National Library of Energy BETA

Sample records for nuclear facility portion

  1. Nuclear Facilities

    Broader source: Energy.gov [DOE]

    The nuclear sites list and map shows how DOE nuclear operations are mostly divided between nuclear weapons stockpile maintenance, research and environmental cleanup. The operations are performed within several different facilities supporting nuclear reactor operations, nuclear research, weapons disassembly, maintenance and testing, hot cell operations, nuclear material storage and processing and waste disposal.

  2. EIS-0350-S1: Supplemental Environmental Impact Statement for the Nuclear Facility Portion of the Chemistry and Metallurgy Research Building Replacement Project at Los Alamos National Laboratory, New Mexico

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Supplemental EIS evaluates the completion of the Chemistry and Metallurgy Research Building Replacement (CMRR) Project, which consists of constructing the nuclear facility portion (CMRR-NF) at Los Alamos National Laboratory (LANL). The CMRR Project provides the analytical chemistry and materials characterization capabilities currently or previously performed in the existing Chemistry and Metallurgy Research (CMR) Building. Because of recent detailed site geotechnical investigations, certain aspects of the CMRR-NR project have changed resulting in change to the environmental impacts.

  3. Nuclear Facilities Production Facilities

    National Nuclear Security Administration (NNSA)

    Facilities Production Facilities Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. Sand 2011-4582P. ENERGY U.S. DEPARTMENT OF Gamma Irradiation Facility (GIF) The GIF provides test cells for the irradiation of experiments with high-intensity gamma ray sources. The main features

  4. Hanford facility dangerous waste permit application, general information portion

    SciTech Connect (OSTI)

    Hays, C.B.

    1998-05-19

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in this report).

  5. Defense Nuclear Facility Safety Board

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

    8, 2014 Defense Nuclear Facility Safety Board Defense Nuclear Facility Safety Board (DNSFB) Vice Chairwoman Jesse Roberson visited and toured the WIPP site this week. While...

  6. Defense Nuclear Facility | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Defense Nuclear Facility NNSA's safety office accredited and recognized for leadership in safe operation of defense nuclear facilities Part of NNSA's commitment to maintaining the nation's safe, secure, and effective nuclear deterrent are relentlessly high standards for technically capable nuclear enterprise personnel qualifications for all aspects of Defense Nuclear Facility operations. In December 2015, the Department of Energy

  7. Hanford facility dangerous waste permit application, general information portion. Revision 3

    SciTech Connect (OSTI)

    Sonnichsen, J.C.

    1997-08-21

    For purposes of the Hanford facility dangerous waste permit application, the US Department of Energy`s contractors are identified as ``co-operators`` and sign in that capacity (refer to Condition I.A.2. of the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit). Any identification of these contractors as an ``operator`` elsewhere in the application is not meant to conflict with the contractors` designation as co-operators but rather is based on the contractors` contractual status with the U.S. Department of Energy, Richland Operations Office. The Dangerous Waste Portion of the initial Hanford Facility Resource Conservation and Recovery Act Permit, which incorporated five treatment, storage, and/or disposal units, was based on information submitted in the Hanford Facility Dangerous Waste Permit Application and in closure plan and closure/postclosure plan documentation. During 1995, the Dangerous Waste Portion was modified twice to incorporate another eight treatment, storage, and/or disposal units; during 1996, the Dangerous Waste Portion was modified once to incorporate another five treatment, storage, and/or disposal units. The permit modification process will be used at least annually to incorporate additional treatment, storage, and/or disposal units as permitting documentation for these units is finalized. The units to be included in annual modifications are specified in a schedule contained in the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit. Treatment, storage, and/or disposal units will remain in interim status until incorporated into the Permit. The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to individual operating treatment, storage, and/or disposal units for which

  8. CRAD, Facility Safety- Nuclear Facility Safety Basis

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  9. CRAD, Facility Safety- Nuclear Facility Design

    Broader source: Energy.gov [DOE]

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

  10. Listing of Defense Nuclear Facilities

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

    Listing of Defense Nuclear Facilities The facilities listed below are considered DOE defense nuclear facilities for purposes of Section 3161. Kansas City Plant Pinellas Plant Mound Facility Fernald Environmental Management Project Site Pantex Plant Rocky Flats Environmental Technology Site, including the Oxnard Facility Savannah River Site Los Alamos National Laboratory Sandia National Laboratory Lawrence Livermore National Laboratory Oak Ridge National Laboratory Nevada Test Site 1 Y-12 Plant

  11. US nuclear warhead facility profiles

    SciTech Connect (OSTI)

    Cochran, T.B.; Arkin, W.A.; Norris, R.S.; Hoenig, M.M.

    1987-01-01

    US Nuclear Warhead Facility Profiles is the third volume of the Nuclear Weapons Databook, a series published by the Natural Resources Defense Council. This volume reviews the different facilities in the US nuclear warhead complex. Because of the linkage between nuclear energy and nuclear weapons, the authors cover not only those facilities associated mainly with nuclear power research, but also those well known for weapons development. They are: the Argonne National Laboratory; the Hanford Reservation; the Oak Ridge National Laboratory; the Pantex plant; the Los Alamos Test Site; the Rocky Flats plant; the Sandia National Laboratories; and a host of others. Information on each facility is organized into a standard format that makes the book easy to use. The reader will find precise information ranging from a facility's address to its mission, management, establishment, budget, and staff. An additional, more in-depth presentation covers the activities and technical process of each facility. Maps, pictures, and figures complement the text.

  12. Nuclear Science Research facility at LANSCE

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

    Neutron and Nuclear Science (WNR) Facility at LANSCE lansce facility at LANL Introduction ... Neutron Scattering Center (Target-1) and the Neutron and Nuclear Science Research facility ...

  13. Preservation and Dissemination of the Hardcopy Documentation Portion of the NCSP Nuclear Criticality Bibliographic Database

    SciTech Connect (OSTI)

    Koponen, B L; Heinrichs, D

    2009-05-18

    The U.S. Department of Energy supports a nuclear criticality safety bibliographic internet database that contains approximately 15,000 records. We are working to ensure that a substantial portion of the corresponding hardcopy documents are preserved, digitized, and made available to criticality safety practitioners via the Nuclear Criticality Safety Program web site.

  14. NNSA and Defense Nuclear Facilities

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

    and Defense Nuclear Facilities Safety Board certifications free up 47 million in previously allocated funding October 2, 2009 Los Alamos, New Mexico, Oct. 2, 2009 - The Chemistry...

  15. Office of Nuclear Facility Safety Programs

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Office of Nuclear Facility Safety Programs establishes nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities.

  16. Independent Activity Report, Defense Nuclear Facilities Safety...

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

    Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October...

  17. WIPP Nuclear Facilities Transparency

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

    the safety, security, and legitimate management of nuclear materials." Other Links Yucca Mountain Test Data Carlsbad Environmental Monitoring and Research Center Dimitrovograd Site ...

  18. Nuclear Power Facilities (2008) | Department of Energy

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

    Nuclear Power Facilities (2008) Nuclear Power Facilities (2008) Nuclear Power Facilities (2008) (408.42 KB) More Documents & Publications Front-end Nuclear Facilities (2008) Financial Institution Partnership Program - Commercial Technology Renewable Energy Generation Projects Issued: October 7, 2009 Transmission Infrastructure Investment Projects (2009)

  19. Establishing nuclear facility drill programs

    SciTech Connect (OSTI)

    1996-03-01

    The purpose of DOE Handbook, Establishing Nuclear Facility Drill Programs, is to provide DOE contractor organizations with guidance for development or modification of drill programs that both train on and evaluate facility training and procedures dealing with a variety of abnormal and emergency operating situations likely to occur at a facility. The handbook focuses on conducting drills as part of a training and qualification program (typically within a single facility), and is not intended to included responses of personnel beyond the site boundary, e.g. Local or State Emergency Management, Law Enforcement, etc. Each facility is expected to develop its own facility specific scenarios, and should not limit them to equipment failures but should include personnel injuries and other likely events. A well-developed and consistently administered drill program can effectively provide training and evaluation of facility operating personnel in controlling abnormal and emergency operating situations. To ensure the drills are meeting their intended purpose they should have evaluation criteria for evaluating the knowledge and skills of the facility operating personnel. Training and evaluation of staff skills and knowledge such as component and system interrelationship, reasoning and judgment, team interactions, and communications can be accomplished with drills. The appendices to this Handbook contain both models and additional guidance for establishing drill programs at the Department`s nuclear facilities.

  20. Nuclear Facility Risk Ranking | Department of Energy

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

    Facility Risk Ranking Nuclear Facility Risk Ranking Nuclear Facility Risk Ranking The CNS has purview of over ninety EM nuclear facilities across the DOE complex. To ensure that limited resources are applied in a risk-informed and balanced approach, the CNS performed a methodical assessment of the EM nuclear facilities. This risk-informed approach provides a data-driven foundation on which to construct a balanced set of operating plans and staff assignments. 2015 Risk Analysis Methodology.jpg

  1. Nuclear Energy Advisory Committee, Facility Subcommittee visit...

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

    Facility Subcommittee visit to Idaho National Laboratory May 19-20, 2010 The Nuclear Energy Advisory Committee, Facility Subcommittee visited the Idaho National...

  2. Startup and Restart of Nuclear Facilities

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

    1995-09-29

    The order establishes the requirements for startup of new nuclear facilities and for the restart of existing nuclear facilities that have been shutdown. Cancels DOE 5480.31. Canceled by DOE O 425.1A.

  3. Startup and Restart of Nuclear Facilities

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

    1998-12-28

    To establish the requirements for startup of new nuclear facilities and for the restart of existing nuclear facilities that have been shut down. Cancels DOE O 425.1. Canceled by DOE O 425.1B.

  4. Defense Nuclear Facilities Safety Board (DNFSB) Letters and Recommenda...

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

    Defense Nuclear Facilities Safety Board (DNFSB) Letters and Recommendations Defense Nuclear Facilities Safety Board (DNFSB) Letters and Recommendations Defense Nuclear Facilities ...

  5. RADIATION FACILITY FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Currier, E.L. Jr.; Nicklas, J.H.

    1961-12-12

    A radiation facility is designed for irradiating samples in close proximity to the core of a nuclear reactor. The facility comprises essentially a tubular member extending through the biological shield of the reactor and containing a manipulatable rod having the sample carrier at its inner end, the carrier being longitudinally movable from a position in close proximity to the reactor core to a position between the inner and outer faces of the shield. Shield plugs are provided within the tubular member to prevent direct radiation from the core emanating therethrough. In this device, samples may be inserted or removed during normal operation of the reactor without exposing personnel to direct radiation from the reactor core. A storage chamber is also provided within the radiation facility to contain an irradiated sample during the period of time required to reduce the radioactivity enough to permit removal of the sample for external handling. (AEC)

  6. WIRELESS FOR A NUCLEAR FACILITY

    SciTech Connect (OSTI)

    Shull, D; Joe Cordaro, J

    2007-03-28

    The introduction of wireless technology into a government site where nuclear material is processed and stored brings new meaning to the term ''harsh environment''. At SRNL, we are attempting to address not only the harsh RF and harsh physical environment common to industrial facilities, but also the ''harsh'' regulatory environment necessitated by the nature of the business at our site. We will discuss our concepts, processes, and expected outcomes in our attempts to surmount the roadblocks and reap the benefits of wireless in our ''factory''.

  7. Startup and Restart of Nuclear Facilities

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

    2000-12-21

    To establish the requirements for the Department of Energy, including the National Nuclear Security Administration (NNSA), for start up of new nuclear facilities and for the restart of existing nuclear facilities that have been shut down. Cancels DOE O 425.1A. Canceled by DOE O 425.1C.

  8. Startup and Restart of Nuclear Facilities

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

    1995-10-26

    To establish the requirements for the Department of Energy, including the National Nuclear Security Administration (NNSA), for start up of new nuclear facilities and for the restart of existing nuclear facilities that have been shut down. Cancels DOE 5480.31. Canceled by DOE O 425.1A.

  9. Startup and Restart of Nuclear Facilities

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

    2003-03-13

    To establish the requirements for the Department of Energy, including the National Nuclear Security Administration (NNSA), for start up of new nuclear facilities and for the restart of existing nuclear facilities that have been shut down. Cancels DOE O 425.1B. Canceled by DOE O 425.1D

  10. Nuclear Facilities and Applied Technologies at Sandia

    SciTech Connect (OSTI)

    Wheeler, Dave; Kaiser, Krista; Martin, Lonnie; Hanson, Don; Harms, Gary; Quirk, Tom

    2014-11-28

    The Nuclear Facilities and Applied Technologies organization at Sandia National Laboratoriesí Technical Area Five (TA-V) is the leader in advancing nuclear technologies through applied radiation science and unique nuclear environments. This video describes the organizationís capabilities, facilities, and culture.

  11. CRAD, Nuclear Facility Construction - Mechanical Equipment -...

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

    Nuclear Facility Construction - Mechanical Equipment Installation, (HSS CRAD 45-53, Rev. 0) This Criteria Review and Approach Document (HSS CRAD 45-53) establishes review criteria...

  12. Preparation Of Nonreactor Nuclear Facility Documented Safety...

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

    9-2014, Preparation Of Nonreactor Nuclear Facility Documented Safety Analysis by Website Administrator This Department of Energy (DOE) Standard (STD), DOE-STD-3009-2014, describes...

  13. Nuclear Facilities Fire Accident Model

    Energy Science and Technology Software Center (OSTI)

    1999-09-01

    4. NATURE OF PROBLEM SOLVED FIRAC predicts fire-induced flows, thermal and material transport, and radioactive and nonradioactive source terms in a ventilation system. It is designed to predict the radioactive and nonradioactive source terms that lead to gas dynamic, material transport, and heat transfer transients. FIRAC's capabilities are directed toward nuclear fuel cycle facilities and the primary release pathway, the ventilation system. However, it is applicable to other facilities and can be used to modelmore¬†¬Ľ other airflow pathways within a structure. The basic material transport capability of FIRAC includes estimates of entrainment, convection, deposition, and filtration of material. The interrelated effects of filter plugging, heat transfer, and gas dynamics are also simulated. A ventilation system model includes elements such as filters, dampers, ducts, and blowers connected at nodal points to form networks. A zone-type compartment fire model is incorporated to simulate fire-induced transients within a facility. 5. METHOD OF SOLUTION FIRAC solves one-dimensional, lumped-parameter, compressible flow equations by an implicit numerical scheme. The lumped-parameter method is the basic formulation that describes the gas dynamics system. No spatial distribution of parameters is considered in this approach, but an effect of spatial distribution can be approximated by noding. Network theory, using the lumped parameter method, includes a number of system elements, called branches, joined at certain points, called nodes. Ventilation system components that exhibit flow resistance and inertia, such as dampers, ducts, valves, and filters, and those that exhibit flow potential, such as blowers, are located within the branches of the system. The connection points of branches are nodes for components that have finite volumes, such as rooms, gloveboxes, and plenums, and for boundaries where the volume is practically infinite. All internal nodes, therefore, possess some

  14. Facility Clearance Program | National Nuclear Security Administration |

    National Nuclear Security Administration (NNSA)

    (NNSA) Facility Clearance Program The Facility Clearance (FCL) Program regulates DOE approval of a Federal or contractor facility's eligibility to access, receive, generate, reproduce, store, transmit, or destroy classified information or matter, special nuclear material (SNM), other hazardous material presenting a potential radiological, chemical, or biological sabotage threat, and/or DOE property of significant monetary value, exclusive of facilities and land values (hereinafter referred

  15. Office of Nuclear Safety Basis and Facility Design

    Broader source: Energy.gov [DOE]

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

  16. Nuclear Facility Risk Ranking | Department of Energy

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

    risk-informed and balanced approach, the CNS performed a methodical assessment of the EM nuclear facilities. This risk-informed approach provides a data-driven foundation on which...

  17. Nuclear Facility Operations | Department of Energy

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

    Operations Nuclear Facility Operations INL is a science-based, applied engineering national laboratory dedicated to meeting the nation's environmental, energy, nuclear technology, and national security needs. INL is a science-based, applied engineering national laboratory dedicated to meeting the nation's environmental, energy, nuclear technology, and national security needs. The Idaho Operations Office oversees these contract activities in accordance with DOE directives. INL is a multi-program

  18. Front-end Nuclear Facilities (2008) | Department of Energy

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

    Front-end Nuclear Facilities (2008) Front-end Nuclear Facilities (2008) Front-end Nuclear Facilities (2008) (399.4 KB) More Documents & Publications Nuclear Power Facilities (2008) Financial Institution Partnership Program - Commercial Technology Renewable Energy Generation Projects Issued: October 7, 2009 Transmission Infrastructure Investment Projects (2009)

  19. Independent Oversight Review, DOE Nuclear Facilities- May 2013

    Broader source: Energy.gov [DOE]

    Lessons Learned from Targeted Reviews of Implementation Verification Review Processes at Department of Energy Nuclear Facilities

  20. Maintenance Management Program for DOE Nuclear Facilities

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

    2001-06-01

    To define the program for the management of cost-effective maintenance of Department of Energy (DOE) nuclear facilities. Guidance for compliance with this Order is contained in DOE G 433.1-1, Nuclear Facility Maintenance Management Program Guide for use with DOE O 433.1, which references Federal regulations, DOE directives, and industry best practices using a graded approach to clarify requirements and guidance for maintaining DOE-owned Government property. (Cancels DOE 4330.4B, Chapter II, Maintenance Management Program, dated 2-10-94.) Cancels DOE 4330.4B (in part). Canceled by DOE O 433.1A.

  1. Uranium Processing Facility | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Uranium Processing Facility

  2. 2016 Nuclear and Facility Safety Program Workshop | Department of Energy

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

    Nuclear and Facility Safety Program Workshop 2016 Nuclear and Facility Safety Program Workshop March 22, 2016 - 3:48pm Addthis 2016 Nuclear and Facility Safety Program Workshop The Office of Environmental Health, Safety, and Security will sponsor the 2016 Nuclear and Facility Safety Program Workshop which will be held May 2-6, 2016 at the Alexis Park in Las Vegas, Nevada. The Workshop will include meetings for the DOE Safety Culture Improvement Panel, Federal Technical Capability Panel, Facility

  3. Guidelines for Evaluation of Nuclear Facility Training Programs

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

    1995-11-22

    The Guidelines for Evaluation of Nuclear Facility Training Programs establish objectives and criteria for evaluating nuclear facility training programs. The guidance in this standard provides a framework for the systematic evaluation of training programs at nuclear facilities and is based, in part, on established criteria for Technical Safety Appraisals, Tiger Team Assessments, commercial nuclear industry evaluations, and the DOE Training Accreditation Program.

  4. 2015 Nuclear & Facility Safety Programs Workshop Agenda | Department...

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

    2015 Nuclear and Facility Safety Programs Workshop agenda outlining following: Training Plenary Session Award Presentations Guest speakers Fire Safety Workshop Facility...

  5. Improving the Safeguardability of Nuclear Facilities

    SciTech Connect (OSTI)

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

    2009-07-01

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

  6. Security Upgrades Completed at Three Russian Nuclear Facilities | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration | (NNSA) Security Upgrades Completed at Three Russian Nuclear Facilities December 10, 2004 NNSA continues work to keep nuclear material out of the hands of terrorists RUSSIA -- The National Nuclear Security Administration (NNSA) commemorated ten years of work securing nuclear and radiological material in Russia and the former Soviet Union by completing security upgrades at two Russian nuclear facilities this week. Upgrades at a third facility were completed in

  7. CRAD, New Nuclear Facility Documented Safety Analysis and Technical...

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

    December 2, 2014 New Nuclear Facility Documented Safety Analysis and Technical Safety Requirements Criteria Review and Approach Document (EA CRAD 31-07, Rev. 0) CRAD, New Nuclear...

  8. Y-12 Removes Nuclear Materials from Two Facilities to Reduce...

    National Nuclear Security Administration (NNSA)

    Blog Home Field Offices Welcome to the NNSA Production Office NPO News Releases Y-12 Removes Nuclear Materials from Two Facilities ... Y-12 Removes Nuclear Materials from...

  9. Iraq nuclear facility dismantlement and disposal project

    SciTech Connect (OSTI)

    Cochran, J.R.; Danneels, J.; Kenagy, W.D.; Phillips, C.J.; Chesser, R.K.

    2007-07-01

    The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

  10. Nuclear Energy Advisory Committee, Facility Subcommittee visit to Idaho

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

    National Laboratory | Department of Energy Advisory Committee, Facility Subcommittee visit to Idaho National Laboratory Nuclear Energy Advisory Committee, Facility Subcommittee visit to Idaho National Laboratory The Nuclear Energy Advisory Committee, Facility Subcommittee visited the Idaho National Laboratory on 19-20 May 2010 to tour the nuclear infrastructure and to discuss the INL plans for facility modernization as a dimension of the DOE Office of Nuclear Energy's (NE) mission. This was

  11. Appendix B: Rules and Directives Applicable to Nuclear Facilities Line

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

    Management Oversight | Department of Energy Appendix B: Rules and Directives Applicable to Nuclear Facilities Line Management Oversight Appendix B: Rules and Directives Applicable to Nuclear Facilities Line Management Oversight Appendix B to DOE G 226.1-2A "Federal Line Management Oversight of Department of Energy Nuclear Facilities". Consists of a list of rules and directives that are applicable to nuclear facilities line management oversight. Appendix B: Rules and Directives

  12. CRAD, Nuclear Facility Safety System- September 25, 2009

    Broader source: Energy.gov [DOE]

    Nuclear Facility Safety System Functionality Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-17, Rev 0 )

  13. Maintenance Management Program for DOE Nuclear Facilities

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

    2010-04-21

    The order defines the safety management program required by 10 CFR 830.204(b)(5) for maintenance and the reliable performance of structures, systems and components that are part of the safety basis required by 10 CFR 830.202 at hazard category 1, 2 and 3 DOE nuclear facilities. Admin Chg 1, dated 3-12-2013, supersedes DOE O 433.1B.

  14. Maintenance Management Program for DOE Nuclear Facilities

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

    2007-02-13

    The Order defines the safety management program required by 10 CFR 830.204(b)(5) for maintenance and the reliable performance of Structures, Systems and Components (SSCs) that are part of the safety basis required by 10 CFR 830.202.1 at hazard category 1, 2 and 3 Department of Energy (DOE) nuclear facilities. Cancels DOE O 433.1. Canceled by DOE O 433.1B.

  15. Maintenance Management Program for DOE Nuclear Facilities

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

    2010-04-21

    The order defines the safety management program required by 10 CFR 830.204(b)(5) for maintenance and the reliable performance of structures, systems and components that are part of the safety basis required by 10 CFR 830.202 at hazard category 1, 2 and 3 DOE nuclear facilities. Admin Chg 1, dated 3-12-2013. Cancels DOE O 433.1A.

  16. Listing of Defense Nuclear Facilities | Department of Energy

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

    Listing of Defense Nuclear Facilities Listing of Defense Nuclear Facilities Attachment 1 - Listing of Defense Nuclear Facilities (55.77 KB) More Documents & Publications Draft Policy and Planning Guidance for Community Transition Activities Workforce Restructuring Policy The First Five Years FY 2004-2008

  17. Y-12 Removes Nuclear Materials from Two Facilities to Reduce Site's Nuclear

    National Nuclear Security Administration (NNSA)

    Footprint (Alpha 5 and 9720-38 No Longer Designated as Nuclear Facilities) | National Nuclear Security Administration | (NNSA) Removes Nuclear Materials from Two Facilities to Reduce Site's Nuclear Footprint (Alpha 5 and 9720-38 No Longer Designated as Nuclear Facilities) September 03, 2010 Microsoft Office document icon R-9-2

  18. Nuclear facility decommissioning and site remedial actions

    SciTech Connect (OSTI)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  19. Nuclear facility decommissioning and site remedial actions

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  20. Financing Strategies for Nuclear Fuel Cycle Facility

    SciTech Connect (OSTI)

    David Shropshire; Sharon Chandler

    2005-12-01

    To help meet our nation’s energy needs, reprocessing of spent nuclear fuel is being considered more and more as a necessary step in a future nuclear fuel cycle, but incorporating this step into the fuel cycle will require considerable investment. This report presents an evaluation of financing scenarios for reprocessing facilities integrated into the nuclear fuel cycle. A range of options, from fully government owned to fully private owned, was evaluated using a DPL (Dynamic Programming Language) 6.0 model, which can systematically optimize outcomes based on user-defined criteria (e.g., lowest life-cycle cost, lowest unit cost). Though all business decisions follow similar logic with regard to financing, reprocessing facilities are an exception due to the range of financing options available. The evaluation concludes that lowest unit costs and lifetime costs follow a fully government-owned financing strategy, due to government forgiveness of debt as sunk costs. Other financing arrangements, however, including regulated utility ownership and a hybrid ownership scheme, led to acceptable costs, below the Nuclear Energy Agency published estimates. Overwhelmingly, uncertainty in annual capacity led to the greatest fluctuations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; the annual operating costs dominate the government case. It is concluded that to finance the construction and operation of such a facility without government ownership could be feasible with measures taken to mitigate risk, and that factors besides unit costs should be considered (e.g., legal issues, social effects, proliferation concerns) before making a decision on financing strategy.

  1. Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities

    Office of Environmental Management (EM)

    Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities Standard Review Plan Volume 4 - Nuclear Safety Basis Program Review During Facility Decommissioning and Environmental Restoration February 2015 i Standard Review Plan Volume 4 Nuclear Safety Basis Program Review during Facility Decommissioning and Environmental Restoration Facility Life Cycle Applicability CD-1 CD-2 CD-3 CD-4 Operations and Transitions Decommissioning & Environmental Restoration February

  2. Enterprise Assessments Targeted Review of Nuclear Reactor Facility

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

    Operations at Sandia National Laboratories - March 2016 | Department of Energy Nuclear Reactor Facility Operations at Sandia National Laboratories - March 2016 Enterprise Assessments Targeted Review of Nuclear Reactor Facility Operations at Sandia National Laboratories - March 2016 March 2016 Targeted Review of Nuclear Reactor Facility Operations at Sandia National Laboratories The U.S. Department of Energy independent Office of Enterprise Assessments (EA) conducted a review of nuclear

  3. Safety of Decommissioning of Nuclear Facilities

    SciTech Connect (OSTI)

    Batandjieva, B.; Warnecke, E.; Coates, R.

    2008-01-15

    Full text of publication follows: ensuring safety during all stages of facility life cycle is a widely recognised responsibility of the operators, implemented under the supervision of the regulatory body and other competent authorities. As the majority of the facilities worldwide are still in operation or shutdown, there is no substantial experience in decommissioning and evaluation of safety during decommissioning in majority of Member States. The need for cooperation and exchange of experience and good practices on ensuring and evaluating safety of decommissioning was one of the outcomes of the Berlin conference in 2002. On this basis during the last three years IAEA initiated a number of international projects that can assist countries, in particular small countries with limited resources. The main IAEA international projects addressing safety during decommissioning are: (i) DeSa Project on Evaluation and Demonstration of Safety during Decommissioning; (ii) R{sup 2}D{sup 2}P project on Research Reactors Decommissioning Demonstration Project; and (iii) Project on Evaluation and Decommissioning of Former Facilities that used Radioactive Material in Iraq. This paper focuses on the DeSa Project activities on (i) development of a harmonised methodology for safety assessment for decommissioning; (ii) development of a procedure for review of safety assessments; (iii) development of recommendations on application of the graded approach to the performance and review of safety assessments; and (iv) application of the methodology and procedure to the selected real facilities with different complexities and hazard potentials (a nuclear power plant, a research reactor and a nuclear laboratory). The paper also outlines the DeSa Project outcomes and planned follow-up activities. It also summarises the main objectives and activities of the Iraq Project and introduces the R{sup 2}D{sup 2} Project, which is a subject of a complementary paper.

