

Midway carries soma 100 nuclear weapons and the missiles onthe removal of U. S. nuclear weapons from Asia. It is ti-aeof U. S. tactical nuclear weapons This set the figure for

Schirmer, Daniel Boone

1981-01-01T23:59:59.000Z

422

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

Science Conference Proceedings (OSTI)

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.

NONE

1995-01-31T23:59:59.000Z

423

Rainout assessment: the ACRA system and summaries of simulation results. [Computer systems to estimate threats from precipitation scavenging of radioactive debris clouds from nuclear weapons  

SciTech Connect

A generalized, three-dimensional, integrated computer code system was developed to estimate collateral-damage threats from precipitation-scavenging (rainout) of airborne debris-clouds from defensive tactical nuclear engagements. This code system, called ACRA for Atmospheric-Contaminant Rainout Assessment, is based on Monte Carlo statistical simulation methods that allow realistic, unbiased simulations of probabilistic storm, wind, and precipitation fields that determine actual magnitudes and probabilities of rainout threats. Detailed models (or data bases) are included for synoptic-scale storm and wind fields; debris transport and dispersal (with the roles of complex flow fields, time-dependent diffusion, and multidimensional shear effects accounted for automatically); microscopic debris-precipitation interactions and scavenging probabilities; air-to-ground debris transport; local demographic features, for assessing actual threats to populations; and nonlinear effects accumulations from multishot scenarios. We simulated several hundred representative shots for West European scenarios and climates to study single-shot and multishot sensitivities of rainout effects to variations in pertinent physical variables.

Watson, C.W.; Barr, S.; Allenson, R.E.

1977-09-01T23:59:59.000Z

424

Tutorial Design Windows - CECM  

E-Print Network (OSTI)

Tutorial Design Windows: Activity 2: Activity 2 Design Window Return to tutorial. Exercise 1: Exercise 1 Design Window Return to exercises. Exercise 2: Exercise ...

425

Design and analysis tool validation  

DOE Green Energy (OSTI)

The Solar Energy Research Institute (SERI) is developing a procedure for the validation of Building Energy Analysis Simulation Codes (BEAS). These codes are being used increasingly in the building design process, both directly and as the basis for simplified design tools and guidelines. The importance of the validity of the BEAS in predicting building energy performance is obvious when one considers the money and energy that could be wasted by energy-inefficient designs. However, to date, little or no systematic effort has been made to ensure the validity of the various BEAS. The validation work at SERI consists of three distinct parts: Comparative Study, Analytical Verification, and Empirical Validation. The procedures have been developed for the first two parts and have been implemented on a sampling of the major BEAS; results have shown major problems in one of the BEAS tested. Furthermore, when one building design was run using several of the BEAS, large differences were found in the predicted annual cooling and heating loads. The empirical validation procedure has been developed, and five two-zone test cells have been constructed for validation; a summer validation run will take place as soon as the data acquisition system is completed. Additionally, a test validation exercise is now in progress using the low-cal house to fine-tune the empirical validation procedure and better define monitoring data requirements.

Judkoff, R.

1981-07-01T23:59:59.000Z

426

Structural Basis of Cell Wall Cleavage by a Staphylococcal  

E-Print Network (OSTI)

The major autolysins (Atl) of Staphylococcus epidermidis and S. aureus play an important role in cell separation, and their mutants are also attenuated in virulence. Therefore, autolysins represent a promising target for the development of new types of antibiotics. Here, we report the high-resolution structure of the catalytically active amidase domain AmiE (amidase S. epidermidis) from the major autolysin of S. epidermidis. This is the first protein structure with an amidase-like fold from a bacterium with a gram-positive cell wall architecture. AmiE adopts a globular fold, with several a-helices surrounding a central b-sheet. Sequence comparison reveals a cluster of conserved amino acids that define a putative binding site with a buried zinc ion. Mutations of key residues in the putative active site result in loss of activity, enabling us to propose a catalytic mechanism. We also identified and synthesized muramyltripeptide, the minimal peptidoglycan fragment that can be used as a substrate by the enzyme. Molecular docking and digestion assays with muramyltripeptide derivatives allow us to identify key determinants of ligand binding. This results in a plausible model of interaction of this ligand not only for AmiE, but also for other PGN-hydrolases that share the same fold. As AmiE active-site mutations also show a severe growth defect, our findings provide an excellent platform for the design of specific inhibitors that target staphylococcal cell

Sebastian Zoll; Bernhard Ptzold; Martin Schlag; Friedrich Gtz; Hubert Kalbacher

2010-01-01T23:59:59.000Z

427

Simplicity in interaction design  

Science Conference Proceedings (OSTI)

Attaining simplicity is a key challenge in interaction design. Our approach relies on a minimalist design exercise to explore the communication capacity for interaction components. This approach results in expressive design solutions, useful perspectives ... Keywords: expressiveness, interface design, simplicity, usability

Angela Chang; James Gouldstone; Jamie Zigelbaum; Hiroshi Ishii

2007-02-01T23:59:59.000Z

428

Conceptual and computational basis for the quantification of margins and uncertainty.  