  4. Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities

    Office of Environmental Management (EM)

    Volume 3 - Nuclear Safety Basis Program Review During Facility Operations and Transitions February 2015 i Standard Review Plan Volume 3 Nuclear Safety Basis Program Review during Facility Operations and Transitions Facility Life Cycle Applicability CD-1 CD-2 CD-3 CD-4 Operations and Transitions Decommissioning & Environmental Restoration February 2015 ii Table of Contents Acronyms

  5. Nuclear fuel cycle facility accident analysis handbook

    SciTech Connect (OSTI)

    1998-03-01

    The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

  6. Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities

    Office of Environmental Management (EM)

    Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities Standard Review Plan Volume 2 -- Nuclear Safety Basis Program Review During Design February 2015 i Standard Review Plan Volume 2 Nuclear Safety Basis Program Review during Design Facility Life Cycle Applicability CD-1 CD-2 CD-3 CD-4 Operations and Transitions Decommissioning & Environmental Restoration February 2015 ii Table of Contents Acronyms

  7. Seismic requirements for design of nuclear power plants and nuclear test facilities

    SciTech Connect (OSTI)

    Not Available

    1985-02-01

    This standard establishes engineering requirements for the design of nuclear power plants and nuclear test facilities to accommodate vibratory effects of earthquakes.

  8. CRAD, Nuclear Reactor Facility Operations - December 4, 2014...

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

    Reactor Facility Operations - December 4, 2014 (EA CRAD 31-08, Rev. 0) CRAD, Nuclear Reactor Facility Operations - December 4, 2014 (EA CRAD 31-08, Rev. 0) December 4, 2014 CRAD,...

  9. Facilities | National Nuclear Security Administration | (NNSA...

    National Nuclear Security Administration (NNSA)

    Dual Axis Radiographic Hydrodynamic Test (DARHT) Facility, Los Alamos National ... Dual Axis Radiographic Hydrodynamic Test Facility High Explosives Application ...

  10. Criteria for Evaluation of Nuclear Facility Training Programs

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

    Reaffirmed June 2013 DOE STANDARD CRITERIA FOR EVALUATION OF NUCLEAR FACILITY TRAINING PROGRAMS (Formerly Titled: Guidelines for Evaluation of Nuclear Facility Training Programs) U.S. Department of Energy FSC Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE HDBK-1070-94 Errata June 2013 Table of Changes Page/Section Change Cover Criteria for Evaluation of Nuclear Facility Training Programs Page ii This document is available on the

  11. Approaches used for Clearance of Lands from Nuclear Facilities among

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

    Several Countries: Evaluation for Regulatory Input | Department of Energy Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input The study entitled, "Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input," focuses on the issue of

  12. Idaho Nuclear Technology and Engineering Center Tank Farm Facility |

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

    Department of Energy Idaho Nuclear Technology and Engineering Center Tank Farm Facility Idaho Nuclear Technology and Engineering Center Tank Farm Facility The Secretary of Energy signed Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 basis of determination for the disposal of grouted residual waste in the tank systems at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF) on November 19, 2006. Section 3116 of the

  13. Cleanup of Nuclear Licensed Facility 57

    SciTech Connect (OSTI)

    Jeanjacques, Michel; Bremond, Marie Pierre; Marchand, Carole; Poyau, Cecile; Viallefont, Cecile; Gautier, Laurent; Masure, Frederic

    2008-01-15

    This summary describes the operations to clean up the equipment of the Nuclear Licensed Facility 57 (NLF 57). Due to the diversity of the research and development work carried out on the reprocessing of spent fuel in it, this installation is emblematic of many of the technical and organizational issues liable to be encountered in the final closure of nuclear facilities. The French atomic energy commission's center at Fontenay aux Roses (CEA-FAR) was created in 1946 to house pile ZOE. Laboratories for fuel cycle research were installed in existing buildings at the site. Work was later concentrated on spent fuel reprocessing, in a pilot workshop referred to as the 'Usine Pu'. In the early sixties, after the dismantling of these first generation facilities, a radiochemistry laboratory dedicated to research and development work on reprocessing was constructed, designated Building 18. During the same decade, more buildings were added: Building 54, storehouses and offices, Building 91, a hall and laboratories for chemical engineering research on natural and depleted uranium. Together, these three building constitute NLF 57. Building 18 architecture featured four similar modules. Each module had three levels: a sub-level consisting of technical galleries and rooms for the liquid effluent tanks, a ground floor and roof space in which the ventilation was installed. Offices, change rooms, four laboratories and a hall were situated on the ground floor. The shielded lines were installed in the laboratories and the halls. Construction of the building took place between 1959 and 1962, and its commissioning began in 1961. The research and development programs performed in NLF 57 related to studies of the reprocessing of spent fuel, including dry methods and the Purex process, techniques for the treatment of waste (vitrification, alpha waste decontamination, etc.) as well as studies and production of transuranic elements for industry and research. In addition to this work, the

  14. Independent Oversight Review, DOE/NNSA Nuclear Facilities- April 2013

    Broader source: Energy.gov [DOE]

    Lessons Learned from the 2012 Targeted Reviews of Emergency Preparedness for Severe Natural Phenomena Events at Select DOE/NNSA Nuclear Facilities

  15. NNSA and Defense Nuclear Facilities Safety Board certifications...

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

    allocated funding NNSA and Defense Nuclear Facilities Safety Board certifications free up 47 million in previously allocated funding The DNFSB and NNSA required the CMRR...

  16. Approaches used for Clearance of Lands from Nuclear Facilities...

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

    for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input," focuses on the issue of showing compliance with given clearance levels ...

  17. Enterprise Assessments Targeted Review of Nuclear Reactor Facility...

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

    Reactor Facility Operations at Sandia National Laboratories The U.S. Department of Energy independent Office of Enterprise Assessments (EA) conducted a review of nuclear reactor ...

  18. Sandia completes major overhaul of key nuclear weapons test facilities |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration | (NNSA) completes major overhaul of key nuclear weapons test facilities Tuesday, May 13, 2014 - 2:46pm Sandia National Laboratories recently completed the renovation of five large-scale test facilities that are crucial to ensuring the safety and reliability of the nation's nuclear weapons systems. The work supports Sandia's ongoing nuclear stockpile modernization work on the B61-12 and W88 Alt, assessments of current stockpile systems, and test and

  19. Windy Flats(3Q09 portion) | Open Energy Information

    Open Energy Info (EERE)

    Flats(3Q09 portion) Jump to: navigation, search Name Windy Flats(3Q09 portion) Facility Windy Flats(3Q09 portion) Sector Wind energy Facility Type Commercial Scale Wind Facility...

  20. Infrastructure and Facilities Management | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    backlog of old facilities, reduction of excess facilities and utility construction. ... real property), and infrastructure planning and line item construction sub-programs. ...

  1. high explosives pressing facility | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    pressing facility high explosives pressing facility Thornberry hosts House Majority Leader at Pantex visit Rep. Mac Thornberry, R-Texas, hosted Majority Leader Kevin McCarthy,...

  2. Verification of Readiness to Start Up or Restart Nuclear Facilities

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

    2010-04-16

    The order establishes requirements for verifying readiness for startup of new Hazard Category 1, 2, and 3 nuclear facilities, activities, and operations, and for restart of existing Hazard Category 1, 2, and 3 nuclear facilities, activities, and operations that have been shut down. Adm Chg 1, dated 4-2-13, supersedes DOE O 425.1D.

  3. Verification of Readiness to Start Up or Restart Nuclear Facilities

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

    2010-04-16

    The order establishes requirements for verifying readiness for startup of new Hazard Category 1, 2, and 3 nuclear facilities, activities, and operations, and for restart of existing Hazard Category 1, 2, and 3 nuclear facilities, activities, and operations that have been shut down. Cancels DOE O 425.1C. Adm Chg 1, dated 4-2-13.

  4. Facilities | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Evaluation / Research and Development Facilities Photo: DARHT's Accelerators help create the x-rays at DARHT, the world's most advanced radiography facility. Research and Development Facilities Research and Development manages and oversees the operation of an exceptional suite of science, technology and engineering facilities that support and further the national stockpile stewardship agenda. Of varying size, scope and capabilities, the facilities work in a concert to accomplish the following

  5. National Ignition Facility | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    National Ignition Facility Glass amplifiers in Laser Bay 2 at the National Ignition Facility. The construction of the 192-beam 1.8 MJ UV NIF, the world's most energetic laser, was ...

  6. ICF Facilities | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Facilities Nike mirror array and lens array ICF operates a set of world-class experimental facilities to create HEDP conditions and to obtain quantitative data in support of its numerous stockpile stewardship-related activities. To learn about three high energy experimental facilities and two small lasers that provide ICF capabilities, select the links below. National Ignition Facility, Lawrence Livermore National Laboratory OMEGA and OMEGA EP, University of Rochester Laboratory for Laser

  7. Enterprise Assessments Targeted Review of the Targeted Review of the Safety Significant Ventilation System and Interconnected Portions of the Associated Safety Class Confinement System, and Review of Federal Assurance Capability at the Los Alamos National Laboratory Technical Area 55 Plutonium Facility ¬Ö August 2015

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

    Review of the Safety Significant Ventilation System and Interconnected Portions of the Associated Safety Class Confinement System, and Review of Federal Assurance Capability at the Los Alamos National Laboratory Technical Area 55 Plutonium Facility August 2015 Office of Nuclear Safety and Environmental Assessments Office of Environment, Safety and Health Assessments Office of Enterprise Assessments U.S. Department of Energy i Table of Contents Acronyms

  8. ICF Facilities | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    ICF operates a set of world-class experimental facilities to create HEDP conditions and to obtain quantitative data in support of its numerous stockpile stewardship-related ...

  9. Interface with the Defense Nuclear Facilities Safety Board

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

    1999-01-26

    This Manual presents the process the Department of Energy will use to interface with the Defense Nuclear Facilities Safety Board (DNFSB) and its staff. Cancels DOE M 140.1-1.

  10. Appendix B: Rules and Directives Applicable to Nuclear Facilities...

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

    Appendix B: Rules and Directives Applicable to Nuclear Facilities Line Management Oversight Appendix B to DOE G 226.1-2A "Federal Line Management Oversight of Department of Energy ...

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

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

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

  12. Interface with the Defense Nuclear Facilities Safety Board

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

    1996-12-30

    The manual defines the process DOE will use to interface with the Defense Nuclear Facilities Safety Board and its staff. Canceled by DOE M 140.1-1A. Does not cancel other directives.

  13. Federal Line Management Oversight of Department of Energy Nuclear Facilities

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

    2013-04-04

    The Guide was developed in support of DOE O 226.1B to provide guidance that may be useful to DOE line management organizations in meeting the provisions of that order when applied to nuclear facilities.

  14. Interface with the Defense Nuclear Facilities Safety Board

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

    2001-03-30

    This Manual presents the process the Department of Energy will use to interface with the Defense Nuclear Facilities Safety Board (DNFSB) and its staff. Supersedes DOE M 140.1-1A.

  15. Preparation Of Nonreactor Nuclear Facility Documented Safety Analysis

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

    2014-11-12

    This Department of Energy (DOE) Standard (STD), DOE-STD-3009-2014, describes a method for preparing a Documented Safety Analysis (DSA) that is acceptable to DOE for nonreactor nuclear facilities.

  16. CRAD, NNSA- Startup and Restart of Nuclear Facilities (SNF)

    Broader source: Energy.gov [DOE]

    CRAD for Startup and Restart of Nuclear Facilities (SNF). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs.

  17. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    SciTech Connect (OSTI)

    Garcia, Humberto; Burr, Tom; Coles, Garill A; Edmunds, Thomas A.; Garrett, Alfred; Gorensek, Maximilian; Hamm, Luther; Krebs, John; Kress, Reid L; Lamberti, Vincent; Schoenwald, David; Tzanos, Constantine P; Ward, Richard C

    2012-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  18. INTEGRATION OF FACILITY MODELING CAPABILITIES FOR NUCLEAR NONPROLIFERATION ANALYSIS

    SciTech Connect (OSTI)

    Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

    2011-07-18

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  19. Criteria for Evaluation of Nuclear Facility Training Programs

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

    Reaffirmed July 2014 DOE STANDARD CRITERIA FOR EVALUATION OF NUCLEAR FACILITY TRAINING PROGRAMS (Formerly Titled: Guidelines for Evaluation of Nuclear Facility Training Programs) U.S. Department of Energy FSC-6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE-STD-1070-94 This document is available on the Department of Energy Technical Standards Program Web page at http://www.hss.doe.gov/nuclearsafety/ns/techstds/ DOE-STD-1070-94

  20. Report of the Facilities Subcommittee Nuclear Energy Advisory Committee

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

    Facilities Subcommittee Nuclear Energy Advisory Committee Presented June 17, 2016 Washington DC John I Sackett Charge to the Facilities Subcommittee * "..request that NEAC now undertake a forward looking review of where you believe the Idaho National Laboratory should be ten years from now to maintain overall world-class status in nuclear energy research, development, and demonstration, and considering its role as a maturing multi-program national laboratory." * "The review should

  1. Deactivation and Storage Issues Shared by Fossil and Nuclear Facilities

    SciTech Connect (OSTI)

    Thomas S. LaGuardia

    1998-12-31

    The deactivation of a power plant, be it nuclear or fossil fueled, requires that the facility be placed in a safe and stable condition to prevent unacceptable exposure of the public or the environment to hazardous materials until the facility can be decommissioned. The conditions at two Texas plants are examined. These plants are fossil fueled, but their conditions might be duplicated at a nuclear plant.

  2. Departmental Representative to the Defense Nuclear Facilities Safety Board

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

    (DNFSB) | Department of Energy Departmental Representative to the Defense Nuclear Facilities Safety Board (DNFSB) Departmental Representative to the Defense Nuclear Facilities Safety Board (DNFSB) The Office of the Departmental Representative ensures effective cross-organizational leadership and coordination to resolve DNFSB-identified technical and management issues as we work to ensure the health, safety, and security of the workers, public, and environment. This web site is an important

  3. HYDROGEN IGNITION MECHANISM FOR EXPLOSIONS IN NUCLEAR FACILITY PIPE SYSTEMS

    SciTech Connect (OSTI)

    Leishear, R

    2010-05-02

    Hydrogen and oxygen generation due to the radiolysis of water is a recognized hazard in pipe systems used in the nuclear industry, where the accumulation of hydrogen and oxygen at high points in the pipe system is expected, and explosive conditions exist. Pipe ruptures at nuclear facilities were attributed to hydrogen explosions inside pipelines, in nuclear facilities, i.e., Hamaoka, Nuclear Power Station in Japan, and Brunsbuettel in Germany. Prior to these accidents an ignition source for hydrogen was questionable, but these accidents, demonstrated that a mechanism was, in fact, available to initiate combustion and explosion. Hydrogen explosions may occur simultaneously with water hammer accidents in nuclear facilities, and a theoretical mechanism to relate water hammer to hydrogen deflagrations and explosions is presented herein.

  4. Facility Approvals, Security Surveys, and Nuclear Materials Surveys

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

    1992-09-15

    To establish Department of Energy (DOE) requirements for granting facility approvals prior to permitting safeguards and security interests on the premises and the conduct of insite security and/or nuclear material surveys of facilities with safeguards and security interests. Cancels DOE 5634.1A. Canceled by DOE O 470.1 dated 9-28-95.

  5. Facility Approvals, Security Surveys, and Nuclear Materials Surveys

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

    1988-02-03

    To establish the Department of Energy (DOE) requirements for granting facility approvals prior to permitting safeguards and security interests on the premises and the conduct of on-site security and/or nuclear material surveys of facilities with safeguards and security interests. Cancels DOE O 5630.7 and DOE O 5634.1. Canceled by DOE 5634.1B.

  6. Nuclear Energy Advisory Committee Facility Subcommittee visit...

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

    Klein (Oregon State University). Tansel Selekler (Department of Energy Office of Nuclear Energy) accompanied the Subcommittee. The visit was well-coordinated by Sherrell...

  7. National Ignition Facility | National Nuclear Security Administration |

    National Nuclear Security Administration (NNSA)

    (NNSA) National Ignition Facility Glass amplifiers in Laser Bay 2 at the National Ignition Facility. The construction of the 192-beam 1.8 MJ UV NIF, the world's most energetic laser, was completed in March 2009. Current experiments are focusing on using the NIF laser and other ICF high energy density facilities leading to demonstrate fusion ignition and thermonuclear burn in the laboratory. The NIF is also being used to support basic science and SSP experiments. By the end of FY 2012, the

  8. Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities

    Office of Environmental Management (EM)

    1 -- Nuclear Safety Basis Program Review Overview and Management Oversight February 2015 i Standard Review Plan Volume 1 Nuclear Safety Basis Program Review Overview and Management Oversight Facility Life Cycle Applicability CD-1 CD-2 CD-3 CD-4 Operations and Transitions Decommissioning & Environmental Restoration February 2015 ii Table of Contents Acronyms ................................................................................................................................... iii

  9. Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities

    Office of Environmental Management (EM)

    5 - Nuclear Safety Basis Program Review of TSRs, USQs and SERs February 2015 i Standard Review Plan Volume 5 Nuclear Safety Basis Program Review of TSRs, USQs and SERs Facility Life Cycle Applicability CD-1 CD-2 CD-3 CD-4 Operations and Transitions Decommissioning & Environmental Restoration February 2015 ii Table of Contents Acronyms ................................................................................................................................... iii Introduction

  10. Personnel Selection, Qualification, and Training Requirements for DOE Nuclear Facilities

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

    2001-07-12

    To establish selection, qualification, and training requirements for management and operating (M&O) contractor personnel involved in the operation, maintenance, and technical support of Department of Energy and National Nuclear Security Administration Category A and B reactors and non-reactor nuclear facilities. Canceled by DOE O 426.2

  11. Method and means of monitoring the effluent from nuclear facilities

    DOE Patents [OSTI]

    Lattin, Kenneth R.; Erickson, Gerald L.

    1976-01-01

    Radioactive iodine is detected in the effluent cooling gas from a nuclear reactor or nuclear facility by passing the effluent gas through a continuously moving adsorbent filter material which is then purged of noble gases and conveyed continuously to a detector of radioactivity. The purging operation has little or no effect upon the concentration of radioactive iodine which is adsorbed on the filter material.

  12. EM Issues Amended Decision to Expand Use of Nuclear Facility

    Broader source: Energy.gov [DOE]

    AIKEN, S.C. ‚Äď EM issued an amended Record of Decision (ROD) to the Savannah River Site (SRS) Spent Nuclear Fuel Environmental Impact Statement to expand the operations of the H-Canyon Facility at SRS to support a major nuclear non-proliferation goal and save taxpayer dollars.

  13. lasers. National Ignition Facility | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    target shot of fiscal year 2015 WASHINGTON - Last week, the National Ignition Facility (NIF) fired its 300th laser target shot in fiscal year (FY) 2015, meeting the year's goal...

  14. Highly Enriched Uranium Materials Facility | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Congressmen tour Y-12 facilities During a recent visit to the Y-12 National Security Complex, Rep. Mike Simpson (R-Idaho), chairman of the House Energy and Water Appropriations ...

  15. Public Reading Facilities | National Nuclear Security Administration...

    National Nuclear Security Administration (NNSA)

    The DOE, as well as other DOE sites, has established a home page on the Internet with links to other Web Sites. If you determine a specific facility might have records in which you ...

  16. Contained Firing Facility | National Nuclear Security Administration |

    National Nuclear Security Administration (NNSA)

    (NNSA) Contained Firing Facility The CFF firing chamber is the largest explosive chamber in the world, used for large-scale experiments using high-explosives with full containment of hazardous materials. The facility provides a combination of capabilities, including wide-angle flash radiography, laser velocimetry, pin-dome measurements, and high-speed optical cameras that are used to measure dynamics during the experiments. CFF is a key component of NNSA's national hydrotest strategy and was

  17. High Explosives Application Facility | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) High Explosives Application Facility A Livermore scientist uses a laser spectroscopic method with a diamond anvil DOE/NNSA has identified LLNL's High Explosives Applications Facility (HEAF) as the complex-wide "Center of Excellence" for High-Explosives Research and Development. In this capacity, HEAF is a source of subject matter expertise for high explosives and other energetic materials. Its mission is to provide this expertise to serve multiple government

  18. Test facilities for evaluating nuclear thermal propulsion systems

    SciTech Connect (OSTI)

    Beck, D.F.; Allen, G.C.; Shipers, L.R.; Dobranich, D.; Ottinger, C.A.; Harmon, C.D.; Fan, W.C. ); Todosow, M. )

    1992-09-22

    Interagency panels evaluating nuclear thermal propulsion (NTP) development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and baseline performance of some of the major subsystems designed to support a proposed ground test complex for evaluating nuclear thermal propulsion fuel elements and engines being developed for the Space Nuclear Thermal Propulsion (SNTP) program. Some preliminary results of evaluating this facility for use in testing other NTP concepts are also summarized.

  19. Construction Cost Growth for New Department of Energy Nuclear Facilities

    SciTech Connect (OSTI)

    Kubic, Jr., William L.

    2014-05-25

    Cost growth and construction delays are problems that plague many large construction projects including the construction of new Department of Energy (DOE) nuclear facilities. A study was conducted to evaluate cost growth of large DOE construction projects. The purpose of the study was to compile relevant data, consider the possible causes of cost growth, and recommend measures that could be used to avoid extreme cost growth in the future. Both large DOE and non-DOE construction projects were considered in this study. With the exception of Chemical and Metallurgical Research Building Replacement Project (CMRR) and the Mixed Oxide Fuel Fabrication Facility (MFFF), cost growth for DOE Nuclear facilities is comparable to the growth experienced in other mega construction projects. The largest increase in estimated cost was found to occur between early cost estimates and establishing the project baseline during detailed design. Once the project baseline was established, cost growth for DOE nuclear facilities was modest compared to non-DOE mega projects.

  20. Project Hanford management contract quality assurance program implementation plan for nuclear facilities

    SciTech Connect (OSTI)

    Bibb, E.K.

    1997-10-15

    During transition from the Westinghouse Hanford Company (WHC) Management and Operations (M and O) contract to the Fluor Daniel Hanford (FDH) Management and Integration (M and I) contract, existing WHC policies, procedures, and manuals were reviewed to determine which to adopt on an interim basis. Both WHC-SP-1131,Hanford Quality Assurance Program and Implementation Plan, and WHC-CM-4-2, Quality Assurance Manual, were adopted; however, it was recognized that revisions were required to address the functions and responsibilities of the Project Hanford Management Contract (PHMC). This Quality Assurance Program Implementation Plan for Nuclear Facilities (HNF-SP-1228) supersedes the implementation portion of WHC-SP-1 13 1, Rev. 1. The revised Quality Assurance (QA) Program is documented in the Project Hanford Quality Assurance Program Description (QAPD), HNF-MP-599. That document replaces the QA Program in WHC-SP-1131, Rev. 1. The scope of this document is limited to documenting the nuclear facilities managed by FDH and its Major Subcontractors (MSCS) and the status of the implementation of 10 CFR 830.120, Quality Assurance Requirements, at those facilities. Since the QA Program for the nuclear facilities is now documented in the QAPD, future updates of the information provided in this plan will be by letter. The layout of this plan is similar to that of WHC-SP-1 13 1, Rev. 1. Sections 2.0 and 3.0 provide an overview of the Project Hanford QA Program. A list of Project Hanford nuclear facilities is provided in Section 4.0. Section 5.0 provides the status of facility compliance to 10 CFR 830.120. Sections 6.0, 7.0, and 8.0 provide requested exemptions, status of open items, and references, respectively. The four appendices correspond to the four projects that comprise Project Hanford.

  1. Laboratory instrumentation modernization at the WPI Nuclear Reactor Facility

    SciTech Connect (OSTI)

    Not Available

    1995-01-01

    With partial funding from the Department of Energy (DOE) University Reactor Instrumentation Program several laboratory instruments utilized by students and researchers at the WPI Nuclear Reactor Facility have been upgraded or replaced. Designed and built by General Electric in 1959, the open pool nuclear training reactor at WPI was one of the first such facilities in the nation located on a university campus. Devoted to undergraduate use, the reactor and its related facilities have been since used to train two generations of nuclear engineers and scientists for the nuclear industry. The low power output of the reactor and an ergonomic facility design make it an ideal tool for undergraduate nuclear engineering education and other training. The reactor, its control system, and the associate laboratory equipment are all located in the same room. Over the years, several important milestones have taken place at the WPI reactor. In 1969, the reactor power level was upgraded from 1 kW to 10 kW. The reactor`s Nuclear Regulatory Commission operating license was renewed for 20 years in 1983. In 1988, under DOE Grant No. DE-FG07-86ER75271, the reactor was converted to low-enriched uranium fuel. In 1992, again with partial funding from DOE (Grant No. DE-FG02-90ER12982), the original control console was replaced.

  2. National Ignition Facility | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Ignition Facility Former Army Ranger wins Sandia-sponsored student of the year award Former Army Ranger Damon Alcorn recently received the Sandia National Laboratories-Livermore Chamber of Commerce Student of the Year Award. Presented at the Chamber's State of the City Luncheon last month, the annual award highlights a Las Positas College student with exemplary academic... NNSA makers and hackers engage innovation and partnerships NNSA's labs change the world everyday through cutting-edge

  3. Assessment of Space Nuclear Thermal Propulsion Facility and Capability Needs

    SciTech Connect (OSTI)

    James Werner

    2014-07-01

    The development of a Nuclear Thermal Propulsion (NTP) system rests heavily upon being able to fabricate and demonstrate the performance of a high temperature nuclear fuel as well as demonstrating an integrated system prior to launch. A number of studies have been performed in the past which identified the facilities needed and the capabilities available to meet the needs and requirements identified at that time. Since that time, many facilities and capabilities within the Department of Energy have been removed or decommissioned. This paper provides a brief overview of the anticipated facility needs and identifies some promising concepts to be considered which could support the development of a nuclear thermal propulsion system. Detailed trade studies will need to be performed to support the decision making process.

  4. Nuclear Science User Facilities (NSUF) Monthly Report March 2015

    SciTech Connect (OSTI)

    Soelberg, Renae

    2015-03-01

    Nuclear Science User Facilities (NSUF) Formerly: Advanced Test Reactor National Scientific User Facility (ATR NSUF) Monthly Report February 2015 Highlights; Jim Cole attended the OECD NEA Expert Group on Innovative Structural Materials meeting in Paris, France; Jim Lane and Doug Copsey of Writers Ink visited PNNL to prepare an article for the NSUF annual report; Brenden Heidrich briefed the Nuclear Energy Advisory Committee-Facilities Subcommittee on the Nuclear Energy Infrastructure Database project and provided them with custom reports for their upcoming visits to Argonne National Laboratory, Idaho National Laboratory, Oak Ridge National Laboratory and the Massachusetts Institute of Technology; and University of California-Berkeley Principal Investigator Mehdi Balooch visited PNNL to observe measurements and help finalize plans for completing the desired suite of analyses. His visit was coordinated to coincide with the visit of Jim Lane and Doug Copsey.

  5. Nondestructive assay of special nuclear material for uranium fuel-fabrication facilities

    SciTech Connect (OSTI)

    Smith, H.A. Jr.; Schillebeeckx, P.

    1997-08-01

    A high-quality materials accounting system and effective international inspections in uranium fuel-fabrication facilities depend heavily upon accurate nondestructive assay measurements of the facility`s nuclear materials. While item accounting can monitor a large portion of the facility inventory (fuel rods, assemblies, storage items), the contents of all such items and mass values for all bulk materials must be based on quantitative measurements. Weight measurements, combined with destructive analysis of process samples, can provide highly accurate quantitative information on well-characterized and uniform product materials. However, to cover the full range of process materials and to provide timely accountancy data on hard-to-measure items and rapid verification of previous measurements, radiation-based nondestructive assay (NDA) techniques play an important role. NDA for uranium fuel fabrication facilities relies on passive gamma spectroscopy for enrichment and U isotope mass values of medium-to-low-density samples and holdup deposits; it relies on active neutron techniques for U-235 mass values of high-density and heterogeneous samples. This paper will describe the basic radiation-based nondestructive assay techniques used to perform these measurements. The authors will also discuss the NDA measurement applications for international inspections of European fuel-fabrication facilities.