Science Conference Proceedings (OSTI)

In 2001, the National Nuclear Security Administration of the U.S. Department of Energy in conjunction with the national security laboratories (i.e, Los Alamos National Laboratory, Lawrence Livermore National Laboratory and Sandia National Laboratories) initiated development of a process designated Quantification of Margins and Uncertainty (QMU) for the use of risk assessment methodologies in the certification of the reliability and safety of the nation's nuclear weapons stockpile. This presentation discusses and illustrates the conceptual and computational basis of QMU in analyses that use computational models to predict the behavior of complex systems. Topics considered include (1) the role of aleatory and epistemic uncertainty in QMU, (2) the representation of uncertainty with probability, (3) the probabilistic representation of uncertainty in QMU analyses involving only epistemic uncertainty, (4) the probabilistic representation of uncertainty in QMU analyses involving aleatory and epistemic uncertainty, (5) procedures for sampling-based uncertainty and sensitivity analysis, (6) the representation of uncertainty with alternatives to probability such as interval analysis, possibility theory and evidence theory, (7) the representation of uncertainty with alternatives to probability in QMU analyses involving only epistemic uncertainty, and (8) the representation of uncertainty with alternatives to probability in QMU analyses involving aleatory and epistemic uncertainty. Concepts and computational procedures are illustrated with both notional examples and examples from reactor safety and radioactive waste disposal.

Helton, Jon Craig (Arizona State University, Tempe, AZ)

2009-06-01T23:59:59.000Z

429

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

Science Conference Proceedings (OSTI)

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.

Hickey, Eva E.; Strom, Daniel J.

2005-08-01T23:59:59.000Z

430

A criterion for determining exceedance of the operating basis earthquake: Final report  

Science Conference Proceedings (OSTI)

A criterion is recommended for determining whether the Operating Basis Earthquake (OBE) has been exceeded after the occurrence of a seismic event at a nuclear power plant. The technical procedure provides a fast and effective means for assessing the damage potential of any ''felt'' earthquake in the first few hours after occurrence. For OBE exceedance to occur, the recommended criterion requires exceedance of both a response spectrum parameter and a second damage parameter, referred to as the Cumulative Absolute Velocity (CAV). The detailed operational requirements for implementing the criterion are provided. The criterion was developed, based on a study of earthquake damage to conventional buildings, review of past damage to power plants and heavy industrial facilities, blast damage, fragility data and equipment vibration performance, to ensure that ground motions greater than Modified Mercalli Intensity VI are conservatively identified as exceeding the OBE. Based on direct correlations of the criterion parameters with damage data, ground motions which cause damage to buildings of good design and construction (which in general are not as seismically strong as nuclear facilities) are a factor of at least 1.5 larger than the recommended criterion threshold values. This ensures adequate conservatism in the criterion. Issues related to OBE exceedance, including the history of the OBE, regulatory and operational issues, plant operation concerns, current industry activities related to OBE exceedance and recent earthquake experience are discussed in the report.

Reed, J.W.; Anderson, N.; Chokshi, N.C.; Kennedy, R.P.; Metevia, W.J.; Ostrom, D.K.; Stevenson, J.D.

1988-07-01T23:59:59.000Z

431

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Establishing the Technical Basis for Disposal of Heat-generating 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 safety case is strong and has been made by the German repository program, RD&D programs continue in order to help reduce uncertainty, to improve understanding of certain complex processes, to demonstrate operational concepts, to confirm performance expectations, and to improve modeling capabilities utilizing the latest software platforms.