  6. Ceremony celebrates new NNSA facility in Kansas City | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Ceremony celebrates new NNSA facility in Kansas City Friday, August 22, 2014 - 3:00pm Energy Secretary Ernest Moniz and Under Secretary for Nuclear Security and NNSA Administrator Lt. Gen. Frank Klotz today hailed the completion of the new National Security Campus at a dedication ceremony in Kansas City, Mo. The new facility was completed ahead of schedule, $10 million under budget, and with the site's best safety and security performance on record. The event

  7. Computational Nuclear Structure | Argonne Leadership Computing Facility

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

    Excellent scaling is achieved by the production Automatic Dynamic Load Balancing (ADLB) library on the BG/P. Computational Nuclear Structure PI Name: David Dean Hai Nam PI Email: namha@ornl.gov deandj@ornl.gov Institution: Oak Ridge National Laboratory Allocation Program: INCITE Allocation Hours at ALCF: 15 Million Year: 2010 Research Domain: Physics Researchers from Oak Ridge and Argonne national laboratories are using complementary techniques, including Green's Function Monte Carlo, the No

  8. Nuclear and Facility Safety Directives | Department of Energy

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

    Directives Nuclear and Facility Safety Directives DOE Order (O) 252.1A, Technical Standards Program DOE O 252.1A promotes DOE's use of Voluntary Consensus Standards (VCS) as the primary method for application of technical standards and establishes and manages the DOE Technical Standards Program (TSP) including technical standards development, information, activities, issues, and interactions. AU-30 Contact: Jeff Feit DOE Policy (P) 420.1, Department of Energy Nuclear Safety Policy DOE P 420.1,

  9. Support of the Iraq nuclear facility dismantlement and disposal program

    SciTech Connect (OSTI)

    Coates, Roger; Cochran, John; Danneels, Jeff; Chesser, Ronald; Phillips, Carlton; Rogers, Brenda

    2007-07-01

    Available in abstract form only. Full text of publication follows: Iraq's former nuclear facilities contain large quantities of radioactive materials and radioactive waste. The Iraq Nuclear Facility Dismantlement and Disposal Program (the Iraq NDs Program) is a new program to decontaminate and permanently dispose of radioactive wastes in Iraq. The NDs Program is led by the Government of Iraq, under International Atomic Energy Agency (IAEA) auspices, with guidance and assistance from a number of countries. The U.S. participants include Texas Tech University and Sandia National Laboratories. A number of activities are ongoing under the broad umbrella of the Iraq NDs Program: drafting a new nuclear law that will provide the legal basis for the cleanup and disposal activities; assembly and analysis of existing data; characterization of soil contamination; bringing Iraqi scientists to the world's largest symposium on radioactive waste management; touring U.S. government and private sector operating radwaste disposal facilities in the U.S., and hosting a planning workshop on the characterization and cleanup of the Al-Tuwaitha Nuclear Facility. (authors)

  10. Iraq nuclear facility dismantlement and disposal project (NDs Project).

    SciTech Connect (OSTI)

    Cochran, John Russell

    2010-06-01

    The Al Tuwaitha nuclear complex near Baghdad contains a number of facilities from Saddam Hussan's nuclear weapons program. Past military operations, lack of upkeep and looting have created an enormous radioactive waste problem at the Al Tuwaitha complex, which contains various, uncharacterized radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals that must be constantly guarded. Iraq has never had a radioactive waste disposal facility and the lack of a disposal facility means that ever increasing quantities of radioactive material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS is funding the IAEA to provide technical assistance via Technical Cooperation projects. Program coordination will be provided by the DOS, consistent with GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for implementation of the NDs Program.

  11. Federal Line Management Oversight of Department of Energy Nuclear Facilities

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

    2014-04-14

    The Guide was developed in support of DOE O 226.1B to provide guidance that may be useful to DOE line management organizations in meeting the provisions of that order when applied to nuclear facilities. Supersedes DOE G 226.1-2

  12. Los Alamos Neutron Science Center (LANSCE) Nuclear Science Facilities

    SciTech Connect (OSTI)

    Nelson, Ronald Owen; Wender, Steve

    2015-06-19

    The Los Alamos Neutron Science Center (LANSCE) facilities for Nuclear Science consist of a high-energy "white" neutron source (Target 4) with 6 flight paths, three low-energy nuclear science flight paths at the Lujan Center, and a proton reaction area. The neutron beams produced at the Target 4 complement those produced at the Lujan Center because they are of much higher energy and have shorter pulse widths. The neutron sources are driven by the 800-MeV proton beam of the LANSCE linear accelerator. With these facilities, LANSCE is able to deliver neutrons with energies ranging from a milli-electron volt to several hundreds of MeV, as well as proton beams with a wide range of energy, time and intensity characteristics. The facilities, instruments and research programs are described briefly.

  13. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    SciTech Connect (OSTI)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-07-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning

  14. EARTHQUAKE CAUSED RELEASES FROM A NUCLEAR FUEL CYCLE FACILITY

    SciTech Connect (OSTI)

    Charles W. Solbrig; Chad Pope; Jason Andrus

    2014-08-01

    The fuel cycle facility (FCF) at the Idaho National Laboratory is a nuclear facility which must be licensed in order to operate. A safety analysis is required for a license. This paper describes the analysis of the Design Basis Accident for this facility. This analysis involves a model of the transient behavior of the FCF inert atmosphere hot cell following an earthquake initiated breach of pipes passing through the cell boundary. The hot cell is used to process spent metallic nuclear fuel. Such breaches allow the introduction of air and subsequent burning of pyrophoric metals. The model predicts the pressure, temperature, volumetric releases, cell heat transfer, metal fuel combustion, heat generation rates, radiological releases and other quantities. The results show that releases from the cell are minimal and satisfactory for safety. This analysis method should be useful in other facilities that have potential for damage from an earthquake and could eliminate the need to back fit facilities with earthquake proof boundaries or lessen the cost of new facilities.

  15. Nuclear diagnostics for the National Ignition Facility (invited)

    SciTech Connect (OSTI)

    Murphy, Thomas J.; Barnes, Cris W.; Berggren, R. R.; Bradley, P.; Caldwell, S. E.; Chrien, R. E.; Faulkner, J. R.; Gobby, P. L.; Hoffman, N.; Jimerson, J. L.

    2001-01-01

    The National Ignition Facility (NIF), currently under construction at the Lawrence Livermore National Laboratory, will provide unprecedented opportunities for the use of nuclear diagnostics in inertial confinement fusion experiments. The completed facility will provide 2 MJ of laser energy for driving targets, compared to the approximately 40 kJ that was available on Nova and the approximately 30 kJ available on Omega. Ignited NIF targets are anticipated to produce up to 10{sup 19} DT neutrons. In addition to a basic set of nuclear diagnostics based on previous experience, these higher NIF yields are expected to allow innovative nuclear diagnostic techniques to be utilized, such as neutron imaging, recoil proton techniques, and gamma-ray-based reaction history measurements.

  16. Facilities

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

    Facilities Facilities LANL's mission is to develop and apply science and technology to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. Contact Operator Los Alamos National Laboratory (505) 667-5061 Some LANL facilities are available to researchers at other laboratories, universities, and industry. Unique facilities foster experimental science, support the Lab's security mission

  17. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    SciTech Connect (OSTI)

    Burr, Tom; Gorensek, M. B.; Krebs, John; Kress, Reid L; Lamberti, Vincent; Schoenwald, David; Ward, Richard C

    2012-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclearnonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facilitymodeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facilitymodeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facilitymodelingcapabilities and illustrates how they could be integrated and utilized for nonproliferationanalysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facilitymodeling tools. After considering a representative sampling of key facilitymodelingcapabilities, the proposed integration framework is illustrated with several examples.

  18. SUMMARY OF REVISED TORNADO, HURRICANE AND EXTREME STRAIGHT WIND CHARACTERISTICS AT NUCLEAR FACILITY SITES

    Office of Energy Efficiency and Renewable Energy (EERE)

    Summary of Revised Tornado, Hurricane and Extreme Straight Wind Characteristics at Nuclear Facility Sites BY: John D. Stevenson Consulting Engineer

  19. Pyroprocessing of Fast Flux Test Facility Nuclear Fuel

    SciTech Connect (OSTI)

    B.R. Westphal; G.L. Fredrickson; G.G. Galbreth; D. Vaden; M.D. Elliott; J.C. Price; E.M. Honeyfield; M.N. Patterson; L. A. Wurth

    2013-10-01

    Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electrorefined uranium products exceeded 99%.

  20. Pyroprocessing of fast flux test facility nuclear fuel

    SciTech Connect (OSTI)

    Westphal, B.R.; Wurth, L.A.; Fredrickson, G.L.; Galbreth, G.G.; Vaden, D.; Elliott, M.D.; Price, J.C.; Honeyfield, E.M.; Patterson, M.N.

    2013-07-01

    Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electro-refined uranium products exceeded 99%. (authors)

  1. Underground Facility at Nevada National Security Site | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Underground Facility at Nevada National Security Site The U1a Complex is an underground laboratory at the Nevada National Security Site used for dynamic experiments with special nuclear material (SNM) and other weapon materials. The Complex provides an infrastructure of high-bandwidth diagnostics, data acquisition, timing and firing, control and monitor systems capable of supporting experiments designed to acquire information on fundamental materials

  2. Federal Line Management Oversight of Department of Energy Nuclear Facilities

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

    2011-04-25

    The purpose of this Guide is to provide U.S. Department of Energy (DOE) line management with guidance that may be useful to them in effectively and efficiently implementing the requirements of DOE O 226.1B, Implementation of Department of Energy Oversight Policy, date April 25, 2011, as applied to Federal line management of hazard category 1, 2, and 3 nuclear facilities.

  3. Airborne release fractions/rates and respirable fractions for nonreactor nuclear facilities. Volume 2, Appendices

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    This document contains compiled data from the DOE Handbook on Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear facilities. Source data and example facilities utilized, such as the Plutonium Recovery Facility, are included.

  4. DOE - Office of Legacy Management -- Piqua Nuclear Power Facility - OH 08

    Office of Legacy Management (LM)

    Piqua Nuclear Power Facility - OH 08 FUSRAP Considered Sites Site: Piqua Nuclear Power Facility (OH.08 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Piqua, Ohio, Decommissioned Reactor Site Documents Related to Piqua Nuclear Power Facility

  5. Nuclear facility decommissioning and site remedial actions: a selected bibliography

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

    1982-09-01

    This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

  6. DECOMMISSIONING OF NUCLEAR FACILITIES IN GERMANY - STATUS AT BMBF SITES

    SciTech Connect (OSTI)

    Papp, R.; Komorowski, K.

    2002-02-25

    In a period of approximately 40 years prior to 1994, the German Federal Government had spent about {approx} 15 billion to promote nuclear technology. These funds were earmarked for R&D projects as well as demonstration facilities which took up operation between 1960 and 1980. These BMBF (Federal Ministry for Research) facilities were mainly located at the sites of the federal research centers at Juelich and Karlsruhe (the research reactors AVR, FR2, FRJ-1, KNK, and MZFR, the pilot reprocessing plant WAK) but included also the pilot plants SNR-300 and THTR-300 for fast breeder and high-temperature gas-cooled reactor development, respectively, and finally the salt mine Asse which had been used for waste emplacement prior to conversion into an underground research laboratory. In the meantime, almost all of these facilities were shut down and are now in a state of decommissioning and dismantling. This is mainly due to the facts that R&D needs are satisfied or do not exist any more and that, secondly, the lack of political consensus led to the cancellation of advanced nuclear technology.

  7. Melting of the metallic wastes generated by dismantling retired nuclear research facilities

    SciTech Connect (OSTI)

    Chong-Hun Jung; Pyung-Seob Song; Byung-Youn Min; Wang-Kyu Choi

    2008-01-15

    The decommissioning of nuclear installations results in considerably large amounts of radioactive metallic wastes such as stainless steel, carbon steel, aluminum, copper etc. It is known that the reference 1,000 MWe PWR and 881 MWe PHWR will generate metal wastes of 24,800 ton and 26,500 ton, respectively. In Korea, the D and D of KRR-2 and a UCP at KAERI have been performed. The amount of metallic wastes from the KRR-1 and UCP was about 160 ton and 45 ton, respectively, up to now. These radioactive metallic wastes will induce problems of handling and storing these materials from environmental and economical aspects. For this reason, prompt countermeasures should be taken to deal with the metal wastes generated by dismantling retired nuclear facilities. The most interesting materials among the radioactive metal wastes are stainless steel (SUS), carbon steel (CS) and aluminum wastes because they are the largest portions of the metallic wastes generated by dismantling retired nuclear research facilities. As most of these steels are slightly contaminated, if they are properly treated they are able to be recycled and reused in the nuclear field. In general, the technology of a metal melting is regarded as one of the most effective methods to treat metallic wastes from nuclear facilities. In conclusion: The melting of metal wastes (Al, SUS, carbon steel) from a decommissioning of research reactor facilities was carried out with the use of a radioisotope such as cobalt and cesium in an electric arc furnace. In the aluminum melting tests, the cobalt was captured at up to 75% into the slag phase. Most of the cesium was completely eliminated from the aluminum ingot phase and moved into the slag and dust phases. In the melting of the stainless steel wastes, the {sup 60}Co could almost be retained uniformly in the ingot phase. However, we found that significant amounts of {sup 60}Co remained in the slag at up to 15%. However the removal of the cobalt from the ingot phase was

  8. Financing Strategies For A Nuclear Fuel Cycle Facility

    SciTech Connect (OSTI)

    David Shropshire; Sharon Chandler

    2006-07-01

    To help meet the nation’s energy needs, recycling of partially used nuclear fuel is required to close the nuclear fuel cycle, but implementing this step will require considerable investment. This report evaluates financing scenarios for integrating recycling facilities into the nuclear fuel cycle. A range of options from fully government owned to fully private owned were evaluated using DPL (Decision Programming Language 6.0), which can systematically optimize outcomes based on user-defined criteria (e.g., lowest lifecycle cost, lowest unit cost). This evaluation concludes that the lowest unit costs and lifetime costs are found for a fully government-owned financing strategy, due to government forgiveness of debt as sunk costs. However, this does not mean that the facilities should necessarily be constructed and operated by the government. The costs for hybrid combinations of public and private (commercial) financed options can compete under some circumstances with the costs of the government option. This analysis shows that commercial operations have potential to be economical, but there is presently no incentive for private industry involvement. The Nuclear Waste Policy Act (NWPA) currently establishes government ownership of partially used commercial nuclear fuel. In addition, the recently announced Global Nuclear Energy Partnership (GNEP) suggests fuels from several countries will be recycled in the United States as part of an international governmental agreement; this also assumes government ownership. Overwhelmingly, uncertainty in annual facility capacity led to the greatest variations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; and the annual operating costs, forgiveness of debt, and overnight costs dominate the costs computed for

  9. Development of nuclear diagnostics for the National Ignition Facility (invited)

    SciTech Connect (OSTI)

    Glebov, V. Yu.; Meyerhofer, D. D.; Sangster, T. C.; Stoeckl, C.; Roberts, S.; Barrera, C. A.; Celeste, J. R.; Cerjan, C. J.; Dauffy, L. S.; Eder, D. C.; Griffith, R. L.; Haan, S. W.; Hammel, B. A.; Hatchett, S. P.; Izumi, N.; Kimbrough, J. R.; Koch, J. A.; Landen, O. L.; Lerche, R. A.; MacGowan, B. J.

    2006-10-15

    The National Ignition Facility (NIF) will provide up to 1.8 MJ of laser energy for imploding inertial confinement fusion (ICF) targets. Ignited NIF targets are expected to produce up to 10{sup 19} DT neutrons. This will provide unprecedented opportunities and challenges for the use of nuclear diagnostics in ICF experiments. In 2005, the suite of nuclear-ignition diagnostics for the NIF was defined and they are under development through collaborative efforts at several institutions. This suite includes PROTEX and copper activation for primary yield measurements, a magnetic recoil spectrometer and carbon activation for fuel areal density, neutron time-of-flight detectors for yield and ion temperature, a gamma bang time detector, and neutron imaging systems for primary and downscattered neutrons. An overview of the conceptual design, the developmental status, and recent results of prototype tests on the OMEGA laser will be presented.

  10. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    SciTech Connect (OSTI)

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  11. Human factors design guidelines for maintainability of Department of Energy nuclear facilities

    SciTech Connect (OSTI)

    Bongarra, J.P. Jr.; VanCott, H.P.; Pain, R.F.; Peterson, L.R.; Wallace, R.I.

    1985-06-18

    Intent of these guidelines is to provide design and design review teams of DOE nuclear facilities with human factors principles to enhance the design and aid in the inspection of DOE nuclear facilities, systems, and equipment. These guidelines are concerned with design features of DOE nuclear facilities which can potentially affect preventive and corrective maintenance of systems within DOE nuclear facilities. Maintenance includes inspecting, checking, troubleshooting, adjusting, replacing, repairing, and servicing activities. Other factors which influence maintainability such as repair and maintenance suport facilities, maintenance information, and various aspects of the environment are also addressed.

  12. Energy Department Issues Request For Proposal for Nuclear Regulatory Commission Licensed Facilities Procurement

    Broader source: Energy.gov [DOE]

    Cincinnati ‚Äď The U.S. Department of Energy (DOE) today issued a final Request for Proposal (RFP) for the Nuclear Regulatory Commission (NRC) Licensed Facilities procurement. The NRC Licensed Facilities contract is for managing Spent Nuclear Fuel (SNF) storage facilities and licenses under NRC regulations.

  13. Application of Engineering and Technical Requirements for 30, 60, and 90% Design of DOE Nuclear Facilities

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Standard Review Plan (SRP), Application of Engineering and Technical Requirements for 30, 60 and 90% Design of DOE Nuclear Facilities, was developed by the Office of Chief of Nuclear Safety (CNS), Office of the Environmental Management. The SRP is designed to help strengthen the technical rigor of line management oversight and federal monitoring of the design process of DOE nuclear facilities.

  14. Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for Use with DOE O 420.1, Facility Safety

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

    2000-03-28

    This Guide provides guidance on the application of requirements for nonreactor nuclear facilities and explosives facilities of Department of Energy (DOE) O 420.1, Facility Safety, Section 4.1, Nuclear and Explosives Safety Design Criteria. No cancellation.

  15. Magnet design considerations for Fusion Nuclear Science Facility

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

    Zhai, Yuhu; Kessel, Chuck; El-guebaly, Laila; Titus, Peter

    2016-02-25

    The Fusion Nuclear Science Facility (FNSF) is a nuclear confinement facility to provide a fusion environment with components of the reactor integrated together to bridge the technical gaps of burning plasma and nuclear science between ITER and the demonstration power plant (DEMO). Compared to ITER, the FNSF is smaller in size but generates much higher magnetic field, 30 times higher neutron fluence with 3 orders of magnitude longer plasma operation at higher operating temperatures for structures surrounding the plasma. Input parameters to the magnet design from system code analysis include magnetic field of 7.5 T at the plasma center withmore¬†¬Ľ plasma major radius of 4.8 m and minor radius of 1.2 m, and a peak field of 15.5 T on the TF coils for FNSF. Both low temperature superconductor (LTS) and high temperature superconductor (HTS) are considered for the FNSF magnet design based on the state-of-the-art fusion magnet technology. The higher magnetic field can be achieved by using the high performance ternary Restack Rod Process (RRP) Nb3Sn strands for toroidal field (TF) magnets. The circular cable-in-conduit conductor (CICC) design similar to ITER magnets and a high aspect ratio rectangular CICC design are evaluated for FNSF magnets but low activation jacket materials may need to be selected. The conductor design concept and TF coil winding pack composition and dimension based on the horizontal maintenance schemes are discussed. Neutron radiation limits for the LTS and HTS superconductors and electrical insulation materials are also reviewed based on the available materials previously tested. As a result, the material radiation limits for FNSF magnets are defined as part of the conceptual design studies for FNSF magnets.¬ę¬†less

  16. Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting- October 2012

    Broader source: Energy.gov [DOE]

    Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02

  17. DOE Issues Landmark Rule for Risk Insurance for Advanced Nuclear Facilities

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

    | Department of Energy Landmark Rule for Risk Insurance for Advanced Nuclear Facilities DOE Issues Landmark Rule for Risk Insurance for Advanced Nuclear Facilities May 8, 2006 - 10:36am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) issued on Saturday, the interim final rule required by the Energy Policy Act of 2005 (EPACT) for risk insurance to facilitate construction of new advanced nuclear power facilities. The rule establishes the requirements for risk insurance to cover

  18. DOE - Office of Legacy Management -- Hallam Nuclear Power Facility - NE 01

    Office of Legacy Management (LM)

    Hallam Nuclear Power Facility - NE 01 FUSRAP Considered Sites Site: Hallam Nuclear Power Facility (NE.01 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Hallam, Nebraska, Decommissioned Reactor Site Documents Related to Hallam Nuclear Power Facility U.S. Department of Energy 2009 Annual Inspection - Hallam, Nebraska June 2009 Page 1

  19. DOE-STD-1104-96 CN-1; Review and Approval of Nuclear Facility...

    Energy Savers [EERE]

    for facilities under the Office of Nuclear Energy, Science and Technology, was ... p. 12 Sect. 2.5 Safety Management Program Characteristics Requirements from 10 CFR ...

  20. CRAD, Nuclear Facility Construction- Piping and Pipe Supports Inspection- March 29, 2012

    Broader source: Energy.gov [DOE]

    Nuclear Facility Construction - Piping and Pipe Supports Inspection Criteria, Approach and Lines of Inquiry (HSS CRAD 45-52, Rev. 0)

  1. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    SciTech Connect (OSTI)

    Garvin, L.J.

    1995-11-01

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement.

  2. Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

    SciTech Connect (OSTI)

    Soelberg, Nicolas R.; Garn, Troy; Greenhalgh, Mitchell; Law, Jack; Jubin, Robert T.; Strachan, Denis M.; Thallapally, Praveen K.

    2013-07-22

    Nuclear fission results in the production of fission products and activation products, some of which tend to be volatile during used fuel reprocessing. These can evolve in volatile species in the reprocessing facility off-gas streams, depending on the separations and reprocessing technologies that are used. Radionuclides that have been identified as ‚Äúvolatile radionuclides‚ÄĚ are noble gases (most notably isotopes of Kr and Xe); 3H; 14C; and 129I. Radionuclides that tend to form volatile species that evolve into reprocessing facility off-gas systems are more challenging to efficiently control compared to radionuclides that tend to stay in solid or liquid phases. Future used fuel reprocessing facilities in the United States can require efficient capture of some volatile radionuclides in their off-gas streams to meet regulatory emission requirements. In aqueous reprocessing, these radionuclides are most commonly expected to evolve into off-gas streams in tritiated water [3H2O (T2O) and 3HHO (THO)], radioactive CO2, noble gases, and gaseous HI, I2, or volatile organic iodides. The fate and speciation of these radionuclides from a non-aqueous fuel reprocessing facility is less well known at this time, but active investigations are in progress. An Off-Gas Sigma Team was formed in late FY 2009 to integrate and coordinate the Fuel Cycle Research and Development (FCR&D) activities directed towards the capture and sequestration of the these volatile radionuclides (Jubin 2012a). The Sigma Team concept was envisioned to bring together multidisciplinary teams from across the DOE complex that would work collaboratively to solve the technical challenges and to develop the scientific basis for the capture and immobilization technologies such that the sum of the efforts was greater than the individual parts. The Laboratories currently participating in this effort are Argonne National Laboratory (ANL), Idaho National Laboratory (INL), Oak Ridge National Laboratory (ORNL), Pacific

  3. Safeguards considerations related to the decontamination and decommissioning of former nuclear weapons facilities

    SciTech Connect (OSTI)

    Crawford, D.

    1995-12-31

    In response to the post-Cold War environment and the changes in the U. S. Department of Energy defense mission, many former nuclear operations are being permanently shut down. These operations include facilities where nuclear materials production, processing, and weapons manufacturing have occurred in support of the nation`s defense industry. Since defense-related operations have ceased, many of the classification and sensitive information concerns do not exist. However, nuclear materials found at these sites are of interest to the DOE from environmental, safety and health, and materials management perspectives. Since these facilities played a role in defense activities, the nuclear materials found at these facilities are considered special nuclear materials, primarily highly enriched uranium and/or plutonium. Consequently, these materials pose significant diversion, theft, and sabotage threats, and significant nuclear security issues exist that must be addressed. This paper focuses on the nuclear materials protection issues associated with facility decommissioning and decontamination, primarily safeguards.

  4. DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility in

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

    Idaho | Department of Energy Loan Guarantee for Front End Nuclear Facility in Idaho DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility in Idaho May 20, 2010 - 12:00am Addthis Washington, DC - As part of a broad effort to expand the use of nuclear power in the United States and reduce carbon pollution, U.S. Secretary of Energy Steven Chu announced today the Department's first conditional commitment for a front-end nuclear facility. The $2 billion loan guarantee will support

  5. A survey of decontamination processes applicable to DOE nuclear facilities

    SciTech Connect (OSTI)

    Chen, L.; Chamberlain, D.B.; Conner, C.; Vandegrift, G.F.

    1997-05-01

    The objective of this survey was to select an appropriate technology for in situ decontamination of equipment interiors as part of the decommissioning of U.S. Department of Energy nuclear facilities. This selection depends on knowledge of existing chemical decontamination methods. This report provides an up-to-date review of chemical decontamination methods. According to available information, aqueous systems are probably the most universally used method for decontaminating and cleaning metal surfaces. We have subdivided the technologies, on the basis of the types of chemical solvents, into acid, alkaline permanganate, highly oxidizing, peroxide, and miscellaneous systems. Two miscellaneous chemical decontamination methods (electrochemical processes and foam and gel systems) are also described. A concise technical description of various processes is given, and the report also outlines technical considerations in the choice of technologies, including decontamination effectiveness, waste handing, fields of application, and the advantages and limitations in application. On the basis of this survey, six processes were identified for further evaluation. 144 refs., 2 tabs.

  6. Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

    SciTech Connect (OSTI)

    N. R. Soelberg; J. D. Law; T. G. Garn; M. Greenhalgh; R. T. Jubin; P. Thallapally; D. M. Strachan

    2013-08-01

    The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radionuclide control and immobilization problems. In this paper, we focus on the control requirements and methodologies for 85Kr and 129I. Numerous candidate technologies have been studied and developed at laboratory and pilot-plant scales in an effort to meet the need for high iodine control efficiency and to advance alternatives to cryogenic separations for krypton control. Several of these show promising results. Iodine decontamination factors as high as 105, iodine loading capacities, and other adsorption parameters including adsorption rates have been demonstrated under some conditions for both silver zeolite (AgZ) and Ag-functionalized aerogel. Sorbents, including an engineered form of AgZ and selected metal organic framework materials (MOFs), have been successfully demonstrated to capture Kr and Xe without the need for separations at cryogenic temperatures.

  7. Heat barrier for use in a nuclear reactor facility

    DOE Patents [OSTI]

    Keegan, Charles P.

    1988-01-01

    A thermal barrier for use in a nuclear reactor facility is disclosed herein. Generally, the thermal barrier comprises a flexible, heat-resistant web mounted over the annular space between the reactor vessel and the guard vessel in order to prevent convection currents generated in the nitrogen atmosphere in this space from entering the relatively cooler atmosphere of the reactor cavity which surrounds these vessels. Preferably, the flexible web includes a blanket of heat-insulating material formed from fibers of a refractory material, such as alumina and silica, sandwiched between a heat-resistant, metallic cloth made from stainless steel wire. In use, the web is mounted between the upper edges of the guard vessel and the flange of a sealing ring which surrounds the reactor vessel with a sufficient enough slack to avoid being pulled taut as a result of thermal differential expansion between the two vessels. The flexible web replaces the rigid and relatively complicated structures employed in the prior art for insulating the reactor cavity from the convection currents generated between the reactor vessel and the guard vessel.

  8. DOE-STD-1067; DOE Standard Guideline to Good Practices for Maintenance Facilities, Equipment, and Tools at DOE Nuclear Facilities

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

    7-94 June 1994 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR MAINTENANCE FACILITIES, EQUIPMENT, AND TOOLS AT DOE NUCLEAR FACILITIES U.S. Department of Energy AREA MNTY Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (615) 576-8401. Available

  9. Groundbreaking at National Ignition Facility | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Groundbreaking at National Ignition Facility Groundbreaking at National Ignition Facility Livermore, CA Secretary Pena participates in the ground breaking ceremony for the National Ignition Facility, a centerpiece of the stockpile stewardship program, at the Lawrence Livermore National Laboratory

  10. Hanford, WA Selected as Plutonium Production Facility | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Hanford, WA Selected as Plutonium Production Facility Hanford, WA Selected as Plutonium Production Facility Hanford, WA Groves selects Hanford, Washington, as site for full-scale plutonium production and separation facilities. Three reactors--B, D, and F--are built

  11. EM Facilities Startup is Focus of June 8 Event for House Nuclear Cleanup

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

    Caucus | Department of Energy Facilities Startup is Focus of June 8 Event for House Nuclear Cleanup Caucus EM Facilities Startup is Focus of June 8 Event for House Nuclear Cleanup Caucus June 7, 2016 - 4:45pm Addthis WASHINGTON, D.C. - The topic of startup and commissioning of several facilities critical to EM's cleanup progress takes center stage on Wed., June 8 at an event on Capitol Hill for the bipartisan House Nuclear Cleanup Caucus. EM Principal Deputy Assistant Secretary Mark Whitney

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

    SciTech Connect (OSTI)

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

    2009-09-01

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

  13. Facility Operations and User Support | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Facility Operations and User Support This sub-program provides both necessary physical facility and operational support for reliable, cross-lab production computing and storage environments as well as a suite of user services for effective use of ASC tri-lab computing resources. The scope of the facility operations includes planning, integration and deployment, continuing product support, software license and maintenance fees, procurement of operational equipment and

  14. Facility Operations and User Support | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Facility Operations and User Support This sub-program provides both necessary physical ... groups that enable the program to improve its planning and execution of its mission. ...

  15. National Laser Users' Facility Grant Program Awards | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) National Laser Users' Facility Grant Program Awards 2015 Awards 2012 Awards Learn More 2012 NLUF Awards 2015 NLUF Awards

  16. NNSA Holds Groundbreaking at MOX Facility | National Nuclear...

    National Nuclear Security Administration (NNSA)

    NNSA's plutonium disposition program moved another step forward with the start of site preparation for its Mixed Oxide (MOX) Fuel Fabrication Facility at the Savannah River Site. ...

  17. Section E Nuclear Facility D&D, Remainder of Hanford

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

    months Completed annual surveillance of Redox facilities. Completed replacement of PUREX uninterruptible power supply (UPS) battery cell. EMS Objectives and Target Status...

  18. Enterprise Assessments Targeted Review of Nuclear Reactor Facility...

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

    ... Safety and Health, and Emergency Management Assessment ... for resolving facility problems in a timely manner. ... support, oversight planning, and periodic evaluation ...

  19. Nuclear Facilities Subcommittee of NEAC; 5 June 2014

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

    Facilities Subcommittee of NEAC; 5 June 2014 John Sackett, Chair John Ahearne, Denis Beller Dana Christensen, Thomas Cochran Michael Corradini, David Hill Andrew Klein, Paul Murray ...

  20. Nonreactor Nuclear Safety Design Guide for use with DOE O 420.1C, Facility Safety

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

    2012-12-04

    This Guide provides an acceptable approach for safety design of DOE hazard category 1, 2 and 3 nuclear facilities for satisfying the requirements of DOE O 420.1C. Supersedes DOE G 420.1-1.

  1. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  2. Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities

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

    2007-02-07

    This standard provides a framework for generating Criticality Safety Evaluations (CSE) supporting fissionable material operations at Department of Energy (DOE) nonreactor nuclear facilities. This standard imposes no new criticality safety analysis requirements.

  3. Certification of U.S. instrumentation in Russian nuclear processing facilities

    SciTech Connect (OSTI)

    D.H. Powell; J.N. Sumner

    2000-07-12

    Agreements between the United States (U.S.) and the Russian Federation (R.F.) require the down-blending of highly enriched uranium (HEU) from dismantled Russian Federation nuclear weapons. The Blend Down Monitoring System (BDMS) was jointly developed by the Los Alamos National Laboratory (LANL) and the Oak Ridge National Laboratory (ORNL) to continuously monitor the enrichments and flow rates in the HEU blending operations at the R.F. facilities. A significant requirement of the implementation of the BDMS equipment in R.F. facilities concerned the certification of the BDMS equipment for use in a Russian nuclear facility. This paper discusses the certification of the BDMS for installation in R.F. facilities, and summarizes the lessons learned from the process that can be applied to the installation of other U.S. equipment in Russian nuclear facilities.

  4. Mixed Oxide Fuel Fabrication Facility | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Mixed Oxide Fuel Fabrication Facility Mixed Oxide (MOX) Fuel Fabrication Facility Documents related to the project: Plutonium Disposition Study Options Independent Assessment Phase 1 Report, April 13, 2015 Plutonium Disposition Study Options Independent Assessment Phase 2 Report, August 20, 2015 Final Report of the Plutonium Disposition Red Team, August 13, 2015 Commentary on

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

    SciTech Connect (OSTI)

    Robert Bean; Casey Durst

    2009-10-01

    This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called ‚ÄúSafeguards-by-Design.‚ÄĚ This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, ‚ÄúInternational Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,‚ÄĚ published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a

  6. Energy Department Issues Draft Request For Proposal for Nuclear Regulatory Commission Licensed Facilities Procurement

    Broader source: Energy.gov [DOE]

    Cincinnati ‚Äď The U.S. Department of Energy (DOE) today issued a Draft Request for Proposal (DRFP) for the Nuclear Regulatory Commission (NRC) Licensed Facilities procurement. The NRC Licensed Facilities procurement is one of the four procurements that resulted from the Idaho Site Office of Environmental Management Post FY 2015 Acquisition Planning.

  7. Ab Initio Nuclear Theory | Argonne Leadership Computing Facility

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

    Nuclear Theory Authors: Vary, J.P. The vision of solving the nuclear many-body problem with fundamental interactions tied to QCD appears to approach reality. The goals are to preserve the predictive power of the underlying theory, to test fundamental symmetries with the nucleus as laboratory and to develop new understandings of the full range of complex nuclear phenomena. Recent progress includes the derivation, within chiral perturbation theory (ChPT), of the leading terms of the nucleon

  8. Fire accident analysis modeling in support of non-reactor nuclear facilities at Sandia National Laboratories

    SciTech Connect (OSTI)

    Restrepo, L.F.

    1993-06-01

    The Department of Energy (DOE) requires that fire hazard analyses (FHAs) be conducted for all nuclear and new facilities, with results for the latter incorporated into Title I design. For those facilities requiring safety analysis documentation, the FHA shall be documented in the Safety Analysis Reports (SARs). This paper provides an overview of the methodologies and codes being used to support FHAs at Sandia facilities, with emphasis on SARs.

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

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

    provide a viable shield from gamma rays but fail to insulate neutrons. Poor neutron shielding can lead to disastrous consequences: When neutron-irradiating nuclear materials are...

  10. DOE's Approach to Nuclear Facility Safety Analysis and Management

    Broader source: Energy.gov [DOE]

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

  11. NNSA Issues Amended Record of Decision to Build Nuclear Facility...

    National Nuclear Security Administration (NNSA)

    only support the safety, security, and reliability of existing nuclear weapons but also ... NNSA maintains and enhances the safety, security, reliability, and performance of the U.S. ...

  12. National Laser User Facilities Program | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) National Laser User Facilities Program National Laser Users' Facility Grant Program Overview The Laboratory for Laser Energetics (LLE) at the University of Rochester (UR) was established in 1970 to investigate the interaction of high power lasers with matter. It is home of the Omega Laser Facility that includes OMEGA, a 30 kJ UV 60-beam laser system (at a wavelength of 0.35 mm) and OMEGA EP, a four-beam, high-energy, laser system with up to 26 kJ UV. Two of the OMEGA

  13. Project Title: Nuclear Astrophysics Data from Radioactive Beam Facilities

    SciTech Connect (OSTI)

    Alan A. Chen

    2008-03-27

    The scientific aims of this project have been the evaluation and dissemination of key nuclear reactions in nuclear astrophysics, with a focus on ones to be studied at new radioactive beam facilities worldwide. These aims were maintained during the entire funding period from 2003 - 2006. In the following, a summary of the reactions evaluated during this period is provided. Year 1 (2003-04): {sup 21}Na(p,{gamma}){sup 22}Mg and {sup 18}Ne({alpha},p){sup 21}Na - The importance of the {sup 21}Na(p,{gamma}){sup 22}Mg and the {sup 18}Ne({alpha},p){sup 21}Na reactions in models of exploding stars has been well documented: the first is connected to the production of the radioisotope {sup 22}Na in nova nucleosynthesis, while the second is a key bridge between the Hot-CNO cycles and the rp-process in X-ray bursts. By the end of Summer 2004, our group had updated these reaction rates to include all published data up to September 2004, and cast the reaction rates into standard analytical and tabular formats with the assistance of Oak Ridge National Laboratory's computational infrastructure for reaction rates. Since September 2004, ongoing experiments on these two reactions have been completed, with our group's participation in both: {sup 21}Na(p,{gamma}){sup 22}Mg at the TRIUMF-ISAC laboratory (DRAGON collaboration), and 18Ne({alpha},p){sup 21}Na at Argonne National Laboratory (collaboration with Ernst Rehm, Argonne). The data from the former was subsequently published and included in our evaluation. Publication from the latter still awaits independent confirmation of the experimental results. Year 2 (2004-05): The 25Al(p,{gamma}){sup 26}Si and {sup 13}N(p,{gamma})14O reactions - For Year 2, we worked on evaluations of the {sup 25}Al(p,{gamma}){sup 26}Si and {sup 13}N(p,{gamma}){sup 14}O reactions, in accordance with our proposed deliverables and following similar standard procedures to those used in Year 1. The {sup 25}Al(p,{gamma}){sup 26}Si reaction is a key uncertainty in

  14. DOE Standard 3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis, Roll Out Training

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Safety is performing a series of site visits to provide roll-out training and assistance to Program and Site Offices and their contractors on effective implementation of the new revision to DOE Standard 3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis.

  15. Enterprise Assessments Targeted Review of Nuclear Reactor Facility Operations at Sandia National Laboratories ¬Ö March 2016

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

    Review of Nuclear Reactor Facility Operations at Sandia National Laboratories March 2016 Office of Nuclear Safety and Environmental Assessments Office of Environment, Safety and Health Assessments Office of Enterprise Assessments U.S. Department of Energy i Table of Contents Acronyms ...................................................................................................................................................... ii Executive Summary

  16. Mock Nuclear Processing Facility-Safeguards Training Requirements

    SciTech Connect (OSTI)

    Gibbs, Philip; Hasty, Tim; Johns, Rissell; Baum, Gregory

    2014-08-31

    This document outlines specific training requirements in the topical areas of Material Control and Accounting (MC&A) and Physical Protection(PP) which are to be used as technical input for designing a mock Integrated Security Facility (ISF) at Sandia National Laboratories (SNL). The overall project objective for these requirements is to enhance the ability to deliver training on Material Protection Control and Accounting (MC&A) concepts regarding hazardous material such as irradiated materials with respect to bulk processing facilities.

  17. Study Builds Knowledge of Nuclear Waste Glass, Provides Insight to Facility

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

    Design | Department of Energy Study Builds Knowledge of Nuclear Waste Glass, Provides Insight to Facility Design Study Builds Knowledge of Nuclear Waste Glass, Provides Insight to Facility Design April 14, 2016 - 12:40pm Addthis Simulated low-activity waste is cooled in a prototypic steel container as part of ORP-sponsored testing at a Columbia, Md., facility in September 2003. Simulated low-activity waste is cooled in a prototypic steel container as part of ORP-sponsored testing at a

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

    SciTech Connect (OSTI)

    Richard Metcalf; Robert Bean

    2009-10-01

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

  19. Atmospheric Dispersion and Consequence Analysis at Sandia's TA-V Nuclear Facilities

    Office of Environmental Management (EM)

    Atmospheric Dispersion and Consequence Analysis at Sandia's TA-V Nuclear Facilities Jim Dahl Manager, Nuclear Safety Analysis Sandia National Laboratories Office: 505-284-9067 Email: jjdahl@sandia.gov SAND2012-4478P 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. 2 Dispersion and Consequence Analysis at Sandia's TA-V Topics: * Site

  20. About the Neutron and Nuclear Science Research (WNR) facility...

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

    "white" neutron source (Target 4) with 6 flight paths, three low-energy nuclear science flight paths at the Lujan Center (Target-1), and a proton reaction area (Target-2). ...

  1. Approaches used for Clearance of Lands from Nuclear Facilities...

    Office of Environmental Management (EM)

    ... Project information Contact person SSM: Henrik Efraimsson SSM 2013:14 2013:14 Author: ... 26, 2011. http:www.world-nuclear.orginfoinf85.html. 19 Buildings& Site Release ...

  2. NNSA Breaks Ground on Tritium Facilities at SRS | National Nuclear...

    National Nuclear Security Administration (NNSA)

    and decommissioning of several 1950s era structures. Tritium is a heavy isotope of hydrogen and a key component of nuclear weapons, but it decays radioactively at the rate of...

  3. Application of Engineering and Technical Requirements for DOE Nuclear Facilities Standard Review Plan (SRP)

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Standard Review Plan (SRP), Application of Engineering and Technical Requirements for DOE Nuclear Facilities, was developed by the Chief of Nuclear Safety (CNS)1, Office of the Under Secretary for Nuclear Security, to help strengthen the technical rigor of line management oversight and federal monitoring of DOE nuclear facilities. This SRP (hereafter refers to as the Engineering SRP) provides consistent review guidance to assure that engineering and technical requirements are appropriately applied for the design, operations and disposition2 of DOE nuclear facilities. It is one of a series of three SRPs developed by the CNS. The other two SRPs address: 1) nuclear safety basis program review; and 2) application of requirements of DOE O 413.3B, Program and Project Management for the Acquisition of Capital Assets, and DOE-STD-1189, Integration of Safety into the Design Process, for DOE Critical Decision (CD) review and approval. These SRPs may be revised in the future to reflect changes in the DOE requirements, lessons learned, and experience/insights from nuclear facility design, operations, and disposition.

  4. National Laser Users' Facility Grant Program | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) National Laser Users' Facility Grant Program The Laboratory for Laser Energetics (LLE) at the University of Rochester (UR) was established in 1970 to investigate the interaction of high power lasers with matter. It is home of the Omega Laser Facility that includes OMEGA, a 30 kJ UV 60-beam laser system (at a wavelength of 0.35 mm) and OMEGA EP, a four-beam, high energy, laser system with up to 26 kJ UV. Two of the OMEGA EP beamlines can also be operated as

  5. Destruction of nuclear energy facilities in war: the problem and the implications

    SciTech Connect (OSTI)

    Ramberg, B.

    1980-01-01

    This book examines current practices, policies, and regulations concerning nuclear energy in the light of potential sabotage. Dr. Ramberg explains clearly, for both the lay reader and the technical community, the vulnerabilities of different sorts of nuclear facilities. In a case-by-case analysis of countries using or building nuclear power plants, he outlines the strategic hazards of these facilities. The safety of thousands could depend on such volatile factors as the psychological sensitivity of national leaders and the direction of the wind. A combination of engineering changes, use of alternative forms of energy to limit nuclear proliferation, and changes in international law could lessen these risks. Finally, Dr. Ramberg suggests specific national and international guidelines for monitoring nuclear exports.

  6. The environmental impact assessment process for nuclear facilities: An examination of the Indian experience

    SciTech Connect (OSTI)

    Ramana, M.V.; Rao, Divya Badami

    2010-07-15

    India plans to construct numerous nuclear plants and uranium mines across the country, which could have significant environmental, health, and social impacts. The national Environmental Impact Assessment process is supposed to regulate these impacts. This paper examines how effective this process has been, and the extent to which public inputs have been taken into account. In addition to generic problems associated with the EIA process for all kinds of projects in India, there are concerns that are specific to nuclear facilities. One is that some nuclear facilities are exempt from the environmental clearance process. The second is that data regarding radiation baseline levels and future releases, which is the principle environmental concern with respect to nuclear facilities, is controlled entirely by the nuclear establishment. The third is that members of the nuclear establishment take part in almost every level of the environmental clearance procedure. For these reasons and others, the EIA process with regard to nuclear projects in India is of dubious quality. We make a number of recommendations that could address these lacunae, and more generally the imbalance of power between the nuclear establishment on the one hand, and civil society and the regulatory agencies on the other.

  7. Mixed Oxide (MOX) Fuel Fabrication Facility | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) fieldoffices / Savannah River Field Office Mixed Oxide (MOX) Fuel Fabrication Facility Documents related to the project: Plutonium Disposition Study Options Independent Assessment Phase 1 Report, April 13, 2015 Plutonium Disposition Study Options Independent Assessment Phase 2 Report, August 20, 2015 Final Report of the Plutonium Disposition Red Team, August 13, 2015 Commentary on Report by High Bridge Associates, Inc., Feb. 12, 2016 Related Topics Mixed Oxide Fuel

  8. Guide for the Mitigation of Natural Phenomena Hazards for DOE Nuclear Facilities and NonNuclear Facilities

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

    2000-03-28

    This document provides guidance in implementing the Natural Phenomena Hazard (NPH) mitigation requirements of DOE O 420.1, Facility Safety, Section 4.4, "Natural Phenomena Hazards Mitigation." This Guide does not establish or invoke any new requirements. Any apparent conflicts arising from the NPH guidance would defer to the requirements in DOE O 420.1. No cancellation.

  9. Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices

    SciTech Connect (OSTI)

    1995-12-01

    The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

  10. Improving the regulation of safety at DOE nuclear facilities. Final report

    SciTech Connect (OSTI)

    1995-12-01

    The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by DOE itself. The three major recommendations are: under any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

  11. Dual Axis Radiographic Hydrodynamic Test Facility | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Dual Axis Radiographic Hydrodynamic Test Facility An integral part of the national hydrotest program, the DARHT is the world's most powerful x-ray machine. DARHT consists of two electron accelerators oriented at right angles to one another. Each accelerator creates a powerful electron beam that is focused onto a metal target which converts the kinetic energy of the electron beam into high energy x or gamma-rays. The x-ray dose from one DARHT accelerator is

  12. Preparation of Documented Safety Analysis for Interim Operations at DOE Nuclear Facilities

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

    3011-2016 January 2016 DOE STANDARD PREPARATION OF DOCUMENTED SAFETY ANALYSIS FOR INTERIM OPERATIONS AT DOE NUCLEAR FACILITIES U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-3011-2016 ii FOREWORD 1. This Department of Energy (DOE) Standard (STD) has been approved to be used by DOE, including the National Nuclear Security Administration, and their contractors. 2. Beneficial comments

  13. An Overview of Facilities and Capabilities to Support the Development of Nuclear Thermal Propulsion

    SciTech Connect (OSTI)

    James Werner; Sam Bhattacharyya; Mike Houts

    2011-02-01

    Abstract. The future of American space exploration depends on the ability to rapidly and economically access locations of interest throughout the solar system. There is a large body of work (both in the US and the Former Soviet Union) that show that Nuclear Thermal Propulsion (NTP) is the most technically mature, advanced propulsion system that can enable this rapid and economical access by its ability to provide a step increase above what is a feasible using a traditional chemical rocket system. For an NTP system to be deployed, the earlier measurements and recent predictions of the performance of the fuel and the reactor system need to be confirmed experimentally prior to launch. Major fuel and reactor system issues to be addressed include fuel performance at temperature, hydrogen compatibility, fission product retention, and restart capability. The prime issue to be addressed for reactor system performance testing involves finding an affordable and environmentally acceptable method to test a range of engine sizes using a combination of nuclear and non-nuclear test facilities. This paper provides an assessment of some of the capabilities and facilities that are available or will be needed to develop and test the nuclear fuel, and reactor components. It will also address briefly options to take advantage of the greatly improvement in computation/simulation and materials processing capabilities that would contribute to making the development of an NTP system more affordable. Keywords: Nuclear Thermal Propulsion (NTP), Fuel fabrication, nuclear testing, test facilities.

  14. PACCOM: A nuclear waste packaging facility cost model: Draft technical report

    SciTech Connect (OSTI)

    Dippold, D.G.; Tzemos, S.; Smith, D.J.

    1985-05-01

    PACCOM is a computerized, parametric model used to estimate the capital, operating, and decommissioning costs of a variety of nuclear waste packaging facility configurations. The model is based upon a modular waste packaging facility concept from which functional components of the overall facility have been identified and their design and costs related to various parameters such as waste type, waste throughput, and the number of operational shifts employed. The model may be used to either estimate the cost of a particular waste packaging facility configuration or to explore the cost tradeoff between plant capital and labor. That is, one may use the model to search for the particular facility sizes and associated cost which when coupled with a particular number of shifts, and thus staffing level, leads to the lowest overall total cost. The functional components which the model considers include hot cells and their supporting facilities, transportation, cask handling facilities, transuranic waste handling facilities, and administrative facilities such as warehouses, security buildings, maintenance buildings, etc. The cost of each of these functional components is related either directly or indirectly to the various independent design parameters. Staffing by shift is reported into direct and indirect support labor. These staffing levels are in turn related to the waste type, waste throughput, etc. 2 refs., 11 figs., 3 tabs.

  15. Oxygasoline torch cuts demolition time of nuclear test facility

    SciTech Connect (OSTI)

    Gezelman, J. )

    1993-04-01

    A large pressure vessel, which had been used to test relief valves in nuclear power plants, needed to be demolished once all the tests had been completed. What made this particular project so unusual was the fact that the vessel had 10-in.-thick steel walls and was 30 ft tall. James Gezelman Welding was contracted for the demolition. The main challenge was converting the tank to [number sign]1 scrap steel, which meant no piece could be larger than 5 X 2 ft. Since the tank had 10-in.-thick walls, oxygasoline cutting equipment manufactured by Petrogen Co. was chosen for the job. The reasons for this decision were cost-effectiveness, speed and safety.

  16. Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities

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

    2010-04-21

    The order establishes selection, training, qualification, and certification requirements for contractor personnel who can impact the safety basis through their involvement in the operation, maintenance, and technical support of Hazard Category 1, 2, and 3 nuclear facilities. Admin Chg 1, dated 7-29-13, supersedes DOE O 426.2.

  17. Nuclear Facility Construction- Structural Concrete, May 29, 2009 (HSS CRAD 64-15, Rev. 0)

    Broader source: Energy.gov [DOE]

    This Criteria Review and Approach Document (HSS CRAD 64-15) establishes review criteria and lines of inquiry used by the Office of Independent Oversight's Office of Environment, Safety and Health Evaluations to assess the quality of the manufacturing and placement of concrete used in nuclear facility construction at the Department of Energy

  18. Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities

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

    2010-04-21

    The order establishes selection, training, qualification, and certification requirements for contractor personnel who can impact the safety basis through their involvement in the operation, maintenance, and technical support of Hazard Category 1, 2, and 3 nuclear facilities. Cancels DOE O 5480.20A. Admin Chg 1, dated 7-29-13.

  19. Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

    SciTech Connect (OSTI)

    Not Available

    1984-01-01

    This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces.

  20. Investigation of injury/illness data at a nuclear facility. Part II

    SciTech Connect (OSTI)

    Cournoyer, Michael E.; Garcia, Vincent E.; Sandoval, Arnold N.; George, Gerald L.; Gubernatis, David C.; Schreiber, Stephen B.

    2015-07-01

    At Los Alamos National Laboratory (LANL), there are several nuclear facilities, accelerator facilities, radiological facilities, explosives sites, moderate- and high-hazard non-nuclear facilities, biosciences laboratory, etc. The Plutonium Science and Manufacturing Directorate (ADPSM) provides special nuclear material research, process development, technology demonstration, and manufacturing capabilities. ADPSM manages the LANL Plutonium Facility. Within the Radiological Control Area at TA-55 (PF-4), chemical and metallurgical operations with plutonium and other hazardous materials are performed. LANL Health and Safety Programs investigate injury and illness data. In this study, statistically significant trends have been identified and compared for LANL, ADPSM, and PF-4 injury/illness cases. A previously described output metric is used to measures LANL management progress towards meeting its operational safety objectives and goals. Timelines are used to determine trends in Injury/Illness types. Pareto Charts are used to prioritize causal factors. The data generated from analysis of Injury/Illness data have helped identify and reduce the number of corresponding causal factors.

  1. Investigation of injury/illness data at a nuclear facility. Part II

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

    Cournoyer, Michael E.; Garcia, Vincent E.; Sandoval, Arnold N.; George, Gerald L.; Gubernatis, David C.; Schreiber, Stephen B.

    2015-07-01

    At Los Alamos National Laboratory (LANL), there are several nuclear facilities, accelerator facilities, radiological facilities, explosives sites, moderate- and high-hazard non-nuclear facilities, biosciences laboratory, etc. The Plutonium Science and Manufacturing Directorate (ADPSM) provides special nuclear material research, process development, technology demonstration, and manufacturing capabilities. ADPSM manages the LANL Plutonium Facility. Within the Radiological Control Area at TA-55 (PF-4), chemical and metallurgical operations with plutonium and other hazardous materials are performed. LANL Health and Safety Programs investigate injury and illness data. In this study, statistically significant trends have been identified and compared for LANL, ADPSM, and PF-4 injury/illness cases. A previouslymore¬†¬Ľ described output metric is used to measures LANL management progress towards meeting its operational safety objectives and goals. Timelines are used to determine trends in Injury/Illness types. Pareto Charts are used to prioritize causal factors. The data generated from analysis of Injury/Illness data have helped identify and reduce the number of corresponding causal factors.¬ę¬†less

  2. Management concepts and safety applications for nuclear fuel facilities

    SciTech Connect (OSTI)

    Eisner, H.; Scotti, R.S.; Delicate, W.S.

    1995-05-01

    This report presents an overview of effectiveness of management control of safety. It reviews several modern management control theories as well as the general functions of management and relates them to safety issues at the corporate and at the process safety management (PSM) program level. Following these discussions, structured technique for assessing management of the safety function is suggested. Seven modern management control theories are summarized, including business process reengineering, the learning organization, capability maturity, total quality management, quality assurance and control, reliability centered maintenance, and industrial process safety. Each of these theories is examined for-its principal characteristics and implications for safety management. The five general management functions of planning, organizing, directing, monitoring, and integrating, which together provide control over all company operations, are discussed. Under the broad categories of Safety Culture, Leadership and Commitment, and Operating Excellence, key corporate safety elements and their subelements are examined. The three categories under which PSM program-level safety issues are described are Technology, Personnel, and Facilities.

  3. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    SciTech Connect (OSTI)

    Michael Kruzic

    2007-09-01

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

  4. DECOMMISSIONING OF THE NUCLEAR FACILITIES OF VKTA AT THE ROSSENDORF RESEARCH SITE

    SciTech Connect (OSTI)

    U. Helwig, W. Boessert

    2003-02-27

    VKTA decommissioned the old nuclear facilities of former GDR's (German Democratic Republic) Central Institute of Nuclear Research which was closed end of 1991. VKTA is responsible for fissile material and waste management, environmental and radiation protection and runs an accredited laboratory for environmental and radionuclide analytics. The Rossendorf research site is located east of the city of Dresden. The period from 1982 to about 1997 was mainly characterized by obtaining the necessary licenses for decommissioning and developing a new infrastructure (i.e. waste treatment facility, interim storages for fissile material and waste, clearance monitoring facility). The decommissioning work has been in progress since that time. The decommissioning projects are concentrated on three complexes: (1) the reactors and a fuel development and testing facility, (2) the radioisotope production facilities, and (3) the former liquid and solid waste storage facilities. The status of decommissioning progress and treatment of the residues will be demonstrated. Finally an outlook will be given on the future tasks of VKTA based on the ''Conception VKTA 2000 plus'', which was confirmed by the Saxonian government last year.