432

Implementing Safeguards-by-Design  

Science Conference Proceedings (OSTI)

Executive Summary Excerpt Safeguards-by-Design (SBD) is an approach to the design and construction of nuclear facilities whereby safeguards are designed-in from the very beginning. It is a systematic and structured approach for fully integrating international and national safeguards (MC&A), physical security, and other proliferation barriers into the design and construction process for nuclear facilities. SBD is primarily a project management or project coordination challenge, and this report focuses on that aspect of SBD. The present report continues the work begun in 2008 and focuses specifically on the design process, or project management and coordination - the planning, definition, organization, coordination, scheduling and interaction of activities of the safeguards experts and stakeholders as they participate in the design and construction of a nuclear facility. It delineates the steps in a nuclear facility design and construction project, in order to provide the project context within which the safeguards design activities take place, describes the involvement of safeguards experts in the design process, the nature of their analyses, interactions and decisions, as well as describing the documents created and how they are used. Designing and constructing a nuclear facility is an extremely complex undertaking. The stakeholders in an actual project are many owner, operator, State regulators, nuclear facility primary contractor, subcontractors (e.g. instrument suppliers), architect engineers, project management team, safeguards, safety and security experts, in addition to the IAEA and its team. The purpose of the present report is to provide a common basis for discussions amongst stakeholders to collaboratively develop a SBD approach that will be both practically useful and mutually beneficial. The principal conclusions from the present study are: In the short term, the successful implementation of SBD is principally a project management problem. Life-cycle cost analysis can be a useful tool in safeguards design. An important obstacle to straight forward application of life-cycle cost analysis is that there is no single organization responsible for the entire life-cycle cost of the facility. The Safeguards Effectiveness Report (SGER) is proposed as a focus for the safeguards design activities, and is intended to be a living document that contains increasing safeguards relevant scope and content as the facility design emerges. Further work is required in a number of areas. The authors note that other studies supported by NGSI are addressing the development of requirements and performance criteria, as well as contributing to the design toolkit through the development of technology, methodology, and safeguards guidelines for designers. With respect to further development of the SBD design process, the authors recommend: In the short term, conduct a workshop with interested industry representatives, to ensure that their perspectives and needs are factored into further development. In the short term, provide NGSI SBD project documents to IAEA, and support them in the conduct of an SBD Workshop II. In the medium term, continue to support the SBD demonstration work started with the Next Generation Nuclear Plant project. In the longer term, conduct further studies to examine the integration of SBD into projects with concurrent consideration of physical security and safety.

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

2010-02-01T23:59:59.000Z

433

Guideline for the Treatment of Uncertainty in Risk-Informed Applications: Technical Basis Document  

Science Conference Proceedings (OSTI)

This report provides the technical basis for a process to characterize the uncertainty distribution for risk metrics derived from probabilistic risk assessments (PRAs).

2004-12-21T23:59:59.000Z

434

The Molecular Basis for Metabolic and Energetic Diversity  

DOE Green Energy (OSTI)

We have used experimental and computational analysis of R. sphaeroides photosynthesis and other gene expression networks (Kaplan, Gomelsky, Donohue) (3-9, 12, 13, 15-18, 20). We have identified many new candidate photosynthesis genes with expression patterns that varied as a function of light intensity. Results from these experiments suggest there are many more light-regulated aspects of the photosynthetic lifestyle of this bacterium than previously appreciated. Ongoing genetic analysis confirms that mutations in some of these newly-identified photosynthesis block the ability of cells to use solar energy in the laboratory. We also carried out transcriptome and computational analysis of individual R. sphaeroides regulons. This identified additional genes that are directly regulated by individual transcription factors and refined the consensus sequence for master regulators of photosystem development. We also showed that PpsR indirectly regulates genes that do not contain the PpsR-binding sites, e.g. puf and puhA operons. This suggests that PpsR plays a more global role as a regulator of photosystem development than what was assumed before. A similar computational and microarray analysis of PrrA target genes has identified many new candidate promoters that are controlled by this master regulator of photosynthesis. We have begun bioinformatic, genetic and biochemical experiments aimed at elucidating the interactions of transcriptional pathways controlling photosystem development (PrrBA and AppA-PpsR). We carried out computational analysis designed to cluster oxygen-dependent genes in R. sphaeroides based on the transcriptome data for cells grown between 30% and 0% oxygen. As a result, new statistical tools for clustering expression profiles from DNA microarrays have been developed. We have analyzed the assembly, bioenergetic role and regulatory functions of the aerobic respiratory chain (Donohue, Edwards, Hosler, Kaplan)(10, 11, 14)(Hiser, 2000-4612). We have used computational, genetic and biochemical approaches to map the flow of electrons through the major bioenergetic pathways of this bacterium. From this, we have formulated and tested predictions for the major and minor routes of electron transport to the 5 predicted terminal oxidases; these are now being tested by genetic and physiological experiments. We have demonstrated a direct role for the R. sphaeroides cyt cbb{sub 3} terminal oxidase of the aerobic respiratory chain in controlling the activity of a master energy homeostasis pathway, PrrBA. This presents an opportunity for analyzing the ability of a cytochrome oxidase to act as a direct modulator of a second bioenergetic machine like the photosynthetic apparatus. Given the important bioenergetic and regulatory role of the aerobic respiratory chain, we have analyzed assembly of this machine. One of these proteins, Cox11p is a copper protein that plays a critical, yet poorly-understood, role cytochrome oxidase assembly in many bacteria and organelles. We have (for the first time) succeeded in expressing the soluble domain of Cox11p as a fusion protein with thioredoxin in E. coli and shown that the protein binds copper. This and a series of mutant Cox11p proteins are being used to analyze the role of copper in this protein and determine the role of Cox11p homologs in assembly of Cu-dependent bioenergetic machines. In collaboration with GTL researchers at Pacific Northwest National Laboratory, we analyzed and localized the R. sphaeroides proteome (Kaplan, Donohue, Smith)(1, 2, 19). We have determined the entire proteome of cells grown under different energy states and localizes what fraction of the proteome is contained in the major subcellular fractions of the cell, including the photosynthetic apparatus. This has identified many new and unknown proteins within this specialized solar energy harvesting machine that we would like to analyze with future DOE support.