  5. Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility

    SciTech Connect (OSTI)

    Dippre, M. A.

    2003-02-25

    A spent nuclear fuels (SNF) repackaging and storage facility was designed for the Idaho National Engineering and Environmental Laboratory (INEEL), with nuclear solid waste processing capability. Nuclear solid waste included contaminated or potentially contaminated spent fuel containers, associated hardware, machinery parts, light bulbs, tools, PPE, rags, swabs, tarps, weld rod, and HEPA filters. Design of the nuclear solid waste processing facilities included consideration of contractual, regulatory, ALARA (as low as reasonably achievable) exposure, economic, logistical, and space availability requirements. The design also included non-attended transfer methods between the fuel packaging area (FPA) (hot cell) and the waste processing area. A monitoring system was designed for use within the FPA of the facility, to pre-screen the most potentially contaminated fuel canister waste materials, according to contact- or non-contact-handled capability. Fuel canister waste materials which are not able to be contact-handled after attempted decontamination will be processed remotely and packaged within the FPA. Noncontact- handled materials processing includes size-reduction, as required to fit into INEEL permitted containers which will provide sufficient additional shielding to allow contact handling within the waste areas of the facility. The current design, which satisfied all of the requirements, employs mostly simple equipment and requires minimal use of customized components. The waste processing operation also minimizes operator exposure and operator attendance for equipment maintenance. Recently, discussions with the INEEL indicate that large canister waste materials can possibly be shipped to the burial facility without size-reduction. New waste containers would have to be designed to meet the drop tests required for transportation packages. The SNF waste processing facilities could then be highly simplified, resulting in capital equipment cost savings, operational

  6. Earth covered in-the-ground nuclear reactor facility

    SciTech Connect (OSTI)

    Altes, J.; Escherich, K.; Kasper, K.; Kroger, W.; Schwarzer, K.

    1981-01-13

    A clay layer of low permeability and of a thickness of about 2 meters, depending somewhat upon the permeability, immediately covers and laterally surrounds the external concrete wall and roof structure of the nuclear reactor building, this layer extending at least down to a ground water draining or leading ground layer. Above it is a layer of gravel, sand or porous stone of relatively high permeability, typically somewhat less than a meter thick, and on top thereof an earth fill layer of less permeability than the intermediate layer is provided, which is typically 8 meters thick. The clay layer, which could also be a loam layer, prevents the emergence of radioactive materials in the event of cracking of the concrete structure by an accidental malfunction and absorbs aerosols and water-soluble fission products. The gravel layer converts the convective mass flow of the emerging materials into a diffusion flow and prevents the spreading of cracks in the covering layers. In the thick earth fill layer on top, any radioactive materials still spreading are transported only by a process of diffusion. If protection is to be provided against the strongest external effects, a concrete paving can be put on top of the earth fill.

  7. Analysis and consequences of fire inside the ventilation ducts of a nuclear facility

    SciTech Connect (OSTI)

    Briand, A.R.; Laborde, J.C. ); Savornin, J.H.; Tessier, J.L. )

    1989-01-01

    Accident events involving fire are rather frequent and could have a severe effect on the safety of nuclear facilities. Among the fires that have broken out in nuclear plants, several have resulted from ignition of dust deposited inside the ventilation ducts and on the high-efficiency particulate air (HEPA) filters. The BEATRICE test facility has been designed and built at a French nuclear studies center to enable the analysis and consequences of these types of fires to be evaluated. The associated experimental program is aimed at characterizing the fire (fire spread, aerosols formed), determining and simulating the temperature profiles along the duct (thermal losses evaluation by the pipette code), and evaluating the challenge and behavior of the associated HEPA filters (efficiency, contamination release, etc.). The tests performed in this study contributed to improvements in the basic knowledge about fires inside ventilation ducts and define the associated strategies (ventilation control, filters protection, etc.).

  8. ADDRESSING POLLUTION PREVENTION ISSUES IN THE DESIGN OF A NEW NUCLEAR RESEARCH FACILITY

    SciTech Connect (OSTI)

    Cournoyer, Michael E.; Corpion, Juan; Nelson, Timothy O.

    2003-02-27

    The Chemistry and Metallurgical Research (CMR) Facility was designed in 1949 and built in 1952 at Los Alamos National Laboratory (LANL) to support analytical chemistry, metallurgical studies, and actinide research and development on samples of plutonium and other nuclear materials for the Atomic Energy Commission's nuclear weapons program. These primary programmatic uses of the CMR Facility have not changed significantly since it was constructed. In 1998, a seismic fault was found to the west of the CMR Facility and projected to extend beneath two wings of the building. As part of the overall Risk Management Strategy for the CMR Facility, the Department of Energy (DOE) proposed to replace it by 2010 with what is called the CMR Facility Replacement (CMRR). In an effort to make this proposed new nuclear research facility environmentally sustainable, several pollution prevention/waste minimization initiatives are being reviewed for potential incorporation during the design phase. A two-phase approach is being adopted; the facility is being designed in a manner that integrates pollution prevention efforts, and programmatic activities are being tailored to minimize waste. Processes and procedures that reduce waste generation compared to current, prevalent processes and procedures are identified. Some of these ''best practices'' include the following: (1) recycling opportunities for spent materials; (2) replacing lithium batteries with alternate current adaptors; (3) using launderable contamination barriers in Radiological Control Areas (RCAs); (4) substituting mercury thermometers and manometers in RCAs with mercury-free devices; (5) puncturing and recycling aerosol cans; (6) using non-hazardous low-mercury fluorescent bulbs where available; (7) characterizing low-level waste as it is being generated; and (8) utilizing lead alternatives for radiological shielding. Each of these pollution prevention initiatives are being assessed for their technical validity, relevancy

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

    SciTech Connect (OSTI)

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

    2011-07-01

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

  10. Technical Aspects Regarding the Management of Radioactive Waste from Decommissioning of Nuclear Facilities

    SciTech Connect (OSTI)

    Dragolici, F.; Turcanu, C. N.; Rotarescu, G.; Paunica, I.

    2003-02-25

    The proper application of the nuclear techniques and technologies in Romania started in 1957, once with the commissioning of the Research Reactor VVR-S from IFIN-HH-Magurele. During the last 45 years, appear thousands of nuclear application units with extremely diverse profiles (research, biology, medicine, education, agriculture, transport, all types of industry) which used different nuclear facilities containing radioactive sources and generating a great variety of radioactive waste during the decommissioning after the operation lifetime is accomplished. A new aspect appears by the planning of VVR-S Research Reactor decommissioning which will be a new source of radioactive waste generated by decontamination, disassembling and demolition activities. By construction and exploitation of the Radioactive Waste Treatment Plant (STDR)--Magurele and the National Repository for Low and Intermediate Radioactive Waste (DNDR)--Baita, Bihor county, in Romania was solved the management of radioactive wastes arising from operation and decommissioning of small nuclear facilities, being assured the protection of the people and environment. The present paper makes a review of the present technical status of the Romanian waste management facilities, especially raising on treatment capabilities of ''problem'' wastes such as Ra-266, Pu-238, Am-241 Co-60, Co-57, Sr-90, Cs-137 sealed sources from industrial, research and medical applications. Also, contain a preliminary estimation of quantities and types of wastes, which would result during the decommissioning project of the VVR-S Research Reactor from IFIN-HH giving attention to some special category of wastes like aluminum, graphite and equipment, components and structures that became radioactive through neutron activation. After analyzing the technical and scientific potential of STDR and DNDR to handle big amounts of wastes resulting from the decommissioning of VVR-S Research Reactor and small nuclear facilities, the necessity of

  11. COMPLETION OF THE FIRST INTEGRATED SPENT NUCLEAR FUEL TRANSSHIPMENT/INTERIM STORAGE FACILITY IN NW RUSSIA

    SciTech Connect (OSTI)

    Dyer, R.S.; Barnes, E.; Snipes, R.L.; Hoeibraaten, S.; Gran, H.C.; Foshaug, E.; Godunov, V.

    2003-02-27

    Northwest and Far East Russia contain large quantities of unsecured spent nuclear fuel (SNF) from decommissioned submarines that potentially threaten the fragile environments of the surrounding Arctic and North Pacific regions. The majority of the SNF from the Russian Navy, including that from decommissioned nuclear submarines, is currently stored in on-shore and floating storage facilities. Some of the SNF is damaged and stored in an unstable condition. Existing Russian transport infrastructure and reprocessing facilities cannot meet the requirements for moving and reprocessing this amount of fuel. Additional interim storage capacity is required. Most of the existing storage facilities being used in Northwest Russia do not meet health and safety, and physical security requirements. The United States and Norway are currently providing assistance to the Russian Federation (RF) in developing systems for managing these wastes. If these wastes are not properly managed, they could release significant concentrations of radioactivity to these sensitive environments and could become serious global environmental and physical security issues. There are currently three closely-linked trilateral cooperative projects: development of a prototype dual-purpose transport and storage cask for SNF, a cask transshipment interim storage facility, and a fuel drying and cask de-watering system. The prototype cask has been fabricated, successfully tested, and certified. Serial production is now underway in Russia. In addition, the U.S. and Russia are working together to improve the management strategy for nuclear submarine reactor compartments after SNF removal.

  12. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron Activated Shield Wall

    SciTech Connect (OSTI)

    Michael R. Kruzic

    2007-09-16

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D&D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D&D strategy is now being employed on the larger ''sister'' facility, Test Cell C.

  13. A HYDROGEN IGNITION MECHANISM FOR EXPLOSIONS IN NUCLEAR FACILITY PIPING SYSTEMS

    SciTech Connect (OSTI)

    Leishear, R.

    2013-03-28

    Hydrogen explosions may occur simultaneously with water hammer accidents in nuclear facilities, and a theoretical mechanism to relate water hammer to hydrogen deflagrations and explosions is presented herein. Hydrogen and oxygen generation due to the radiolysis of water is a recognized hazard in pipe systems used in the nuclear industry, where the accumulation of hydrogen and oxygen at high points in the pipe system is expected, and explosive conditions may occur. Pipe ruptures in nuclear reactor cooling systems were attributed to hydrogen explosions inside pipelines, i.e., Hamaoka, Nuclear Power Station in Japan, and Brunsbuettel in Germany. Prior to these accidents, an ignition source for hydrogen was not clearly demonstrated, but these accidents demonstrated that a mechanism was, in fact, available to initiate combustion and explosion. A new theory to identify an ignition source and explosion cause is presented here, and further research is recommended to fully understand this explosion mechanism.

  14. Facilities

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

    Secure and Sustainable Energy Future Mission/Facilities Facilities Tara Camacho-Lopez 2016-04-06T18:06:13+00:00 National Solar Thermal Test Facility (NSTTF) facility_nsttf_slide NSTTF's primary goal is to provide experimental engineering data for the design, construction, and operation of unique components and systems in proposed solar thermal electrical plants, which have three generic system architectures: line-focus (trough and continuous linear Fresnel reflector systems), point-focus central

  15. A systematic method for identifying vital areas at complex nuclear facilities.

    SciTech Connect (OSTI)

    Beck, David Franklin; Hockert, John

    2005-05-01

    Identifying the areas to be protected is an important part of the development of measures for physical protection against sabotage at complex nuclear facilities. In June 1999, the International Atomic Energy Agency published INFCIRC/225/Rev.4, 'The Physical Protection of Nuclear Material and Nuclear Facilities.' This guidance recommends that 'Safety specialists, in close cooperation with physical protection specialists, should evaluate the consequences of malevolent acts, considered in the context of the State's design basis threat, to identify nuclear material, or the minimum complement of equipment, systems or devices to be protected against sabotage.' This report presents a structured, transparent approach for identifying the areas that contain this minimum complement of equipment, systems, and devices to be protected against sabotage that is applicable to complex nuclear facilities. The method builds upon safety analyses to develop sabotage fault trees that reflect sabotage scenarios that could cause unacceptable radiological consequences. The sabotage actions represented in the fault trees are linked to the areas from which they can be accomplished. The fault tree is then transformed (by negation) into its dual, the protection location tree, which reflects the sabotage actions that must be prevented in order to prevent unacceptable radiological consequences. The minimum path sets of this fault tree dual yield, through the area linkage, sets of areas, each of which contains nuclear material, or a minimum complement of equipment, systems or devices that, if protected, will prevent sabotage. This method also provides guidance for the selection of the minimum path set that permits optimization of the trade-offs among physical protection effectiveness, safety impact, cost and operational impact.

  16. Safeguards Guidance for Designers of Commercial Nuclear Facilities ‚Äď International Safeguards Requirements for Uranium Enrichment Plants

    SciTech Connect (OSTI)

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

    2010-04-01

    For the past two years, the United States National Nuclear Security Administration, Office of International Regimes and Agreements (NA-243), has sponsored the Safeguards-by-Design Project, through which it is hoped new nuclear facilities will be designed and constructed worldwide more amenable to nuclear safeguards. In the course of this project it was recognized that commercial designer/builders of nuclear facilities are not always aware of, or understand, the relevant domestic and international safeguards requirements, especially the latter as implemented by the International Atomic Energy Agency (IAEA). To help commercial designer/builders better understand these requirements, a report was prepared by the Safeguards-by-Design Project Team that articulated and interpreted the international nuclear safeguards requirements for the initial case of uranium enrichment plants. The following paper summarizes the subject report, the specific requirements, where they originate, and the implications for design and construction. It also briefly summarizes the established best design and operating practices that designer/builder/operators have implemented for currently meeting these requirements. In preparing the subject report, it is recognized that the best practices are continually evolving as the designer/builder/operators and IAEA consider even more effective and efficient means for meeting the safeguards requirements and objectives.

  17. Nuclear facility licensing, documentaion, and reviews, and the SP-100 test site experience

    SciTech Connect (OSTI)

    Cornwell, B.C.; Deobald, T.L.; Bitten, E.J.

    1991-06-01

    The required approvals and permits to test a nuclear facility are extensive. Numerous regulatory requirements result in the preparation of documentation to support the approval process. The principal regulations for the SP-100 Ground Engineering System (GES) include the National Environmental Policy Act, Clean Air Act, and Atomic Energy Act. The documentation prepared for the SP-100 Nuclear Assembly Test (NAT) included an Environmental Assessment, state permit applications, and Safety Analysis Reports. This paper discusses the regulation documentation requirements and the SP-100 NAT Test Site experience. 12 refs., 2 figs., 2 tabs.

  18. Enterprise Assessments Lessons Learned from Targeted Reviews of the Management of Safety Systems at U.S. Department of Energy Nuclear Facilities ‚Äď April 2016

    Broader source: Energy.gov [DOE]

    Lessons Learned from Targeted Reviews of the Management of Safety Systems at U.S. Department of Energy Nuclear Facilities

  19. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    SciTech Connect (OSTI)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-03-13

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  20. Automatic Estimation of the Radiological Inventory for the Dismantling of Nuclear Facilities

    SciTech Connect (OSTI)

    Garcia-Bermejo, R.; Felipe, A.; Gutierrez, S.; Salas, E.; Martin, N.

    2008-01-15

    The estimation of the radiological inventory of Nuclear Facilities to be dismantled is a process that included information related with the physical inventory of all the plant and radiological survey. Estimation of the radiological inventory for all the components and civil structure of the plant could be obtained with mathematical models with statistical approach. A computer application has been developed in order to obtain the radiological inventory in an automatic way. Results: A computer application that is able to estimate the radiological inventory from the radiological measurements or the characterization program has been developed. In this computer applications has been included the statistical functions needed for the estimation of the central tendency and variability, e.g. mean, median, variance, confidence intervals, variance coefficients, etc. This computer application is a necessary tool in order to be able to estimate the radiological inventory of a nuclear facility and it is a powerful tool for decision taken in future sampling surveys.

  1. Descriptions of selected accidents that have occurred at nuclear reactor facilities

    SciTech Connect (OSTI)

    Bertini, H.W.

    1980-04-01

    This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

  2. Review and Approval of Nuclear Facility Safety Basis Documents (Documented Safety Analyses and Technical Safety Requirements)

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

    DOE-STD-1104-96 November 2005 CHANGE NOTICE NO. 3 Date December 2005 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS DOCUMENTS (DOCUMENTED SAFETY ANALYSES AND TECHNICAL SAFETY REQUIREMENTS) U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information

  3. MORTALITY AMONG WORKERS AT THE SAVANNAH RIVER NUCLEAR FUELS PRODUCTION FACILITY

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

    MORTALITY AMONG WORKERS AT THE SAVANNAH RIVER NUCLEAR FUELS PRODUCTION FACILITY Donna L. Cragle and Janice P. Watkins, Center for Epidemiologic Research; Kathryn Robertson-DeMers, Bechtel Hanford, Inc. Donna Cragle, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 Key Words: mortality study, radiation exposure, leukemia, occupational cohort, trend test INTRODUCTION Since 1952 the Savannah River Site (SRS), located in Aiken, South Carolina, has operated as a Department of

  4. Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Nonreactor Nuclear Facilities

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

    STD-3007-2007 February 2007 DOE STANDARD GUIDELINES FOR PREPARING CRITICALITY SAFETY EVALUATIONS AT DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge,

  5. The universe in the laboratory - Nuclear astrophysics opportunity at the facility for antiproton and ion research

    SciTech Connect (OSTI)

    Langanke, K. [GSI Helmholtzzentrum fŁr Schwerionenforschung, Technische Universitšt Darmstadt, Frankfurt Institute of Advanced Studies, D-64291 Darmstadt (Germany)

    2014-05-09

    In the next years the Facility for Antiproton and Ion Research FAIR will be constructed at the GSI Helmholtzze-ntrum fŁr Schwerionenforschung in Darmstadt, Germany. This new accelerator complex will allow for unprecedented and pathbreaking research in hadronic, nuclear, and atomic physics as well as in applied sciences. This manuscript will discuss some of these research opportunities, with a focus on supernova dynamics and nucleosynthesis.

  6. Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data

    SciTech Connect (OSTI)

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information.

  7. Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information

    SciTech Connect (OSTI)

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses.

  8. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    SciTech Connect (OSTI)

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  9. DOE Order Self Study Modules - DOE O 433.1B, Maintenance Management Program for DOE Nuclear Facilities

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

    433.1B MAINTENANCE MANAGEMENT PROGRAM FOR DOE NUCLEAR FACILITIES DOE O 433.1B Familiar Level August 2011 1 DOE O 433.1B MAINTENANCE MANAGEMENT PROGRAM FOR DOE NUCLEAR FACILITIES FAMILIAR LEVEL OBJECTIVES Given the familiar level of this module and the resources, you will be able to answer the following questions: 1. What is the objective of DOE O 433.1B, Maintenance Management Program for DOE Nuclear Facilities? 2. What is the purpose for quantitative indicators in maintenance management? 3.

  10. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

    SciTech Connect (OSTI)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1987-09-01

    The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.

  11. Nuclear facility decommissioning and site remedial actions. Volume 1. A selected bibliography

    SciTech Connect (OSTI)

    Faust, R.A.; Fore, C.S.; Knox, N.P.

    1980-09-01

    This bibliography of 633 references represents the first in a series to be produced by the Remedial Actions Program Information Center (RAPIC) containing scientific, technical, economic, and regulatory information concerning the decommissioning of nuclear facilities. Major chapters selected for this bibliography are Facility Decommissioning, Uranium Mill Tailings Cleanup, Contaminated Site Restoration, and Criteria and Standards. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for (1) author(s), (2) keywords, (3) title, (4) technology development, and (5) publication description. An appendix of 123 entries lists recently acquired references relevant to decommissioning of nuclear facilities. These references are also arranged according to one of the four subject categories and followed by author, title, and publication description indexes. The bibliography was compiled from a specialized data base established and maintained by RAPIC to provide information support for the Department of Energy's Remedial Actions Program, under the cosponsorship of its three major components: Surplus Facilities Management Program, Uranium Mill Tailings Remedial Actions Program, and Formerly Utilized Sites Remedial Actions Program. RAPIC is part of the Ecological Sciences Information Center within the Information Center Complex at Oak Ridge National Laboratory.

  12. Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

    SciTech Connect (OSTI)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1985-09-01

    This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

  13. Advanced Non-Destructive Assay Systems and Special Instrumentation Requirements for Spent Nuclear Fuel Recycling Facilities

    SciTech Connect (OSTI)

    Simpson, A.P.; Clapham, M.J.; Swinson, B.

    2008-07-01

    The safe and efficient operation of the next generation of Spent Nuclear Fuel (SNF) recycling / reprocessing facilities is dependent upon the availability of high performance real time Non- Destructive Assay (NDA) systems at key in-line points. A diverse variety of such special instrument systems have been developed and commissioned at reprocessing plants worldwide over the past fifty years.. The measurement purpose, technique and plant performance for selected key systems have been reviewed. Obsolescence issues and areas for development are identified in the context of the measurements needs of future recycling facilities and their associated waste treatment plants. Areas of concern include (i) Materials Accountancy and Safeguards, (ii) Head End process control and feed envelope verification, (iii) Real-time monitoring at the Product Finishing Stages, (iv) Criticality safety and (v) Radioactive waste characterization. Common characteristics of the traditional NDA systems in historical recycling facilities are (i) In-house development of bespoke instruments resulting in equipment that if often unique to a given facility and generally not commercially available, (ii) Use of 'novel' techniques - not widely deployed in other applications, (iii) Design features that are tailored to the specific plant requirements of the facility operator, (iv) Systems and software implementation that was not always carried out to modern industry standards and (v) A tendency to be overly complex - refined by on-plant operational usage and experience. Although these systems were 'validated in use' and are generally fit for purpose, there are a number of potential problems in transferring technology that was developed ten or more years ago to the new build SNF recycling facilities of the future. These issues include (i) Obsolescence of components - particularly with respect to computer hardware and data acquisition electronics, (ii) Availability of Intellectual Property and design

  14. A nuclear physics program at the Rare Isotope Beams Accelerator Facility in Korea

    SciTech Connect (OSTI)

    Moon, Chang-Bum

    2014-04-15

    This paper outlines the new physics possibilities that fall within the field of nuclear structure and astrophysics based on experiments with radioactive ion beams at the future Rare Isotope Beams Accelerator facility in Korea. This ambitious multi-beam facility has both an Isotope Separation On Line (ISOL) and fragmentation capability to produce rare isotopes beams (RIBs) and will be capable of producing and accelerating beams of wide range mass of nuclides with energies of a few to hundreds MeV per nucleon. The large dynamic range of reaccelerated RIBs will allow the optimization in each nuclear reaction case with respect to cross section and channel opening. The low energy RIBs around Coulomb barrier offer nuclear reactions such as elastic resonance scatterings, one or two particle transfers, Coulomb multiple-excitations, fusion-evaporations, and direct capture reactions for the study of the very neutron-rich and proton-rich nuclides. In contrast, the high energy RIBs produced by in-flight fragmentation with reaccelerated ions from the ISOL enable to explore the study of neutron drip lines in intermediate mass regions. The proposed studies aim at investigating the exotic nuclei near and beyond the nucleon drip lines, and to explore how nuclear many-body systems change in such extreme regions by addressing the following topics: the evolution of shell structure in areas of extreme proton to neutron imbalance; the study of the weak interaction in exotic decay schemes such as beta-delayed two-neutron or two-proton emission; the change of isospin symmetry in isobaric mirror nuclei at the drip lines; two protons or two neutrons radioactivity beyond the drip lines; the role of the continuum states including resonant states above the particle-decay threshold in exotic nuclei; and the effects of nuclear reaction rates triggered by the unbound proton-rich nuclei on nuclear astrophysical processes.

  15. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    SciTech Connect (OSTI)

    Michael R. Kruzic

    2008-06-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

  16. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  17. Facilities

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

    Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & ... large rotary actuators, which reduces system cost; and common inletsoutlets, to ...

  18. Facilities

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

    Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & ... A view upwind of SWIS' aerosol-generating system. Permalink Gallery Sandia ...

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made.

  20. Design and Integrate Improved Systems for Nuclear Facility Ventilation and Exhaust Operations

    SciTech Connect (OSTI)

    Moore, Murray E.

    2014-04-15

    Objective: The objective of this R&D project would complete the development of three new systems and integrate them into a single experimental effort. However, each of the three systems has stand-alone applicability across the DOE complex. At US DOE nuclear facilities, indoor air is filtered and ventilated for human occupancy, and exhaust air to the outdoor environment must be regulated and monitored. At least three technical standards address these functions, and the Los Alamos National Laboratory would complete an experimental facility to answer at least three questions: (1) Can the drag coefficient of a new Los Alamos air mixer be reduced for better operation in nuclear facility exhaust stacks? (2) Is it possible to verify the accuracy of a new dilution method for HEPA filter test facilities? (3) Is there a performance-based air flow metric (volumetric flow or mass flow) for operating HEPA filters? In summary, the three new systems are: a mixer, a diluter and a performance-based metric, respectively. The results of this project would be applicable to at least four technical standards: ANSI N13.1 Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stacks and Ducts of Nuclear Facilities; ASTM F1471 Standard Test Method for Air Cleaning Performance of a High-Efficiency Particulate Air Filter System, ASME N511: In-Service Testing of Nuclear Air Treatment, Heating, Ventilating, and Air-Conditioning Systems, and ASME AG-1: Code On Nuclear Air And Gas Treatment. All of the three proposed new systems must be combined into a single experimental device (i.e. to develop a new function of the Los Alamos aerosol wind tunnel). Technical Approach: The Radiation Protection RP-SVS group at Los Alamos has an aerosol wind tunnel that was originally (2006) designed to evaluate small air samplers (cf. US EPA 40 CFR 53.42). In 2009, the tunnel was modified for exhaust stack verifications per the ANSI N13.1 standard. In 2010, modifications were started on the

  1. Facilities

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

    Facilities The the WTGa1 turbine (aka DOE/SNL #1) retuns to power as part of a final series of commissioning tests. Permalink Gallery First Power for SWiFT Turbine Achieved during Recommissioning Facilities, News, Renewable Energy, SWIFT, Wind Energy, Wind News First Power for SWiFT Turbine Achieved during Recommissioning The Department of Energy's Scaled Wind Farm Technology (SWiFT) Facility reached an exciting milestone with the return to power production of the WTGa1 turbine (aka DOE/SNL #1)

  2. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

    1984-09-01

    This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

  3. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    SciTech Connect (OSTI)

    Not Available

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  4. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    SciTech Connect (OSTI)

    Owen, P. T.; Webb, J. R.; Knox, N. P.; Goins, L. F.; Harrell, R. E.; Mallory, P. K.; Cravens, C. D.

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  5. Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

    SciTech Connect (OSTI)

    Tonnessen, K.; Tewes, H.A.

    1982-08-01

    The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

  6. Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation

    SciTech Connect (OSTI)

    West, K.A.

    1988-11-01

    The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs.

  7. Maximum Reasonable Radioxenon Releases from Medical Isotope Production Facilities and Their Effect on Monitoring Nuclear Explosions

    SciTech Connect (OSTI)

    Bowyer, Ted W.; Kephart, Rosara F.; Eslinger, Paul W.; Friese, Judah I.; Miley, Harry S.; Saey, Paul R.

    2013-01-01

    Fission gases such as 133Xe are used extensively for monitoring the world for signs of nuclear testing in systems such as the International Monitoring System (IMS). These gases are also produced by nuclear reactors and by fission production of 99Mo for medical use. Recently, medical isotope production facilities have been identified as the major contributor to the background of radioactive xenon isotopes (radioxenon) in the atmosphere (Saey, et al., 2009). These releases pose a potential future problem for monitoring nuclear explosions if not addressed. As a starting point, a maximum acceptable daily xenon emission rate was calculated, that is both scientifically defendable as not adversely affecting the IMS, but also consistent with what is possible to achieve in an operational environment. This study concludes that an emission of 5√ó109 Bq/day from a medical isotope production facility would be both an acceptable upper limit from the perspective of minimal impact to monitoring stations, but also appears to be an achievable limit for large isotope producers.