Timothy Donohue, PI

2007-03-19T23:59:59.000Z

435

Signal conditioning circuitry design for instrumentation systems.  

SciTech Connect

This report details the current progress in the design, implementation, and validation of the signal conditioning circuitry used in a measurement instrumentation system. The purpose of this text is to document the current progress of a particular design in signal conditioning circuitry in an instrumentation system. The input of the signal conditioning circuitry comes from a piezoresistive transducer and the output will be fed to a 250 ksps, 12-bit analog-to-digital converter (ADC) with an input range of 0-5 V. It is assumed that the maximum differential voltage amplitude input from the sensor is 20 mV with an unknown, but presumably high, sensor bandwidth. This text focuses on a specific design; however, the theory is presented in such a way that this text can be used as a basis for future designs.

Larsen, Cory A.

2012-01-01T23:59:59.000Z

436

5 MW pulsed spallation neutron source, Preconceptual design study  

Science Conference Proceedings (OSTI)

This report describes a self-consistent base line design for a 5 MW Pulsed Spallation Neutron Source (PSNS). It is intended to establish feasibility of design and as a basis for further expanded and detailed studies. It may also serve as a basis for establishing project cost (30% accuracy) in order to intercompare competing designs for a PSNS not only on the basis of technical feasibility and technical merit but also on the basis of projected total cost. The accelerator design considered here is based on the objective of a pulsed neutron source obtained by means of a pulsed proton beam with average beam power of 5 MW, in {approx} 1 {mu}sec pulses, operating at a repetition rate of 60 Hz. Two target stations are incorporated in the basic facility: one for operation at 10 Hz for long-wavelength instruments, and one operating at 50 Hz for instruments utilizing thermal neutrons. The design approach for the proton accelerator is to use a low energy linear accelerator (at 0.6 GeV), operating at 60 Hz, in tandem with two fast cycling booster synchrotrons (at 3.6 GeV), operating at 30 Hz. It is assumed here that considerations of cost and overall system reliability may favor the present design approach over the alternative approach pursued elsewhere, whereby use is made of a high energy linear accelerator in conjunction with a dc accumulation ring. With the knowledge that this alternative design is under active development, it was deliberately decided to favor here the low energy linac-fast cycling booster approach. Clearly, the present design, as developed here, must be carried to the full conceptual design stage in order to facilitate a meaningful technology and cost comparison with alternative designs.

Not Available

1994-06-01T23:59:59.000Z

437

Slide 1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

/ Jeff Dagle / Jeff Dagle Pacific Northwest National Laboratory "Implications of Design Basis Threat on Critical Infrastructure and Homeland Security" Note! * The context of this presentation doe not represent any findings that are classified or non-classified * The notion or discussion of a critical infrastructure DBT is not itself sensitive and no details that would present such sensitivities are represented in any way in this presentation Summary Slide: Design Basis Threat Implications  Outcomes: Implications of Design Basis Threat concepts relevant to energy sector critical assets and threat  Roadmap Challenge: Vendors do not have specific requirements or standards to build to: threats are hard to demonstrate and quantify  Major Successes: Major projects in