  8. Feasibility study for Zaporozhye Nuclear Power Plant spent fuel dry storage facility in Ukraine. Export trade information

    SciTech Connect (OSTI)

    1995-12-01

    This document reports the results of a Feasibility Study sponsored by a TDA grant to Zaporozhye Nuclear Power Plant (ZNPP) in Ukraine to study the construction of storage facilities for spent nuclear fuel. It provides pertinent information to U.S. companies interested in marketing spent fuel storage technology and related business to countries of the former Soviet Union or Eastern Europe.

  9. Low Prevalence of Chronic Beryllium Disease among Workers at a Nuclear Weapons Research and Development Facility

    SciTech Connect (OSTI)

    Arjomandi, M; Seward, J P; Gotway, M B; Nishimura, S; Fulton, G P; Thundiyil, J; King, T E; Harber, P; Balmes, J R

    2010-01-11

    To study the prevalence of beryllium sensitization (BeS) and chronic beryllium disease (CBD) in a cohort of workers from a nuclear weapons research and development facility. We evaluated 50 workers with BeS with medical and occupational histories, physical examination, chest imaging with HRCT (N=49), and pulmonary function testing. Forty of these workers also underwent bronchoscopy for bronchoalveolar lavage (BAL) and transbronchial biopsies. The mean duration of employment at the facility was 18 yrs and the mean latency (from first possible exposure) to time of evaluation was 32 yrs. Five of the workers had CBD at the time of evaluation (based on histology or HRCT); three others had evidence of probable CBD. These workers with BeS, characterized by a long duration of potential Be exposure and a long latency, had a low prevalence of CBD.

  10. Application of the New Decommissioning Regulation to the Nuclear Licensed Facilities (NLF) at Fontenay-aux-Roses's Nuclear Center (CEA)

    SciTech Connect (OSTI)

    Sauret, Josiane; Piketty, Laurence; Jeanjacques, Michel

    2008-01-15

    This abstract describes the application of the new decommissioning regulation on all Nuclear Licensed Facilities (NLF is to say INB in French) at Fontenay-aux-Roses's Center (CEA/FAR). The decommissioning process has been applied in six buildings which are out of the new nuclear perimeter proposed (buildings no 7, no 40, no 94, no 39, no 52/1 and no 32) and three buildings have been reorganized (no 54, no 91 and no 53 instead of no 40 and no 94) in order to increase the space for temporary nuclear waste disposal and to reduce the internal transports of nuclear waste on the site. The advantages are the safety and radioprotection improvements and a lower operating cost. A global safety file was written in 2002 and 2003 and was sent to the French Nuclear Authority on November 2003. The list of documents required is given in the paragraph I of this paper. The main goals were two ministerial decrees (one decree for each NLF) getting the authorization to modify the NLF perimeter and to carry out cleaning and dismantling activities leading to the whole decommissioning of all NLF. Some specific authorizations were necessary to carry out the dismantling program during the decommissioning procedure. They were delivered by the French Nuclear Safety Authority (FNSA) or with limited delegation by the General Executive Director (GED) on the CEA Fontenay-aux-Roses's Center, called internal authorization. Some partial dismantling or decontamination examples are given below: - evaporator for the radioactive liquid waste treatment station (building no 53): FNSA authorization: phase realised in 2002/2003. - disposal tanks for the radioactive liquid waste treatment station (building no 53) FNSA authorization: phase realised in 2004, - incinerator for the radioactive solid waste treatment station (building no 07): FNSA authorization: operation realised in 2004, - research equipments in the building no. 54 and building no. 91: internal authorization ; realised in 2005, - sample

  11. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

    1988-09-01

    The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

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

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

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

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

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

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

  14. Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input

    Office of Environmental Management (EM)

    :14 Report number: 2013:14 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten.se Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries Evaluation for Regulatory Input Robert A. Meck Author: SSM perspektiv SSM har nyligen beslutat om föreskrifter om friklassning av material, loka- ler, byggnader och mark vid verksamhet med joniserande strålning (SSMFS 201 1:2). Föreskrifterna innehåller bland annat krav på att tillståndshavare, vid avveckling av

  15. Public involvement in the regulatory activities regarding nuclear fuel cycle facilities: A case study

    SciTech Connect (OSTI)

    Austin, D.E.

    1995-12-01

    This paper reviews the involvement of a community-based organization in the activities of the Nuclear Regulatory Commission (NRC) regarding a uranium conversion facility that operated near Gore, Oklahoma from 1970 until 1992. Effective participation requires access to decision making. Access is a complex phenomenon that includes: (1) opportunity, both procedural and physical, (2) a common language, and (3) time and resources. The paper describes how both the community organization and the NRC responded to these requirements for access, the strategies that were most effective in securing meaningful public involvement in the decision making, and the impacts of that involvement on the organization.

  16. NGNP Nuclear-Industrial Facility and Design Certification Boundaries White Paper

    SciTech Connect (OSTI)

    Thomas E. Hicks

    2011-07-01

    The Next Generation Nuclear Plant (NGNP) Project was initiated at Idaho National Laboratory by the U.S. Department of Energy pursuant to the 2005 Energy Policy Act and based on research and development activities supported by the Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of the high temperature gas-cooled reactor (HTGR) technology. The HTGR is helium cooled and graphite moderated and can operate at reactor outlet temperatures much higher than those of conventional light water reactor (LWR) technologies. Accordingly, it can be applied in many industrial applications as a substitute for burning fossil fuels, such as natural gas, in addition to producing electricity, which is the principal application of current LWRs. These varied industrial applications may involve a standard HTGR modular design using different Energy Conversion Systems. Additionally, some of these process heat applications will require process heat delivery systems to lie partially outside the HTGR operator’s facility.

  17. Annual Report To Congress. Department of Energy Activities Relating to the Defense Nuclear Facilities Safety Board, Calendar Year 2003

    SciTech Connect (OSTI)

    None, None

    2004-02-28

    The Department of Energy (Department) submits an Annual Report to Congress each year detailing the Departmentís activities relating to the Defense Nuclear Facilities Safety Board (Board), which provides advice and recommendations to the Secretary of Energy (Secretary) regarding public health and safety issues at the Departmentís defense nuclear facilities. In 2003, the Department continued ongoing activities to resolve issues identified by the Board in formal recommendations and correspondence, staff issue reports pertaining to Department facilities, and public meetings and briefings. Additionally, the Department is implementing several key safety initiatives to address and prevent safety issues: safety culture and review of the Columbia accident investigation; risk reduction through stabilization of excess nuclear materials; the Facility Representative Program; independent oversight and performance assurance; the Federal Technical Capability Program (FTCP); executive safety initiatives; and quality assurance activities. The following summarizes the key activities addressed in this Annual Report.

  18. Facility Safety

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

    1996-10-24

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  19. Facility Safety

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

    1995-11-16

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  20. Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research

    SciTech Connect (OSTI)

    John Jackson; Todd Allen; Frances Marshall; Jim Cole

    2013-03-01

    The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue University’s Interaction of Materials

  1. YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

    SciTech Connect (OSTI)

    Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

    2010-04-28

    The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

  2. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  3. The advanced fuel cycle facility (AFCF) role in the global nuclear energy partnership

    SciTech Connect (OSTI)

    Griffith, Andrew

    2007-07-01

    The Global Nuclear Energy Partnership (GNEP), launched in February, 2006, proposes to introduce used nuclear fuel recycling in the United States with improved proliferation-resistance and a more effective waste management approach. This program is evaluating ways to close the fuel cycle in a manner that builds on recent laboratory breakthroughs in U.S. national laboratories and draws on international and industry partnerships. Central to moving this advanced fuel recycling technology from the laboratory to commercial implementation is a flexible research, development and demonstration facility, called the Advanced Fuel Cycle Facility (AFCF). The AFCF was introduced as one of three projects under GNEP and will provide the U.S. with the capabilities to evaluate technologies that separate used fuel into reusable material and waste in a proliferation-resistant manner. The separations technology demonstration capability is coupled with a remote transmutation fuel fabrication demonstration capability in an integrated manner that demonstrates advanced safeguard technologies. This paper will discuss the key features of AFCF and its support of the GNEP objectives. (author)

  4. Spent nuclear fuel project, Cold Vacuum Drying Facility human factors engineering (HFE) analysis: Results and findings

    SciTech Connect (OSTI)

    Garvin, L.J.

    1998-07-17

    This report presents the background, methodology, and findings of a human factors engineering (HFE) analysis performed in May, 1998, of the Spent Nuclear Fuels (SNF) Project Cold Vacuum Drying Facility (CVDF), to support its Preliminary Safety Analysis Report (PSAR), in responding to the requirements of Department of Energy (DOE) Order 5480.23 (DOE 1992a) and drafted to DOE-STD-3009-94 format. This HFE analysis focused on general environment, physical and computer workstations, and handling devices involved in or directly supporting the technical operations of the facility. This report makes no attempt to interpret or evaluate the safety significance of the HFE analysis findings. The HFE findings presented in this report, along with the results of the CVDF PSAR Chapter 3, Hazards and Accident Analyses, provide the technical basis for preparing the CVDF PSAR Chapter 13, Human Factors Engineering, including interpretation and disposition of findings. The findings presented in this report allow the PSAR Chapter 13 to fully respond to HFE requirements established in DOE Order 5480.23. DOE 5480.23, Nuclear Safety Analysis Reports, Section 8b(3)(n) and Attachment 1, Section-M, require that HFE be analyzed in the PSAR for the adequacy of the current design and planned construction for internal and external communications, operational aids, instrumentation and controls, environmental factors such as heat, light, and noise and that an assessment of human performance under abnormal and emergency conditions be performed (DOE 1992a).

  5. Progress and Status of the Ignalina Nuclear Power Plant's New Solid Waste Management and Storage Facilities

    SciTech Connect (OSTI)

    Rausch, J.; Henderson, R.W.; Penkov, V.

    2008-07-01

    A considerable amount of dry radioactive waste from former NPP operation has accumulated up to date and is presently stored at the Ignalina NPP site, Lithuania. Current storage capacities are nearly exhausted and more waste is to come from future decommissioning of the two RMBKtype reactors. Additionally, the existing storage facilities does not comply to the state-of-the-art technology for handling and storage of radioactive waste. In 2005, INPP faced this situation of a need for waste processing and subsequent interim storage of these wastes by contracting NUKEM with the design, construction, installation and commissioning of new waste management and storage facilities. The subject of this paper is to describe the scope and the status of the new solid waste management and storage facilities at the Ignalina Nuclear Power Plant. In summary: The turnkey contract for the design, supply and commission of the SWMSF was awarded in December 2005. The realisation of the project was initially planned within 48 month. The basic design was finished in August 2007 and the Technical Design Documentation and Preliminary Safety Analyses Report was provided to Authorities in October 2007. The construction license is expected in July 2008. The procurement phase was started in August 2007, start of onsite activities is expected in November 2007. The start of operation of the SWMSF is scheduled for end of 2009. (authors)

  6. Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

    SciTech Connect (OSTI)

    Cochran, John Russell; Danneels, Jeffrey John

    2009-03-01

    Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21-25, 2008. As noted in the

  7. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

    1983-09-01

    This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation.

  8. Development of an ASTM standard guide on performing vulnerability assessments for nuclear facilities

    SciTech Connect (OSTI)

    Wilkey, D.D.

    1995-09-01

    This paper describes an effort undertaken by subcommittee C26.12 (Safeguards) of the American Society for Testing and Materials (ASTM) to develop a standard guide for performing vulnerability assessments (VAs). VAs are performed to determine the effectiveness of safeguards and security systems for both domestic and international nuclear facilities. These assessments address a range of threats, including theft of nuclear material and sabotage, and use an array of methods. The approach to performing and documenting VAs is varied and is largely dependent upon the tools used to perform them. This diversity can lead to tools being misused, making validation of VAs more difficult. The development of a standard guide for performing VAs would, if generally accepted, alleviate these concerns. ASTM provides a forum for developing guides that includes a high level of peer review to assure that the result is acceptable to all potential users. Additionally, the ASTM is widely recognized for setting standards, and endorsement by the Society may increase the likelihood of acceptance by the nuclear community. The goal of this work is to develop a guide that is independent of the tools being used to perform the VA and applicable to the spectrum of threats described above.

  9. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility

    SciTech Connect (OSTI)

    Ansley, Shannon L.

    2002-02-20

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  11. SOFTWARE TOOLS THAT ADDRESS HAZARDOUS MATERIAL ISSUES DURING NUCLEAR FACILITY D and D

    SciTech Connect (OSTI)

    M. COURNOYER; R. GRUNDEMANN

    2001-03-01

    The 49-year-old Chemistry and Metallurgy Research (CMR) Facility is where analytical chemistry and metallurgical studies on samples of plutonium and nuclear materials are conduct in support of the Department of Energy's nuclear weapons program. The CMR Facility is expected to be decontaminated and decommissioned (D and D) over the next ten to twenty years. Over the decades, several hazardous material issues have developed that need to be address. Unstable chemicals must be properly reassigned or disposed of from the workspace during D and D operation. Materials that have critical effects that are primarily chronic in nature, carcinogens, reproductive toxin, and materials that exhibit high chronic toxicity, have unique decontamination requirements, including the decontrolling of areas where these chemicals were used. Certain types of equipment and materials that contain mercury, asbestos, lead, and polychlorinated biphenyls have special provisions that must be addressed. Utilization of commercially available software programs for addressing hazardous material issues during D and D operations such as legacy chemicals and documentation are presented. These user-friendly programs eliminate part of the tediousness associated with the complex requirements of legacy hazardous materials. A key element of this approach is having a program that inventories and tracks all hazardous materials. Without an inventory of chemicals stored in a particular location, many important questions pertinent to D and D operations can be difficult to answer. On the other hand, a well-managed inventory system can address unstable and highly toxic chemicals and hazardous material records concerns before they become an issue. Tapping into the institutional database provides a way to take advantage of the combined expertise of the institution in managing a cost effective D and D program as well as adding a quality assurance element to the program. Using laboratory requirements as a logic flow

  12. NEW MATERIALS DEVELOPED TO MEET REGULATORY AND TECHNICAL REQUIREMENTS ASSOCIATED WITH IN-SITU DECOMMISSIONING OF NUCLEAR REACTORS AND ASSOCIATED FACILITIES

    SciTech Connect (OSTI)

    Blankenship, J.; Langton, C.; Musall, J.; Griffin, W.

    2012-01-18

    For the 2010 ANS Embedded Topical Meeting on Decommissioning, Decontamination and Reutilization and Technology, Savannah River National Laboratory's Mike Serrato reported initial information on the newly developed specialty grout materials necessary to satisfy all requirements associated with in-situ decommissioning of P-Reactor and R-Reactor at the U.S. Department of Energy's Savannah River Site. Since that report, both projects have been successfully completed and extensive test data on both fresh properties and cured properties has been gathered and analyzed for a total of almost 191,150 m{sup 3} (250,000 yd{sup 3}) of new materials placed. The focus of this paper is to describe the (1) special grout mix for filling the P-Reactor vessel (RV) and (2) the new flowable structural fill materials used to fill the below grade portions of the facilities. With a wealth of data now in hand, this paper also captures the test results and reports on the performance of these new materials. Both reactors were constructed and entered service in the early 1950s, producing weapons grade materials for the nation's defense nuclear program. R-Reactor was shut down in 1964 and the P-Reactor in 1991. In-situ decommissioning (ISD) was selected for both facilities and performed as Comprehensive Environmental Response, Compensations and Liability Act actions (an early action for P-Reactor and a removal action for R-Reactor), beginning in October 2009. The U.S. Department of Energy concept for ISD is to physically stabilize and isolate intact, structurally robust facilities that are no longer needed for their original purpose of producing (reactor facilities), processing (isotope separation facilities), or storing radioactive materials. Funding for accelerated decommissioning was provided under the American Recovery and Reinvestment Act. Decommissioning of both facilities was completed in September 2011. ISD objectives for these CERCLA actions included: (1) Prevent industrial worker

  13. CRAD, New Nuclear Facility Documented Safety Analysis and Technical Safety Requirements- December 2, 2014 (EA CRAD 31-07, Rev. 0)

    Broader source: Energy.gov [DOE]

    New Nuclear Facility Documented Safety Analysis and Technical Safety Requirements Criteria Review and Approach Document (EA CRAD 31-07, Rev. 0)

  14. Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10

    Broader source: Energy.gov [DOE]

    Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is...

  15. Emergency preparedness source term development for the Office of Nuclear Material Safety and Safeguards-Licensed Facilities

    SciTech Connect (OSTI)

    Sutter, S.L.; Mishima, J.; Ballinger, M.Y.; Lindsey, C.G.

    1984-08-01

    In order to establish requirements for emergency preparedness plans at facilities licensed by the Office of Nuclear Materials Safety and Safeguards, the Nuclear Regulatory Commission (NRC) needs to develop source terms (the amount of material made airborne) in accidents. These source terms are used to estimate the potential public doses from the events, which, in turn, will be used to judge whether emergency preparedness plans are needed for a particular type of facility. Pacific Northwest Laboratory is providing the NRC with source terms by developing several accident scenarios for eleven types of fuel cycle and by-product operations. Several scenarios are developed for each operation, leading to the identification of the maximum release considered for emergency preparedness planning (MREPP) scenario. The MREPP scenarios postulated were of three types: fire, tornado, and criticality. Fire was significant at oxide fuel fabrication, UF/sub 6/ production, radiopharmaceutical manufacturing, radiopharmacy, sealed source manufacturing, waste warehousing, and university research and development facilities. Tornadoes were MREPP events for uranium mills and plutonium contaminated facilities, and criticalities were significant at nonoxide fuel fabrication and nuclear research and development facilities. Techniques for adjusting the MREPP release to different facilities are also described.

  16. Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2008

    SciTech Connect (OSTI)

    U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research

    2009-12-01

    This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 2008 annual reports submitted by five of the seven categories1 of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. The annual reports submitted by these licensees consist of radiation exposure records for each monitored individual. These records are analyzed for trends and presented in this report in terms of collective dose and the distribution of dose among the monitored individuals. Because there are no geologic repositories for high-level waste currently licensed and no low-level waste disposal facilities in operation, only five categories will be considered in this report.

  17. Search for rare nuclear decays with HPGe detectors at the STELLA facility of the LNGS

    SciTech Connect (OSTI)

    Belli, P.; Di Marco, A.; Bernabei, R.; D'Angelo, S.; Cappella, F.; D'Angelo, A.; Incicchitti, A.; Cerulli, R.; Di Vacri, M. L.; Laubenstein, M.; Nisi, S.; Danevich, F. A.; Kobychev, V. V.; Poda, D. V.; Tretyak, V. I.; Kovtun, G. P.; Kovtun, N. G.; Shcherban, A. P.; Solopikhin, D. A.; Polischuk, O. G.; and others

    2013-12-30

    Results on the search for rare nuclear decays with the ultra low background facility STELLA at the LNGS using gamma ray spectrometry are presented. In particular, the best T{sub 1/2} limits were obtained for double beta processes in {sup 96}Ru and {sup 104}Ru. Several isotopes, which potentially decay through different 2? channels, including also possible resonant double electron captures, were investigated for the first time ({sup 156}Dy, {sup 158}Dy, {sup 184}Os, {sup 192}Os, {sup 190}Pt, {sup 198}Pt). Search for resonant absorption of solar {sup 7}Li axions in a LiF crystal gave the best limit for the mass of {sup 7}Li axions (< 8.6 keV). Rare alpha decay of {sup 190}Pt to the first excited level of {sup 186}Os(E{sub exc}?=?137.2keV) was observed for the first time.

  18. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

    SciTech Connect (OSTI)

    1997-09-01

    This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. Citations to foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - have been included in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.

  19. American National Standard: design requirements for light water reactor spent fuel storage facilities at nuclear power plants

    SciTech Connect (OSTI)

    Not Available

    1983-10-07

    This standard presents necessary design requirements for facilities at nuclear power plants for the storage and preparation for shipment of spent fuel from light-water moderated and cooled nuclear power stations. It contains requirements for the design of fuel storage pool; fuel storage racks; pool makeup, instrumentation and cleanup systems; pool structure and integrity; radiation shielding; residual heat removal; ventilation, filtration and radiation monitoring systems; shipping cask handling and decontamination; building structure and integrity; and fire protection and communication.

  20. A Proposed Cost-Benefit Analysis Approach for Evaluating DOE Nuclear Facility Design Options

    Broader source: Energy.gov [DOE]

    Presenter: Dr. Kamiar Jamali, Senior Technical Advisor to the Chief of Defense Nuclear Safety, National Nuclear Security Administration, Office of Nuclear Safety NA-SH

  1. Mobile Pit verification system design based on passive special nuclear material verification in weapons storage facilities

    SciTech Connect (OSTI)

    Paul, J. N.; Chin, M. R.; Sjoden, G. E.

    2013-07-01

    A mobile 'drive by' passive radiation detection system to be applied in special nuclear materials (SNM) storage facilities for validation and compliance purposes has been designed through the use of computational modeling and new radiation detection methods. This project was the result of work over a 1 year period to create optimal design specifications to include creation of 3D models using both Monte Carlo and deterministic codes to characterize the gamma and neutron leakage out each surface of SNM-bearing canisters. Results were compared and agreement was demonstrated between both models. Container leakages were then used to determine the expected reaction rates using transport theory in the detectors when placed at varying distances from the can. A 'typical' background signature was incorporated to determine the minimum signatures versus the probability of detection to evaluate moving source protocols with collimation. This established the criteria for verification of source presence and time gating at a given vehicle speed. New methods for the passive detection of SNM were employed and shown to give reliable identification of age and material for highly enriched uranium (HEU) and weapons grade plutonium (WGPu). The finalized 'Mobile Pit Verification System' (MPVS) design demonstrated that a 'drive-by' detection system, collimated and operating at nominally 2 mph, is capable of rapidly verifying each and every weapon pit stored in regularly spaced, shelved storage containers, using completely passive gamma and neutron signatures for HEU and WGPu. This system is ready for real evaluation to demonstrate passive total material accountability in storage facilities. (authors)

  2. Damaged Spent Nuclear Fuel at U.S. DOE Facilities Experience and Lessons Learned

    SciTech Connect (OSTI)

    Brett W. Carlsen; Eric Woolstenhulme; Roger McCormack

    2005-11-01

    From a handling perspective, any spent nuclear fuel (SNF) that has lost its original technical and functional design capabilities with regard to handling and confinement can be considered as damaged. Some SNF was damaged as a result of experimental activities and destructive examinations; incidents during packaging, handling, and transportation; or degradation that has occurred during storage. Some SNF was mechanically destroyed to protect proprietary SNF designs. Examples of damage to the SNF include failed cladding, failed fuel meat, sectioned test specimens, partially reprocessed SNFs, over-heated elements, dismantled assemblies, and assemblies with lifting fixtures removed. In spite of the challenges involved with handling and storage of damaged SNF, the SNF has been safely handled and stored for many years at DOE storage facilities. This report summarizes a variety of challenges encountered at DOE facilities during interim storage and handling operations along with strategies and solutions that are planned or were implemented to ameliorate those challenges. A discussion of proposed paths forward for moving damaged and nondamaged SNF from interim storage to final disposition in the geologic repository is also presented.

  3. Facility Representatives

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

    2011-03-01

    This standard, DOE-STD-1063, Facility Representatives, defines the duties, responsibilities and qualifications for Department of Energy (DOE) Facility Representatives, based on facility hazard classification; risks to workers, the public, and the environment; and the operational activity level. This standard provides the guidance necessary to ensure that DOE’s hazardous nuclear and non-nuclear facilities have sufficient staffing of technically qualified facility representatives (FRs) to provide day-to-day oversight of contractor operations.

  4. Calculation code evaluating the confinement of a nuclear facility in case of fires

    SciTech Connect (OSTI)

    Laborde, J.C.; Prevost, C.; Vendel, J.

    1995-02-01

    Accident events involving fire are quite frequent and could have a severe effect on the safety of nuclear facilities. As confinement must be maintained, the ventilation and filtration systems have to be designed to limit radioactive release to the environment. To determine and analyse the consequences of a fire on the contamination confinement, IPSN, COGEMA and SGN are participating in development of a calculation code based on introduction, in the SIMEVENT ventilation code, of various models associated to fire risk and mass transfer in the ventilation networks. This calculation code results from the coupling of the SIMEVENT code with several models describing the temperature in a room resulting of a fire, the temperatures along the ventilation ducts, the contamination transfers through out the ventilation equipments (ducts, dampers, valves, air cleaning systems) and the High Efficiency Particulate Air (HEPA) filters clogging. The paper proposed presents the current level of progress in development of this calculation code. It describes, in particular, the empirical model used for the clogging of HEPA filters by the aerosols derived from the combustion of standard materials used in the nuclear industry. It describes, also, the specific models used to take into account the mass transfers and resulting from the basic mechanisms of aerosols physics. In addition, an assessment of this code is given using the example of a simple laboratory installation.

  5. Investigation of criticality safety control infraction data at a nuclear facility

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

    Cournoyer, Michael E.; Merhege, James F.; Costa, David A.; Art, Blair M.; Gubernatis, David C.

    2014-10-27

    Chemical and metallurgical operations involving plutonium and other nuclear materials account for most activities performed at the LANL's Plutonium Facility (PF-4). The presence of large quantities of fissile materials in numerous forms at PF-4 makes it necessary to maintain an active criticality safety program. The LANL Nuclear Criticality Safety (NCS) Program provides guidance to enable efficient operations while ensuring prevention of criticality accidents in the handling, storing, processing and transportation of fissionable material at PF-4. In order to achieve and sustain lower criticality safety control infraction (CSCI) rates, PF-4 operations are continuously improved, through the use of Lean Manufacturing andmore¬†¬Ľ Six Sigma (LSS) business practices. Employing LSS, statistically significant variations (trends) can be identified in PF-4 CSCI reports. In this study, trends have been identified in the NCS Program using the NCS Database. An output metric has been developed that measures ADPSM Management progress toward meeting its NCS objectives and goals. Using a Pareto Chart, the primary CSCI attributes have been determined in order of those requiring the most management support. Data generated from analysis of CSCI data help identify and reduce number of corresponding attributes. In-field monitoring of CSCI's contribute to an organization's scientific and technological excellence by providing information that can be used to improve criticality safety operation safety. This increases technical knowledge and augments operational safety.¬ę¬†less

  6. Investigation of criticality safety control infraction data at a nuclear facility

    SciTech Connect (OSTI)

    Cournoyer, Michael E.; Merhege, James F.; Costa, David A.; Art, Blair M.; Gubernatis, David C.

    2014-10-27

    Chemical and metallurgical operations involving plutonium and other nuclear materials account for most activities performed at the LANL's Plutonium Facility (PF-4). The presence of large quantities of fissile materials in numerous forms at PF-4 makes it necessary to maintain an active criticality safety program. The LANL Nuclear Criticality Safety (NCS) Program provides guidance to enable efficient operations while ensuring prevention of criticality accidents in the handling, storing, processing and transportation of fissionable material at PF-4. In order to achieve and sustain lower criticality safety control infraction (CSCI) rates, PF-4 operations are continuously improved, through the use of Lean Manufacturing and Six Sigma (LSS) business practices. Employing LSS, statistically significant variations (trends) can be identified in PF-4 CSCI reports. In this study, trends have been identified in the NCS Program using the NCS Database. An output metric has been developed that measures ADPSM Management progress toward meeting its NCS objectives and goals. Using a Pareto Chart, the primary CSCI attributes have been determined in order of those requiring the most management support. Data generated from analysis of CSCI data help identify and reduce number of corresponding attributes. In-field monitoring of CSCI's contribute to an organization's scientific and technological excellence by providing information that can be used to improve criticality safety operation safety. This increases technical knowledge and augments operational safety.

  7. Thermal nuclear pulse simulation at the National Solar Thermal Test Facility

    SciTech Connect (OSTI)

    Cameron, C.P.; Ralph, M.E. ); Ghanbari, C.M. ); Oeding, R.; Shaw, K. )

    1991-01-01

    The National Solar Thermal Test Facility (NSTTF) at Sandia National Laboratories in Albuquerque, New Mexico is being used to simulate the thermal pulse from a nuclear weapon on relatively large surfaces. Pulses varying in length from 2 seconds to 7 seconds have been produced. The desired pulse length varies as a function of the yield of the weapon being simulated. The present experiment capability can accommodate samples as large as 1.2 {times} 1.5 meters. Samples can be flat or three-dimensional. Samples exposed have ranged from fabrics (protective clothing) to an aircraft canopy and cockpit system, complete with a mannequin in a flight suit and helmet. In addition, a windowed wind tunnel has been constructed which permits exposure of flight surface materials to thermal transients with air speed of Mach 0.8. The wind tunnel can accommodate samples up to .48 {times} .76 meters or an array of smaller samples. The maximum flux capability of the NSTTF is about 70 calories/cm{sup 2}-sec. A black-body temperature of about 6000 K is produced by the solar beam and is therefore ideal for simulating the nuclear source. 3 refs., 7 figs.

  8. CRAD, Engineering- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Engineering Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  9. CRAD, Occupational Safety & Health- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Occupational and Industrial Safety and Hygiene Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  10. CRAD, Maintenance- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Office of Energy Efficiency and Renewable Energy (EERE)

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Maintenance Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  11. CRAD, Environmental Protection- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Environmental Compliance Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  12. CRAD, Quality Assurance- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Quality Assurance Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  13. CRAD, Fire Protection- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Fire Protection Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  14. CRAD, Emergency Management- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Emergency Management Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  15. CRAD, Training- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Office of Energy Efficiency and Renewable Energy (EERE)

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Training Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  16. CRAD, Radiological Controls- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Radiation Protection Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  17. CRAD, DOE Oversight- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Conduct of Operations Program portion of an Operational Readiness Review at the Los Alamos National Laboratory, Waste Characterization, Reduction, and Repackaging Facility.

  18. CRAD, Management- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Management portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  19. CRAD, Conduct of Operations- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    Office of Energy Efficiency and Renewable Energy (EERE)

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Conduct of Operations Program portion of an Operational Readiness Review at the Los Alamos National Laboratory, Waste Characterization, Reduction, and Repackaging Facility.

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

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Safety Basis portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  1. Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 1998

    SciTech Connect (OSTI)

    1999-02-01

    This is the ninth Annual Report to the Congress describing Department of Energy (Department) activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of energy regarding public health and safety issues at the Department`s defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department`s defense nuclear facilities. The locations of the major Department facilities are provided. During 1998, Departmental activities resulted in the proposed closure of one Board recommendation. In addition, the Department has completed all implementation plan milestones associated with four other Board recommendations. Two new Board recommendations were received and accepted by the Department in 1998, and two new implementation plans are being developed to address these recommendations. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, a renewed effort to increase the technical capabilities of the federal workforce, and a revised plan for stabilizing excess nuclear materials to achieve significant risk reduction.

  2. Decommissioning and Dismantling of Liquid Waste Storage and Liquid Waste Treatment Facility from Paldiski Nuclear Site, Estonia

    SciTech Connect (OSTI)

    Varvas, M.; Putnik, H.; Johnsson, B.

    2006-07-01

    The Paldiski Nuclear Facility in Estonia, with two nuclear reactors was owned by the Soviet Navy and was used for training the navy personnel to operate submarine nuclear reactors. After collapse of Soviet Union the Facility was shut down and handed over to the Estonian government in 1995. In co-operation with the Paldiski International Expert Reference Group (PIERG) decommission strategy was worked out and started to implement. Conditioning of solid and liquid operational waste and dismantling of contaminated installations and buildings were among the key issues of the Strategy. Most of the liquid waste volume, remained at the Facility, was processed in the frames of an Estonian-Finnish co-operation project using a mobile wastewater purification unit NURES (IVO International OY) and water was discharged prior to the site take-over. In 1999-2002 ca 120 m{sup 3} of semi-liquid tank sediments (a mixture of ion exchange resins, sand filters, evaporator and flocculation slurry), remained after treatment of liquid waste were solidified in steel containers and stored into interim storage. The project was carried out under the Swedish - Estonian co-operation program on radiation protection and nuclear safety. Contaminated installations in buildings, used for treatment and storage of liquid waste (Liquid Waste Treatment Facility and Liquid Waste Storage) were then dismantled and the buildings demolished in 2001-2004. (authors)

  3. Decommissioning Lines-of-Inquiry for Design Review of New Nuclear Facilities

    SciTech Connect (OSTI)

    Negin, C.A.; Urland, C.S.

    2008-01-15

    An independent review of the design of the Salt Waste Processing Facility (SWPF) at Savannah River included a requirement to address the ability to decommission the facility. This paper addresses the lines of inquiry (that were developed for the review and their use in future for reviews of other projects, referred to herein as 'DDLOI'. Decommissioning activities for almost any type of facility are well within the technological state-of-the-art. The major impacts for complications resulting from insufficient consideration during design of a new facility that involves radioactive processes and/or material is the cost of: a) gaining access to high radiation areas and b) dealing with high levels of contamination. For this reason, the DDLOI were developed as a way of raising the awareness of designers and design reviewers to design features that can impede or facilitate ultimate decommissioning. The intent is that this report can be used not only for review, but also by engineers in the early stages of design development when requirements are being assembled. The focus for the DDLOI is on types of facilities that contain nuclear and/or radioactive processes and materials. The level of detail is more specific than would be found in decommissioning plans prepared for regulatory purposes. In commencing this review, the author's could find no precedent for a systematic review of design for decommissioning that included results of a review. Therefore, it was decided to create a report that would provide detailed lines of inquiry along with the rationale for each. The resulting DDLOI report included 21 topical areas for design review. The DDLOI combined the authors' experience in developing baselines for facilities to be deactivated or demolished with prior publications by the U.S. Army and the International Atomic Energy Agency. These two references were found via an Internet search and were the only ones judged to be useful at a field application level. Most others

  4. 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

    SciTech Connect (OSTI)

    PACKER, M.J.

    1999-11-04

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

  5. An Advanced Reverse Osmosis Technology For Application in Nuclear Desalination Facilities

    SciTech Connect (OSTI)

    Humphries, J.R.; Davies, K.; Ackert, J.A.

    2002-07-01

    The lack of adequate supplies of clean, safe water is a growing global problem that has reached crisis proportions in many parts of the world. It is estimated that 1.5 billion people do not have access to adequate supplies of safe water, and that as a result nearly 10,000 people die every day and thousands more suffer from a range of debilitating illnesses due to water related diseases. Included in this total is an estimated 2.2 million child deaths annually. As the world's need for additional sources of fresh water continues to grow, seawater and brackish water desalination are providing an increasingly important contribution to the solution of this problem. Because desalination is an energy intensive process, nuclear desalination provides an economically attractive and environmentally sound alternative to the burning of fossil fuels for desalination. Nevertheless, the enormity of the problem dictates that additional steps must be taken to improve the efficiency of energy utilization and reduce the cost of water production in order to reduce the financial and environmental burden to communities in need. An advanced reverse osmosis (RO) desalination technology has been developed that emphasizes a nontraditional approach to system design and operation, and makes use of a sophisticated design optimization process that can lead to highly optimized design configurations and operating regimes. The technology can be coupled with a nuclear generating station (NGS) to provide an integrated facility for the co-generation of both water and electricity. Waste heat from the NGS allows the use of 'preheated' feedwater into the RO system, improving the efficiency of the RO process and reducing the cost of water production. Because waste heat, rather than process heat, is used the desalination system can be readily coupled to any existing or advanced reactor technology with little or no impact on reactor design and operation and without introducing additional reactor safety

  6. A historical perspective of remote operations and robotics in nuclear facilities. Robotics and Intelligent Systems Program

    SciTech Connect (OSTI)

    Herndon, J.N.

    1992-12-31

    The field of remote technology is continuing to evolve to support man`s efforts to perform tasks in hostile environments. The technology which we recognize today as remote technology has evolved over the last 45 years to support human operations in hostile environments such as nuclear fission and fusion, space, underwater, hazardous chemical, and hazardous manufacturing. The four major categories of approach to remote technology have been (1) protective clothing and equipment for direct human entry, (2) extended reach tools using distance for safety, (3) telemanipulators with barriers for safety, and (4) teleoperators incorporating mobility with distance and/or barriers for safety. The government and commercial nuclear industry has driven the development of the majority of the actual teleoperator hardware available today. This hardware has been developed largely due to the unsatisfactory performance of the protective-clothing approach in many hostile applications. Manipulation systems which have been developed include crane/impact wrench systems, unilateral power manipulators, mechanical master/slaves, and servomanipulators. Viewing systems have included periscopes, shield windows, and television systems. Experience over the past 45 years indicates that maintenance system flexibility is essential to typical repair tasks because they are usually not repetitive, structured, or planned. Fully remote design (manipulation, task provisions, remote tooling, and facility synergy) is essential to work task efficiency. Work for space applications has been primarily research oriented with relatively few successful space applications, although the shuttle`s remote manipulator system has been quite successful. In the last decade, underwater applications have moved forward significantly, with the offshore oil industry and military applications providing the primary impetus.

  7. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    SciTech Connect (OSTI)

    IRWIN, J.J.

    2000-11-18

    The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces and to allow the MCOs and their SNF payloads to be safely transported to the Hanford Site 200 East Area and stored within the SNF Project Canister Storage Building (CSB). The CVDF is located within a few hundred yards of the basins, southwest of the 165KW Power Control Building and the 105KW Reactor Building. The site area required for the facility and vehicle circulation is approximately 2 acres. Access and egress is provided by the main entrance to the 100K inner area using existing roadways. The CVDF will remove free. water from the MCOs to reduce the potential for continued fuel-water corrosion reactions. The cold vacuum drying process involves the draining of bulk water from the MCO and subsequent vacuum drying. The MCO will be evacuated to a pressure of 8 torr or less and backfilled with an inert gas (helium). The MCO will be sealed, leak tested, and then transported to the CSB within a sealed shipping cask. (The MCO remains within the same shipping Cask from the time it enters the basin to receive its SNF payload until it is removed from the Cask by the CSB MCO handling machine.) The CVDF subproject acquired the required process systems, supporting equipment, and facilities. The cold vacuum drying operations result in an MCO containing dried fuel that is prepared for shipment to the CSB by the Cask transportation system. The CVDF subproject also provides equipment to dispose of solid wastes generated by the cold vacuum drying process and transfer process water removed

  8. Occupational radiation exposure at commercial nuclear power reactors and other facilities 1992; Twenty-fifth annual report, Volume 14

    SciTech Connect (OSTI)

    Raddatz, C.T.; Hagemeyer, D.

    1993-12-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC`s Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1992. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10CFR20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10CFR20.408. The 1992 annual reports submitted by about 364 licensees indicated that approximately 204,365 individuals were monitored, 183,927 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.16 rem (cSv) and an average measurable dose of about 0.30 (cSv). Termination radiation exposure reports were analyzed to reveal that about 74,566 individuals completed their employment with one or more of the 364 covered licensees during 1992. Some 71,846 of these individuals terminated from power reactor facilities, and about 9,724 of them were considered to be transient workers who received an average dose of 0.50 rem (cSv).

  9. TRIGA Mark II nuclear reactor facility. Final report, 1 July 1980--30 June 1995

    SciTech Connect (OSTI)

    Ryan, B.C.

    1997-05-01

    This report is a final culmination of activities funded through the Department of Energy`s (DOE) University Reactor Sharing Program, Grant DE-FG02-80ER10273, during the period 1 July 1980 through 30 June 1995. Progress reports have been periodically issued to the DOE, namely the Reactor Facility Annual Reports C00-2082/2219-7 through C00-2082/10723-21, which are contained as an appendix to this report. Due to the extent of time covered by this grant, summary tables are presented. Table 1 lists the fiscal year financial obligations of the grant. As listed in the original grant proposals, the DOE grant financed 70% of project costs, namely the total amount spent of these projects minus materials costs and technical support. Thus the bulk of funds was spent directly on reactor operations. With the exception of a few years, spending was in excess of the grant amount. As shown in Tables 2 and 3, the Reactor Sharing grant funded a immense number of research projects in nuclear engineering, geology, animal science, chemistry, anthropology, veterinary medicine, and many other fields. A list of these users is provided. Out of the average 3000 visitors per year, some groups participated in classes involving the reactor such as Boy Scout Merit Badge classes, teacher`s workshops, and summer internships. A large number of these projects met the requirements for the Reactor Sharing grant, but were funded by the University instead.

  10. Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, Calendar Year 1999

    SciTech Connect (OSTI)

    2000-02-01

    This is the tenth Annual Report to the Congress describing Department of Energy activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of Energy regarding public health and safety issues at the Department's defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department's defense nuclear facilities. During 1999, Departmental activities resulted in the closure of nine Board recommendations. In addition, the Department has completed all implementation plan milestones associated with three Board recommendations. One new Board recommendation was received and accepted by the Department in 1999, and a new implementation plan is being developed to address this recommendation. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, opening of a repository for long-term storage of transuranic wastes, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

  11. Facility Floorplan

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

    facility floorplan Facility Floorplan

  12. Long-term storage facility for reactor compartments in Sayda Bay - German support for utilization of nuclear submarines in Russia

    SciTech Connect (OSTI)

    Wolff, Dietmar; Voelzke, Holger; Weber, Wolfgang; Noack, Volker; Baeuerle, Guenther

    2007-07-01

    The German-Russian project that is part of the G8 initiative on Global Partnership Against the Spread of Weapons and Materials of Mass Destruction focuses on the speedy construction of a land-based interim storage facility for nuclear submarine reactor compartments at Sayda Bay near Murmansk. This project includes the required infrastructure facilities for long-term storage of about 150 reactor compartments for a period of about 70 years. The interim storage facility is a precondition for effective activities of decommissioning and dismantlement of almost all nuclear-powered submarines of the Russian Northern Fleet. The project also includes the establishment of a computer-assisted waste monitoring system. In addition, the project involves clearing Sayda Bay of other shipwrecks of the Russian navy. On the German side the project is carried out by the Energiewerke Nord GmbH (EWN) on behalf of the Federal Ministry of Economics and Labour (BMWi). On the Russian side the Kurchatov Institute holds the project management of the long-term interim storage facility in Sayda Bay, whilst the Nerpa Shipyard, which is about 25 km away from the storage facility, is dismantling the submarines and preparing the reactor compartments for long-term interim storage. The technical monitoring of the German part of this project, being implemented by BMWi, is the responsibility of the Federal Institute for Materials Research and Testing (BAM). This paper gives an overview of the German-Russian project and a brief description of solutions for nuclear submarine disposal in other countries. At Nerpa shipyard, being refurbished with logistic and technical support from Germany, the reactor compartments are sealed by welding, provided with biological shielding, subjected to surface treatment and conservation measures. Using floating docks, a tugboat tows the reactor compartments from Nerpa shipyard to the interim storage facility at Sayda Bay where they will be left on the on-shore concrete

  13. Nuclear Energy Advisory Committee Facility Subcommittee visit to Oak Ridge National Laboratory

    Broader source: Energy.gov [DOE]

    The NEAC Facilities Subcommittee made a site visit to Oak Ridge National Laboratory (ORNL) on August 26, 2010. Subcommittee members included John Ahearne (Vice Chairman of NEAC and Facilities...

  14. US-Russian Cooperation in Upgrading MC&A System at Rosatom Facilities: Measurement of Nuclear Materials

    SciTech Connect (OSTI)

    Powell, Danny H; Jensen, Bruce A

    2011-01-01

    Improve protection of weapons-usable nuclear material from theft or diversion through the development and support of a nationwide sustainable and effective Material Control and Accountability (MC&A) program based on material measurement. The material protection, control, and accountability (MPC&A) cooperation has yielded significant results in implementing MC&A measurements at Russian nuclear facilities: (1) Establishment of MEM WG and MEMS SP; (2) Infrastructure for development, certification, and distribution of RMs; and (3) Coordination on development and implementation of MMs.

  15. Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility

    SciTech Connect (OSTI)

    SCHULTZ, M.V.

    2000-08-22

    As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to

  16. Uranium Processing Facility Team Signs Partnering Agreement ...

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

    Processing Facility ... Uranium Processing Facility Team Signs Partnering Agreement ... Nuclear Security, LLC; John Eschenberg, Uranium Processing Facility Project Office; Brian ...

  17. 20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.

    SciTech Connect (OSTI)

    Ramirez, Amanda Ann

    2008-09-01

    The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

  18. Technical Approach and Plan for Transitioning Spent Nuclear Fuel (SNF) Project Facilities to the Environmental Restoration Program

    SciTech Connect (OSTI)

    SKELLY, W.A.

    1999-10-06

    This document describes the approach and process in which the 100-K Area Facilities are to be deactivated and transitioned over to the Environmental Restoration Program after spent nuclear fuel has been removed from the K Basins. It describes the Transition Project's scope and objectives, work breakdown structure, activity planning, estimated cost, and schedule. This report will be utilized as a planning document for project management and control and to communicate details of project content and integration.

  19. Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14

    SciTech Connect (OSTI)

    Schneider, K.J.

    1982-09-01

    The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation.

  20. Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2010, Prepared for the Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 2012

    SciTech Connect (OSTI)

    D. E. Lewis D. A. Hagemeyer Y. U. McCormick

    2012-07-07

    This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission’s (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 2010 annual reports submitted by five of the seven categories of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Because there are no geologic repositories for high-level waste currently licensed and no NRC-licensed low-level waste disposal facilities currently in operation, only five categories will be considered in this report. The annual reports submitted by these licensees consist of radiation exposure records for each monitored individual. These records are analyzed for trends and presented in this report in terms of collective dose and the distribution of dose among the monitored individuals. Annual reports for 2010 were received from a total of 190 NRC licensees. The summation of reports submitted by the 190 licensees indicated that 192,424 individuals were monitored, 81,961 of whom received a measurable dose. When adjusted for transient workers who worked at more than one licensee during the year, there were actually 142,471 monitored individuals and 62,782 who received a measurable dose. The collective dose incurred by these individuals was 10,617 person-rem, which represents a 12% decrease from the 2009 value. This decrease was primarily due to the decrease in collective dose at commercial nuclear power reactors, as well as a decrease in the collective dose for most of the other categories of NRC licensees. The number of individuals receiving a measurable dose also decreased, resulting in an average measurable dose of 0.13 rem for 2010. The average measurable dose is defined as the total effective dose equivalent (TEDE) divided by the number of individuals receiving a measurable dose. In calendar year 2010, the average annual collective dose per reactor for light water reactor

  1. Future directions in particle and nuclear physics at multi-GeV hadron beam facilities

    SciTech Connect (OSTI)

    Geesaman, D.F. [Argonne National Lab., IL (United States)] [ed.

    1993-11-01

    This report contains papers on the following topics in particle and nuclear physics: hadron dynamics; lepton physics; spin physics; hadron and nuclear spectroscopy; hadronic weak interactions; and Eta physics. These papers have been indexed separately elsewhere.

  2. Annual report to Congress. Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 2000

    SciTech Connect (OSTI)

    2001-03-01

    This Annual Report to the Congress describes the Department of Energy's activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board. During 2000, the Department completed its implementation and proposed closure of one Board recommendation and completed all implementation plan milestones associated with two additional Board recommendations. Also in 2000, the Department formally accepted two new Board recommendations and developed implementation plans in response to those recommendations. The Department also made significant progress with a number of broad-based safety initiatives. These include initial implementation of integrated safety management at field sites and within headquarters program offices, issuance of a nuclear safety rule, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

  3. Facility Representatives

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

    2006-04-06

    REPLACED BY DOE-STD-1063 | SUPERSEDING DOE-STD-1063-2000 (MARCH 2000) The purpose of the DOE Facility Representative Program is to ensure that competent DOE staff personnel are assigned to oversee the day-to-day contractor operations at DOE’s hazardous nuclear and non-nuclear facilities.

  4. Notice of Intent to Revise DOE G 226.1-2, Federal Line Management Oversight of Department of Energy Nuclear Facilities

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

    2013-04-04

    This revision will incorporate new content devoted to Federal oversight and evaluation of effectiveness of activity-level work planning and control (WP&C) at Hazard Category 1, 2, and 3 nuclear facilities.

  5. Hardware compression using common portions of data

    DOE Patents [OSTI]

    Chang, Jichuan; Viswanathan, Krishnamurthy

    2015-03-24

    Methods and devices are provided for data compression. Data compression can include receiving a plurality of data chunks, sampling at least some of the plurality of data chunks extracting a common portion from a number of the plurality of data chunks based on the sampling, and storing a remainder of the plurality of data chunks in memory.

  6. Overview on backfill materials and permeable reactive barriers for nuclear waste disposal facilities.

    SciTech Connect (OSTI)

    Moore, Robert Charles; Hasan, Ahmed Ali Mohamed; Holt, Kathleen Caroline; Hasan, Mahmoud A. (Egyptian Atomic Energy Authority, Cairo, Egypt)

    2003-10-01

    A great deal of money and effort has been spent on environmental restoration during the past several decades. Significant progress has been made on improving air quality, cleaning up and preventing leaching from dumps and landfills, and improving surface water quality. However, significant challenges still exist in all of these areas. Among the more difficult and expensive environmental problems, and often the primary factor limiting closure of contaminated sites following surface restoration, is contamination of ground water. The most common technology used for remediating ground water is surface treatment where the water is pumped to the surface, treated and pumped back into the ground or released at a nearby river or lake. Although still useful for certain remediation scenarios, the limitations of pump-and-treat technologies have recently been recognized, along with the need for innovative solutions to ground-water contamination. Even with the current challenges we face there is a strong need to create geological repository systems for dispose of radioactive wastes containing long-lived radionuclides. The potential contamination of groundwater is a major factor in selection of a radioactive waste disposal site, design of the facility, future scenarios such as human intrusion into the repository and possible need for retrieving the radioactive material, and the use of backfills designed to keep the radionuclides immobile. One of the most promising technologies for remediation of contaminated sites and design of radioactive waste repositories is the use of permeable reactive barriers (PRBs). PRBs are constructed of reactive material(s) to intercept and remove the radionuclides from the water and decontaminate the plumes in situ. The concept of PRBs is relatively simple. The reactive material(s) is placed in the subsurface between the waste or contaminated area and the groundwater. Reactive materials used thus far in practice and research include zero valent iron

  7. A Multidisciplinary Paradigm and Approach to Protecting Human Health and the Environment, Society, and Stakeholders at Nuclear Facilities - 12244

    SciTech Connect (OSTI)

    Burger, Joanna; Gochfeld, Michael; Clarke, James; Powers, Charles W.; Kosson, David

    2012-07-01

    As the Department of Energy (DOE) continues to remediate its lands, and to consider moving toward long-term stewardship and the development of energy parks on its industrial, remediated land, it is essential to adequately characterize the environment around such facilities to protect society, human health, and the environment. While DOE sites re considering several different land-use scenarios, all of them require adequate protection of the environment. Even if DOE lands are developed for energy parks that are mainly for industrializes sections of DOE lands that will not be remediated to residential standards, there is still the need to consider the protection of human health and the environment. We present an approach to characterization and establishment of teams that will gather the information, and integrate that information for a full range of stakeholders from technical personnel, to public policy makers, and that public. Such information is needed to establish baselines, site new energy facilities in energy parks, protect existing nuclear facilities and nuclear wastes, improve the basis for emergency planning, devise suitable monitoring schemes to ensure continued protection, provide data to track local and regional response changes, and for mitigation, remediation and decommissioning planning. We suggest that there are five categories of information or data needs, including 1) geophysical, sources, fate and transport, 2) biological systems, 3) human health, 4) stakeholder and environmental justice, and 5) societal, economic, and political. These informational needs are more expansive than the traditional site characterization, but encompass a suite of physical, biological, and societal needs to protect all aspects of human health and the environment, not just physical health. We suggest a Site Committee be established that oversees technical teams for each of the major informational categories, with appropriate representation among teams and with a broad

  8. Proceedings of the eighth symposium on training of nuclear facility personnel

    SciTech Connect (OSTI)

    Not Available

    1989-04-01

    This conference brought together those persons in the nuclear industry who have a vital interest in the training and licensing of nuclear reactor and nuclear fuel processing plant operators, senior operators, and support personnel for the purpose of an exchange of ideas and information related to the various aspects of training, retraining, examination, and licensing. The document contains 64 papers; each paper was abstracted for the data.

  9. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project

    SciTech Connect (OSTI)

    Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia P. Tuttle

    2012-01-31

    Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts. The model will be used to assess the present-day composite distribution for seismic sources along with their characterization in the CEUS and uncertainty. In addition, this model is in a form suitable for use in PSHA evaluations for regulatory activities, such as Early Site Permit (ESPs) and Combined Operating License Applications (COLAs). Applications, Values, and Use Development of a regional CEUS seismic source model will provide value to those who (1) have submitted an ESP or COLA for Nuclear Regulatory Commission (NRC) review before 2011; (2) will submit an ESP or COLA for NRC review after 2011; (3) must respond to safety issues resulting from NRC Generic Issue 199 (GI-199) for existing plants and (4) will prepare PSHAs to meet design and periodic review requirements for current and future nuclear facilities. This work replaces a previous study performed approximately 25 years ago. Since that study was completed, substantial work has been done to improve the understanding of seismic sources and their characterization in the CEUS. Thus, a new regional SSC model provides a consistent, stable basis for computing PSHA for a future time span. Use of a new SSC model reduces the risk of delays in new plant licensing due to more conservative interpretations in the existing and future literature. Perspective The purpose of this study, jointly sponsored by EPRI, the U.S. Department of Energy (DOE), and the NRC was to develop a new CEUS SSC model. The team assembled to accomplish this purpose was composed of distinguished subject matter experts from industry, government, and academia. The resulting model is unique, and because this project has solicited input from the present-day larger technical community, it is not likely that there will be a need for significant revision for a number of years. See also Sponsors Perspective for more details. The goal of this project was to implement the CEUS SSC work plan

  10. Inspection of alleged design and construction deficiencies in the Nuclear Materials Storage Facility at the Los Alamos National Laboratory

    SciTech Connect (OSTI)

    1997-01-16

    On June 8, 1994, the Office of Inspections, Office of Inspector General (OIG), Department of Energy (DOE), received a letter dated May 31, 1994, from a complainant concerning the Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory. The complainant alleged that the NMSF, completed in 1987, was so poorly designed and constructed that it was never usable and that DOE proposed to gut the entire facility and sandblast the walls. According to the complainant, ``these errors are so gross as to constitute professional malpractice in a commercial design setting.`` The complainant further stated that ``DOE proposes to renovate this facility to store large amounts of plutonium (as much as 30 metric tons, by some accounts), and it is imperative that the public receive some assurance that this waste will not recur and that the facility will be made safe.`` The purpose of our inspection was to determine if the allegations regarding the design and construction of the NMSF were accurate, and if so, to determine if the Government could recover damages from the Architect/Engineer and/or the construction contractor. We also reviewed the Department`s proposed actions to renovate the NMSF.

  11. Enterprise Assessments Lessons Learned from Targeted Reviews of the Management of Safety Systems at U.S. Department of Energy Nuclear Facilities ¬Ö April 2016

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

    Lessons Learned from Targeted Reviews of the Management of Safety Systems at U.S. Department of Energy Nuclear Facilities April 2016 Office of Nuclear Safety and Environmental Assessments Office of Environment, Safety and Health Assessments Office of Enterprise Assessments U.S. Department of Energy i Table of Contents Acronyms ...................................................................................................................................................... ii Executive Summary

  12. Enterprise Assessments Review of the Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear Facilities ¬Ö April 2016

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

    Review of the Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear Facilities April 2016 Office of Nuclear Safety and Environmental Assessments Office of Environment, Safety and Health Assessments Office of Enterprise Assessments U.S. Department of Energy i Table of Contents Acronyms ...................................................................................................................................................... ii Executive Summary

  13. Central Receiver Test Facility

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

    Receiver Test Facility - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us ... Applications National Solar Thermal Test Facility Nuclear Energy Systems ...