438

Study on Aerodynamic Design of Horizontal Axis Wind Turbine Generator System  

Science Conference Proceedings (OSTI)

In this paper the choosing principles of design parameters and multi-airfoils in horizontal axis wind turbine (HAWT) generator system aerodynamic design are introduced. On the basis of the comparison analysis of wind turbine aerodynamic design method ... Keywords: Schmitz, airfoil, partial load, horizontal axis wind turbine (HAWT), blade tip speed ratio (BTSR)

Li Dong; Mingfu Liao; Yingfeng Li; Xiaoping Song; Ke Xu

2009-10-01T23:59:59.000Z

439

Holistic ship design optimization  

Science Conference Proceedings (OSTI)

Ship design is a complex endeavor requiring the successful coordination of many disciplines, of both technical and non-technical nature, and of individual experts to arrive at valuable design solutions. Inherently coupled with the design process is design ... Keywords: Enhanced survivability, Genetic algorithms, Holistic ship design, Minimization of resistance and wash, Multi-objective optimization

Apostolos Papanikolaou

2010-11-01T23:59:59.000Z

440

Whither design space?  

Science Conference Proceedings (OSTI)

Design space exploration is a long-standing focus in computational design research. Its three main threads are accounts of designer action, development of strategies for amplification of designer action in exploration, and discovery of computational ... Keywords: Design Space Exploration, Knowledge Representation, Search, State Space, Typed Feature Structures

Robert F. Woodbury; Andrew L. Burrow

2006-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "design basis threat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Independent Oversight Review of the Idaho National Laboratory Fuel Conditioning Facility Safety Basis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

INDEPENDENT OVERSIGHT INDEPENDENT OVERSIGHT REVIEW OF THE IDAHO NATIONAL LABORATORY FUEL CONDITIONING FACILITY SAFETY BASIS April 2010 U.S. Department of Energy Office of Health, Safety and Security Office of Independent Oversight i INDEPENDENT OVERSIGHT REVIEW OF THE IDAHO NATIONAL LABORATORY FUEL CONDITIONING FACILITY SAFETY BASIS Table of Contents Acronyms ............................................................................................................................ ii Executive Summary ........................................................................................................... iii 1.0 Introduction ..................................................................................................................1

442

A generalization of the Wiener rational basis functions on infinite intervals, Part II - Numerical investigation  

Science Conference Proceedings (OSTI)

In Part I we introduced the generalized Wiener rational basis functions, and here in Part II we continue our investigation with numerical experiments. Wiener's generalized basis can utilize the fast Fourier transform for integer values of the decay parameter ... Keywords: Fast Fourier transform, Infinite intervals, Spectral methods

Akil C. Narayan; Jan S. Hesthaven

2013-01-01T23:59:59.000Z

443

A forecasting system for car fuel consumption using a radial basis function neural network  

Science Conference Proceedings (OSTI)

A predictive system for car fuel consumption using a radial basis function (RBF) neural network is proposed in this paper. The proposed work consists of three parts: information acquisition, fuel consumption forecasting algorithm and performance evaluation. ... Keywords: Artificial neural network, Car fuel consumption, Radial basis function algorithm

Jian-Da Wu; Jun-Ching Liu

2012-02-01T23:59:59.000Z

444

To see the property of , we take a basis set of energy eigenstates  

E-Print Network (OSTI)

MECHANISM To see the property of , we take a basis set of energy eigenstates (although we never employ such a basis in practical calculations) #12;Energy per site u Increases exponentially density of states MECHANISM Energy distribution of Energy distribution of becomes #12;Energy per site u ( ) #12

Shimizu, Akira

445

Microsoft Word - A06AL001_Buff_Cover .doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Follow-Up Audit of the National Nuclear Security Administration's Implementation of the 2003 Design Basis Threat Policy OAS-M-07-04 June 2007 Department of Energy Washington, DC 2...

446

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

SciTech Connect

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.

Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip; Marincel, Michelle K.

2008-03-01T23:59:59.000Z

447

Basis for Section 3116 Determination for the Idaho Nuclear Technology and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Basis for Section 3116 Determination for the Idaho Nuclear Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory This 3116 Basis Document addresses the disposal of stabilized residuals in the TFF, and the TFF tank system, and disposal of the tanks, vaults, and associated piping and ancillary equipment at INTEC. The TFF tank system comprises the eleven 300,000-gal tanks, four 30,000-gal tanks, and the vaults, piping, structures, and ancillary equipment associated with these tanks. Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory

448

An 'optimal' spawning algorithm for adaptive basis set expansion in nonadiabatic dynamics  

Science Conference Proceedings (OSTI)

The full multiple spawning (FMS) method has been developed to simulate quantum dynamics in the multistate electronic problem. In FMS, the nuclear wave function is represented in a basis of coupled, frozen Gaussians, and a 'spawning' procedure prescribes a means of adaptively increasing the size of this basis in order to capture population transfer between electronic states. Herein we detail a new algorithm for specifying the initial conditions of newly spawned basis functions that minimizes the number of spawned basis functions needed for convergence. 'Optimally' spawned basis functions are placed to maximize the coupling between parent and child trajectories at the point of spawning. The method is tested with a two-state, one-mode avoided crossing model and a two-state, two-mode conical intersection model.

Yang, Sandy; Coe, Joshua D.; Kaduk, Benjamin; Martinez, Todd J. [Department of Chemistry and Beckman Institute, University of Illinois at Urbana-Champaign, 600 S. Mathews Ave., Urbana, Illinois 61801 (United States)

2009-04-07T23:59:59.000Z

449

Next Generation CANDU Technology: Competitive Design for the Nuclear Renaissance  

SciTech Connect

AECL has developed the design for a next generation of CANDU{sup R} plants by marrying a set of enabling technologies to well-established successful CANDU features. The basis for the design is to replicate or adapt existing CANDU components for a new core design. By adopting slightly enriched uranium fuel, a core design with light water coolant, heavy water moderator and reflector has been defined, based on the existing CANDU fuel channel module. This paper summarizes the main features and characteristics of the reference next-generation CANDU design. The progress of the next generation of CANDU design program in meeting challenging cost, schedule and performance targets is described. AECL's cost reduction methodology is summarized as an integral part of the design optimization process. Examples are given of cost reduction features together with enhancement of design margins. (authors)

Hopwood, J.M.; Hedges, K.R.; Pakan, M. [Atomic Energy of Canada Ltd., Ontario (Canada)

2002-07-01T23:59:59.000Z

450

Solar control design package  

DOE Green Energy (OSTI)

Information used in the evaluation of design of Solar Control's solar heating and cooling system controller and the Solarstat is presented. System performance specifications, design data brochures, and detailed design drawings are presented.

Not Available

1978-08-01T23:59:59.000Z

451

Computation & design for nanophotonics  

E-Print Network (OSTI)

The versatility of computational design as an alternative to design by nanofabrication has made computers a reliable design tool in nanophotonics. Given that almost any 2d pattern can be fabricated at infrared length scales, ...

Oskooi, Ardavan F

2010-01-01T23:59:59.000Z

452

Towards MultipliCity : Burlington, Vermont - a strategy of design advocacy  

E-Print Network (OSTI)

The thesis has been an exploration within an attitude towards urban design. This attitude is structured on a belief, in the necessity for inclusive thinking and appreciation of the multiple phenomena of life, as the basis ...

Edgcomb, James Loring

1984-01-01T23:59:59.000Z

453

Children learning science through engineering: an investigation of four engineering-design-based curriculum modules  

Science Conference Proceedings (OSTI)

This research investigates the use of engineering design challenges as the basis for primary school science learning environments. We used pre-post tests to compare engineering-based students' science content gains to those of students using their district's ...

Kristen B. Wendell; Kathleen G. Connolly; Christopher G. Wright; Linda Jarvin; Chris Rogers

2010-06-01T23:59:59.000Z

454

Analysis of waste treatment requirements for DOE mixed wastes: Technical basis  

SciTech Connect

The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation`s allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered.

1995-02-01T23:59:59.000Z

455

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

SciTech Connect

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.

Nikkel, D J

2009-07-21T23:59:59.000Z

456

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

SciTech Connect

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.

Nikkel, D J

2009-07-21T23:59:59.000Z

457

Passive Solar Design  

Energy.gov (U.S. Department of Energy (DOE))

The difference between a passive solar home and a conventional home is design. Passive solar homes and other buildings are designed to take advantage of the local climate.

458

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

SciTech Connect

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 operators 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.

David I Gertman; David J Bruemmer

2008-12-01T23:59:59.000Z

459

AHTR Mechanical, Structural, And Neutronic Preconceptual Design  

SciTech Connect

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

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

2012-10-01T23:59:59.000Z

460

AHTR Mechanical, Structural, and Neutronic Preconceptual Design  

SciTech Connect

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.

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

2012-09-15T23:59:59.000Z