  14. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

    SciTech Connect (OSTI)

    P. Calderoni; P. Sharpe; M. Shimada

    2009-09-01

    The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

  15. DOE-STD-1068-94; DOE Standard Guideline to Good Practices For Maintenance History at DOE Nuclear Facilities

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

    8-94 June 1994 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR MAINTENANCE HISTORY AT DOE NUCLEAR FACILITIES U.S. Department of Energy AREA MNTY Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (615) 576-8401. Available to the public from the

  16. Airborne release fractions/rates and respirable fractions for nonreactor nuclear facilities. Volume 1, Analysis of experimental data

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    This handbook contains (1) a systematic compilation of airborne release and respirable fraction experimental data for nonreactor nuclear facilities, (2) assessments of the data, and (3) values derived from assessing the data that may be used in safety analyses when the data are applicable. To assist in consistent and effective use of this information, the handbook provides: identification of a consequence determination methodology in which the information can be used; discussion of the applicability of the information and its general technical limits; identification of specific accident phenomena of interest for which the information is applicable; and examples of use of the consequence determination methodology and airborne release and respirable fraction information.

  17. REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES

    SciTech Connect (OSTI)

    Reilkoff, T. E.; Hetland, M. D.; O'Leary, E. M.

    2002-02-25

    The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

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

    SciTech Connect (OSTI)

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

    2011-07-01

    Many critical infrastructure sectors have been investigating cyber security issues for several years especially with the help of two primary government programs. The U.S. Department of Energy (DOE) National SCADA Test Bed and the U.S. Department of Homeland Security (DHS) Control Systems Security Program have both implemented activities aimed at securing the industrial control systems that operate the North American electric grid along with several other critical infrastructure sectors (ICS). These programs have spent the last seven years working with industry including asset owners, educational institutions, standards and regulating bodies, and control system vendors. The programs common mission is to provide outreach, identification of cyber vulnerabilities to ICS and mitigation strategies to enhance security postures. The success of these programs indicates that a similar approach can be successfully translated into other sectors including nuclear operations, safeguards, and security. The industry regulating bodies have included cyber security requirements and in some cases, have incorporated sets of standards with penalties for non-compliance such as the North American Electric Reliability Corporation Critical Infrastructure Protection standards. These DOE and DHS programs that address security improvements by both suppliers and end users provide an excellent model for nuclear facility personnel concerned with safeguards and security cyber vulnerabilities and countermeasures. It is not a stretch to imagine complete surreptitious collapse of protection against the removal of nuclear material or even initiation of a criticality event as witnessed at Three Mile Island or Chernobyl in a nuclear ICS inadequately protected against the cyber threat.

  19. Nuclear Facility Maintenance Management Program Guide for Use with DOE O 433.1B

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

    2011-09-09

    The guide provides acceptable approaches for implementing requirements for Nuclear Maintenance Management Programs (NMMPs) set forth in DOE O 433.1B. Admin Chg 1, dated 6-14-13, supersedes DOE G 433.1-1A.

  20. Nuclear Facility Maintenance Management Program Guide for Use with DOE O 433.1B

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

    2011-09-12

    The guide provides acceptable approaches for implementing requirements for Nuclear Maintenance Management Programs (NMMPs) set forth in DOE O 433.1B. Cancels DOE G 433.1-1.

  1. Facility Safety

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

    2012-12-04

    The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. This Page Change is limited in scope to changes necessary to invoke DOE-STD-1104, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Document, and revised DOE-STD-3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis as required methods. DOE O 420.1C Chg 1, dated 2-27-15, supersedes DOE O 420.1C.

  2. Facility Effluent Monitoring Plan for the Spent Nuclear Fuel (SNF) Project

    SciTech Connect (OSTI)

    HUNACEK, G.S.

    2000-08-01

    A facility effluent monitoring plan is required by the US. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in Westinghouse Hanford Company (WHC)-EP-0438-1, ''A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans'', and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the third revision to the original annual report. This document is reviewed annually even if there are no operational changes, and it is updated as necessary.

  3. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    SciTech Connect (OSTI)

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  4. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  5. Decommissioning of German Nuclear Research Facilities under the Governance of the Federal Ministry of Education and Research

    SciTech Connect (OSTI)

    Weigl, M. [Forschungszentrum Karlsruhe GmbH, Projekttragerforschungszentrum Karlsruhe (PTKA-WTE), Karlsruhe (Germany)

    2008-07-01

    Since the announcement of the first nuclear program in 1956, nuclear R and D in Germany has been supported by the Federal Government under four nuclear programs and later on under more general energy R and D programs. The original goal was to help German industry to achieve safe, low-cost generation of energy and self-sufficiency in the various branches of nuclear technology, including the fast breeder reactor and the fuel cycle. Several national research centers were established to host or operate experimental and demonstration plants. These are mainly located at the sites of the national research centers at Juelich and Karlsruhe. In the meantime, all these facilities were shut down and most of them are now in a state of decommissioning and dismantling (D and D). Meanwhile, Germany is one of the leading countries in the world in the field of D and D. Two big demonstration plants, the Niederaichbach Nuclear Power Plant (KKN) a heavy-water cooled pressure tube reactor with carbon-dioxide cooling and the Karlstein Superheated Steam Reactor (HDR) a boiling light water reactor with a thermal power of 100 MW, are totally dismantled and 'green field' is reached. For two other projects the return to 'green field' sites will be reached by the end of this decade. These are the dismantling of the Multi-Purpose Research Reactor (MZFR) and the Compact Sodium Cooled Reactor (KNK) both located at the Forschungszentrum Karlsruhe. Within these projects a lot of new solutions und innovative techniques were tested, which were developed at German universities and in small and medium sized companies mostly funded by the Federal Ministry of Education and Research (BMBF). For example, high performance underwater cutting technologies like plasma arc cutting and contact arc metal cutting. (authors)

  6. Fresh and Spent Nuclear Fuel Repatriation from the IRT-2000 Research Reactor Facility, Sofia, Bulgaria

    SciTech Connect (OSTI)

    K. J. Allen; T. G. Apostolov; I. S. Dimitrov

    2009-03-01

    The IRT 2000 research reactor, operated by the Bulgarian Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped all of their Russian-origin nuclear fuel from the Republic of Bulgaria to the Russian Federation beginning in 2003 and completing in 2008. These fresh and spent fuel shipments removed all highly enriched uranium (HEU) from Bulgaria. The fresh fuel was shipped by air in December 2003 using trucks and a commercial cargo aircraft. One combined spent fuel shipment of HEU and low enriched uranium (LEU) was completed in July 2008 using high capacity VPVR/M casks transported by truck, barge, and rail. The HEU shipments were assisted by the Russian Research Reactor Fuel Return Program (RRRFR) and the LEU spent fuel shipment was funded by Bulgaria. This report describes the work, approvals, organizations, equipment, and agreements required to complete these shipments and concludes with several major lessons learned.

  7. Facility Safety

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

    2002-05-20

    To establish facility safety requirements for the Department of Energy, including National Nuclear Security Administration. Cancels DOE O 420.1. Canceled by DOE O 420.1B.

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

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

    2014-12-19

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

  9. Risk-Informed Design of Seismic Isolation Systems for Nuclear Facilities |

    Office of Environmental Management (EM)

    23 (05-92) Ridefinders Application Please submit this application to the U.S. Department of Energy (DOE) Employee Transportation Coordinator, Room 7A-156, Forrestal. U.S. Department of Energy Privacy Act Statement Check all transportation options which interest you: Carpool: Driver Share Driving Rider Vanpool: Driver Share Driving Rider Do you wish to meet your pool in your neighborhood? No (If no, see Alternate Pickup Locations below.) Yes Participation in the Federal Facility Ridesharing

  10. Facility Safety

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

    2005-12-22

    The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and the System Engineer Program.Chg 1 incorporates the use of DOE-STD-1189-2008, Integration of Safety into the Design Process, mandatory for Hazard Category 1, 2 and 3 nuclear facilities. Cancels DOE O 420.1A.

  11. Facility Safety

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

    2000-11-20

    The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

  12. Guideline for Evaluating Analytical Chemistry Capabilities and Recommending Upgraded Methods and Instrumentation for Nuclear Material Control and Accountability at Russian Nuclear Facilities

    SciTech Connect (OSTI)

    Russ, G.P.

    1999-10-21

    Analytical chemistry plays a key role in nuclear material control and accounting (MC and A). A large part of Special Nuclear Material (SNM) inventories and virtually all of the highly attractive SNM inventories are based on sampling bulk materials followed by destructive assay (DA) of these materials. These measurements support MC and A in process control, physical inventory verification, evaluation of the effects of process changes, detecting and resolving shipper-receiver differences, and the resolution of inspector-facility differences. When evaluating these important functions, US Project Teams need to carefully assess the existing Russian analytical chemistry capabilities and to specify appropriate upgrades where needed. This evaluation and the specification of upgrades have proven difficult, in part, because of the highly specialized and technical nature of DA and because of the wide variety of methods and applications. In addition, providing a DA capability to a Russian analytical laboratory requires much more than simply supplying new instrumentation. Experience has shown that DA upgrades at Russian analytical facilities require more support equipment than was originally anticipated by US Teams. The purpose of this guidance document is to: (1) recommend criteria for US Projects Teams to use in their evaluation of Russian DA capabilities; (2) provide a basis for selection of appropriate upgrades where capabilities are inadequate to support MC and A goals; and (3) to provide a list of Da methods suitable for MC and A with the following information: performance and applications information, strengths and limitations, and references and information on cost. Criteria for evaluating existing capabilities and determining appropriate upgrades are difficult to define. However, this is the basic information needed by the US project Teams. Section IV addresses these criteria.

  13. H. R. 1948: A Bill to reduce the threat from nuclear facilities located in the former Soviet Union. Introduced in the House of Representatives, One Hundred Third Congress, First Session, April 29, 1993

    SciTech Connect (OSTI)

    Not Available

    1994-01-01

    This bill gives the President a directive to establish a program to reduce the environmental and national security threats from nuclear facilities located in the former Soviet Union.

  14. Facility Safety

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

    2005-12-22

    This Order establishes facility and programmatic safety requirements for Department of Energy facilities, which includes nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards mitigation, and the System Engineer Program. Cancels DOE O 420.1A. DOE O 420.1B Chg 1 issued 4-19-10.

  15. Instrumentation report 1: specification, design, calibration, and installation of instrumentation for an experimental, high-level, nuclear waste storage facility

    SciTech Connect (OSTI)

    Brough, W.G.; Patrick, W.C.

    1982-01-01

    The Spent Fuel Test-Climax (SFT-C) is being conducted 420 m underground at the Nevada Test Site under the auspices of the US Department of Energy. The test facility houses 11 spent fuel assemblies from an operating commercial nuclear reactor and numerous other thermal sources used to simulate the near-field effects of a large repository. We developed a large-scale instrumentation plan to ensure that a sufficient quality and quantity of data were acquired during the three- to five-year test. These data help satisfy scientific, operational, and radiation safety objectives. Over 800 data channels are being scanned to measure temperature, electrical power, radiation, air flow, dew point, stress, displacement, and equipment operation status (on/off). This document details the criteria, design, specifications, installation, calibration, and current performance of the entire instrumentation package.

  16. Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2. Radioactive waste and laundry shipments

    SciTech Connect (OSTI)

    Doerge, D. H.; Haffner, D. R.

    1988-06-01

    This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order.

  17. NSR&D Program Fiscal Year (FY) 2015 Call for Proposals Mitigation of Seismic Risk at Nuclear Facilities using Seismic Isolation

    SciTech Connect (OSTI)

    Coleman, Justin

    2015-02-01

    Seismic isolation (SI) has the potential to drastically reduce seismic response of structures, systems, or components (SSCs) and therefore the risk associated with large seismic events (large seismic event could be defined as the design basis earthquake (DBE) and/or the beyond design basis earthquake (BDBE) depending on the site location). This would correspond to a potential increase in nuclear safety by minimizing the structural response and thus minimizing the risk of material release during large seismic events that have uncertainty associated with their magnitude and frequency. The national consensus standard America Society of Civil Engineers (ASCE) Standard 4, Seismic Analysis of Safety Related Nuclear Structures recently incorporated language and commentary for seismically isolating a large light water reactor or similar large nuclear structure. Some potential benefits of SI are: 1) substantially decoupling the SSC from the earthquake hazard thus decreasing risk of material release during large earthquakes, 2) cost savings for the facility and/or equipment, and 3) applicability to both nuclear (current and next generation) and high hazard non-nuclear facilities. Issue: To date no one has evaluated how the benefit of seismic risk reduction reduces cost to construct a nuclear facility. Objective: Use seismic probabilistic risk assessment (SPRA) to evaluate the reduction in seismic risk and estimate potential cost savings of seismic isolation of a generic nuclear facility. This project would leverage ongoing Idaho National Laboratory (INL) activities that are developing advanced (SPRA) methods using Nonlinear Soil-Structure Interaction (NLSSI) analysis. Technical Approach: The proposed study is intended to obtain an estimate on the reduction in seismic risk and construction cost that might be achieved by seismically isolating a nuclear facility. The nuclear facility is a representative pressurized water reactor building nuclear power plant (NPP) structure

  18. SAVANNAH RIVER SITE'S H-CANYON FACILITY: IMPACTS OF FOREIGN OBLIGATIONS ON SPECIAL NUCLEAR MATERIAL DISPOSITION

    SciTech Connect (OSTI)

    Magoulas, V.

    2013-06-03

    The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These ‚Äú123 agreements‚ÄĚ are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

  19. Sample registration software for process automation in the Neutron Activation Analysis (NAA) Facility in Malaysia nuclear agency

    SciTech Connect (OSTI)

    Rahman, Nur Aira Abd Yussup, Nolida; Ibrahim, Maslina Bt. Mohd; Mokhtar, Mukhlis B.; Soh Shaari, Syirrazie Bin Che; Azman, Azraf B.; Salim, Nazaratul Ashifa Bt. Abdullah; Ismail, Nadiah Binti

    2015-04-29

    Neutron Activation Analysis (NAA) had been established in Nuclear Malaysia since 1980s. Most of the procedures established were done manually including sample registration. The samples were recorded manually in a logbook and given ID number. Then all samples, standards, SRM and blank were recorded on the irradiation vial and several forms prior to irradiation. These manual procedures carried out by the NAA laboratory personnel were time consuming and not efficient. Sample registration software is developed as part of IAEA/CRP project on ‚ÄėDevelopment of Process Automation in the Neutron Activation Analysis (NAA) Facility in Malaysia Nuclear Agency (RC17399)‚Äô. The objective of the project is to create a pc-based data entry software during sample preparation stage. This is an effective method to replace redundant manual data entries that needs to be completed by laboratory personnel. The software developed will automatically generate sample code for each sample in one batch, create printable registration forms for administration purpose, and store selected parameters that will be passed to sample analysis program. The software is developed by using National Instruments Labview 8.6.

  20. License Amendment Request for Storing Exelon Sister Nuclear Stations Class B/C LLRW in the LaSalle Station Interim Radwaste Storage Facility - 13620

    SciTech Connect (OSTI)

    Azar, Miguel; Gardner, Donald A.; Taylor, Edward R.

    2013-07-01

    Exelon Nuclear (Exelon) designed and constructed an Interim Radwaste Storage Facility (IRSF) in the mid-1980's at LaSalle County Nuclear Station (LaSalle). The facility was designed to store low-level radioactive waste (LLRW) on an interim basis, i.e., up to five years. The primary reason for the IRSF was to offset lack of disposal in case existing disposal facilities, such as the Southeast Compact's Barnwell Disposal Facility in Barnwell, South Carolina, ceased accepting radioactive waste from utilities not in the Southeast Compact. Approximately ninety percent of the Radwaste projected to be stored in the LaSalle IRSF in that period of time was Class A, with the balance being Class B/C waste. On July 1, 2008 the Barnwell Disposal Facility in the Southeast Compact closed its doors to out of- compact Radwaste, which precluded LaSalle from shipping Class B/C Radwaste to an outside disposal facility. Class A waste generated by LaSalle is still able to be disposed at the 'Envirocare of Utah LLRW Disposal Complex' in Clive, Utah. Thus the need for utilizing the LaSalle IRSF for storing Class B/C Radwaste for an extended period, perhaps life-of-plant or more became apparent. Additionally, other Exelon Midwest nuclear stations located in Illinois that did not build an IRSF heretofore also needed extended Radwaste storage. In early 2009, Exelon made a decision to forward Radwaste from the Byron Nuclear Station (Byron), Braidwood Nuclear Station (Braidwood), and Clinton Nuclear Station (Clinton) to LaSalle's IRSF. As only Class B/C Radwaste would need to be forwarded to LaSalle, the original volumetric capacity of the LaSalle IRSF was capable of handling the small number of additional expected shipments annually from the Exelon sister nuclear stations in Illinois. Forwarding Class B/C Radwaste from the Exelon sister nuclear stations in Illinois to LaSalle would require an amendment to the LaSalle Station operating license. Exelon submitted the License Amendment Request

  1. 105-K Basin material design basis feed description for spent nuclear fuel project facilities

    SciTech Connect (OSTI)

    Praga, A.N.

    1998-01-08

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

  2. The meteorological monitoring audit, preventative maintenance and quality assurance programs at a former nuclear weapons facility

    SciTech Connect (OSTI)

    Maxwell, D.R.

    1995-12-31

    The purposes of the meteorological monitoring audit, preventative maintenance, and quality assurance programs at the Rocky Flats Environmental Technology Site (Site), are to (1) support Emergency Preparedness (EP) programs at the Site in assessing the transport, dispersion, and deposition of effluents actually or potentially released into the atmosphere by Site operations; and (2) provide information for onsite and offsite projects concerned with the design of environmental monitoring networks for impact assessments, environmental surveillance activities, and remediation activities. The risk from the Site includes chemical and radioactive emissions historically related to nuclear weapons component production activities that are currently associated with storage of large quantities of radionuclides (plutonium) and radioactive waste forms. The meteorological monitoring program provides information for site-specific weather forecasting, which supports Site operations, employee safety, and Emergency Preparedness operations.

  3. EPRI/NRC-RES fire PRA guide for nuclear power facilities. Volume 1, summary and overview.

    SciTech Connect (OSTI)

    Not Available

    2004-09-01

    This report documents state-of-the-art methods, tools, and data for the conduct of a fire Probabilistic Risk Assessment (PRA) for a commercial nuclear power plant (NPP) application. The methods have been developed under the Fire Risk Re-quantification Study. This study was conducted as a joint activity between EPRI and the U. S. NRC Office of Nuclear Regulatory Research (RES) under the terms of an EPRI/RES Memorandum of Understanding [RS.1] and an accompanying Fire Research Addendum [RS.2]. Industry participants supported demonstration analyses and provided peer review of this methodology. The documented methods are intended to support future applications of Fire PRA, including risk-informed regulatory applications. The documented method reflects state-of-the-art fire risk analysis approaches. The primary objective of the Fire Risk Study was to consolidate recent research and development activities into a single state-of-the-art fire PRA analysis methodology. Methodological issues raised in past fire risk analyses, including the Individual Plant Examination of External Events (IPEEE) fire analyses, have been addressed to the extent allowed by the current state-of-the-art and the overall project scope. Methodological debates were resolved through a consensus process between experts representing both EPRI and RES. The consensus process included a provision whereby each major party (EPRI and RES) could maintain differing technical positions if consensus could not be reached. No cases were encountered where this provision was invoked. While the primary objective of the project was to consolidate existing state-of-the-art methods, in many areas, the newly documented methods represent a significant advancement over previously documented methods. In several areas, this project has, in fact, developed new methods and approaches. Such advances typically relate to areas of past methodological debate.

  4. DECOMMISSIONING OF SHIELDED FACILITIES AT WINFRITH USED FOR POST IRRADIATION EXAMINATION OF NUCLEAR FUELS & OTHER ACTIVE ITEMS

    SciTech Connect (OSTI)

    Miller, K.D.; Parkinson, S.J.; Cornell, R.M.; Staples, A.T.

    2003-02-27

    This paper describes the approaches used in the clearing, cleaning, decontamination and decommissioning of a very large suite of seven concrete shielded caves and other facilities used by UKAEA at Winfrith Technology Centre, England over a period of about 30 years for the postirradiation examination (PIE) of a wide range of nuclear fuels and other very active components. The basic construction of the facilities will first be described, setting the scene for the major challenges that 1970s' thinking posed for decommissioning engineers. The tendency then to use large and heavy items of equipment supported upon massive steel bench structures produced a series of major problems that had to be overcome. The means of solving these problems by utilization of relatively simple and inexpensive equipment will be described. Later, a further set of challenges was experienced to decontaminate the interior surfaces to allow man entries to be undertaken at acceptable dose rates. The paper will describe the types of tooling used and the range of complementary techniques that were employed to steadily reduce the dose rates down to acceptable levels. Some explanations will also be given for the creation of realistic dose budgets and the methods of recording and continuously assessing the progress against these budgets throughout the project. Some final considerations are given to the commercial approaches to be adopted throughout this major project by the decommissioning engineers. Particular emphasis will be given to the selection of equipment and techniques that are effective so that the whole process can be carried out in a cost-effective and timely manner. The paper also provides brief complementary information obtained during the decommissioning of a plutonium-contaminated facility used for a range of semi-experimental purposes in the late 1970s. The main objective here was to remove the alpha contamination in such a manner that the volume of Plutonium Contaminated Materials (P

  5. Qualitative and Quantitative Assessment of Nuclear Materials Contained in High-Activity Waste Arising from the Operations at the 'SHELTER' Facility

    SciTech Connect (OSTI)

    Cherkas, Dmytro

    2011-10-01

    As a result of the nuclear accident at the Chernobyl NPP in 1986, the explosion dispeesed nuclear materials contained in the nuclear fuel of the reactor core over the destroyed facilities at Unit No. 4 and over the territory immediately adjacent to the destroyed unit. The debris was buried under the Cascade Wall. Nuclear materials at the SHELTER can be characterized as spent nuclear fuel, fresh fuel assemblies (including fuel assemblies with damaged geometry and integrity, and individual fuel elements), core fragments of the Chernobyl NPP Unit No. 4, finely-dispersed fuel (powder/dust), uranium and plutonium compounds in water solutions, and lava-like nuclear fuel-containing masses. The new safe confinement (NSC) is a facility designed to enclose the Chernobyl NPP Unit No. 4 destroyed by the accident. Construction of the NSC involves excavating operations, which are continuously monitored including for the level of radiation. The findings of such monitoring at the SHELTER site will allow us to characterize the recovered radioactive waste. When a process material categorized as high activity waste (HAW) is detected the following HLW management operations should be involved: HLW collection; HLW fragmentation (if appropriate); loading HAW into the primary package KT-0.2; loading the primary package filled with HAW into the transportation cask KTZV-0.2; and storing the cask in temporary storage facilities for high-level solid waste. The CDAS system is a system of 3He tubes for neutron coincidence counting, and is designed to measure the percentage ratio of specific nuclear materials in a 200-liter drum containing nuclear material intermixed with a matrix. The CDAS consists of panels with helium counter tubes and a polyethylene moderator. The panels are configured to allow one to position a waste-containing drum and a drum manipulator. The system operates on the ‚Äėadd a source‚Äô basis using a small Cf-252 source to identify irregularities in the matrix during an assay

  6. Frequently Asked Questions Regarding DOE-STD-1195-2011, Design of Safety Significant Safety Instrumented Systems Used at DOE Non-Reactor Nuclear Facilities

    Broader source: Energy.gov [DOE]

    Frequently Asked Questions Regarding DOE-STD-1195-2011 which provides requirements and guidance for the design, procurement, installation, testing, maintenance, operation, and quality assurance of safety instrumented systems (SIS) that may be used at Department of Energy (DOE) nonreactor nuclear facilities for safety significant (SS) functions.

  7. ARM - Facility News Article

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

    March 20, 2014 [Facility News, Publications] 2013 ARM Annual Report Now Available Bookmark and Share The 2013 edition of the ARM Climate Research Facility Annual Report was published in February 2014. The first 25 pages include a short overview of the Facility, followed by featured field campaigns, user research results, and summaries of infrastructure achievements. The back portion of the report includes a summary of all 2013 field campaigns conducted throughout the ARM Facility and a

  8. Facility Representative, Technical Area (TA-55) Plutonium Facility, Los

    National Nuclear Security Administration (NNSA)

    Alamos Site Office | National Nuclear Security Administration | (NNSA) Facility Representative, Technical Area (TA-55) Plutonium Facility, Los Alamos Site Office John Krepps John Krepps June 2010 U.S. Department of Energy Facility Representative of the Year John Krepps, a facility representative for the National Nuclear Security Administration's (NNSA) Los Alamos Site Office, received the Department of Energy's top award for oversight of nuclear and non-nuclear facilities. Krepps, a Los

  9. The Radiochemical Analysis of Gaseous Samples (RAGS) Apparatus for Nuclear Diagnostics at the National Ignition Facility

    SciTech Connect (OSTI)

    Shaughnessy, D A; Velsko, C A; Jedlovec, D R; Yeamans, C B; Moody, K J; Tereshatov, E; Stoeffl, W; Riddle, A

    2012-05-11

    The RAGS (Radiochemical Analysis of Gaseous Samples) diagnostic apparatus was recently installed at the National Ignition Facility. Following a NIF shot, RAGS is used to pump the gas load from the NIF chamber for purification and isolation of the noble gases. After collection, the activated gaseous species are counted via gamma spectroscopy for measurement of the capsule areal density and fuel-ablator mix. Collection efficiency was determined by injecting a known amount of {sup 135}Xe into the NIF chamber, which was then collected with RAGS. Commissioning was performed with an exploding pusher capsule filled with isotopically enriched {sup 124}Xe and {sup 126}Xe added to the DT gas fill. Activated xenon species were recovered post-shot and counted via gamma spectroscopy. Results from the collection and commissioning tests are presented. The performance of RAGS allows us to establish a noble gas collection method for measurement of noble gas species produced via neutron and charged particle reactions in a NIF capsule.

  10. Risk-Based Decision Process for Accelerated Closure of a Nuclear Weapons Facility

    SciTech Connect (OSTI)

    Butler, L.; Norland, R. L.; DiSalvo, R.; Anderson, M.

    2003-02-25

    Nearly 40 years of nuclear weapons production at the Rocky Flats Environmental Technology Site (RFETS or Site) resulted in contamination of soil and underground systems and structures with hazardous substances, including plutonium, uranium and hazardous waste constituents. The Site was placed on the National Priority List in 1989. There are more than 370 Individual Hazardous Substance Sites (IHSSs) at RFETS. Accelerated cleanup and closure of RFETS is being achieved through implementation and refinement of a regulatory framework that fosters programmatic and technical innovations: (1) extensive use of ''accelerated actions'' to remediate IHSSs, (2) development of a risk-based screening process that triggers and helps define the scope of accelerated actions consistent with the final remedial action objectives for the Site, (3) use of field instrumentation for real time data collection, (4) a data management system that renders near real time field data assessment, and (5) a regulatory agency consultative process to facilitate timely decisions. This paper presents the process and interim results for these aspects of the accelerated closure program applied to Environmental Restoration activities at the Site.

  11. A Low-Cost, Real-Time Network for Radiological Monitoring Around Nuclear Facilities

    SciTech Connect (OSTI)

    Bertoldo, N A

    2004-08-13

    reconfiguration to a combined hard-wired and wireless network, which incorporates a robust server and modeling software, the system would be a durable and economical radiological monitoring system for nuclear power plants around the world.

  12. Facility Safety - DOE Directives, Delegations, and Requirements

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

    0.1C Chg 1, Facility Safety by Pranab Guha Functional areas: DNFSB, Defense Nuclear Facility Safety and Health Requirement, Facility Safety, Requires Crosswalk When Revised,...

  13. Facility Safety - DOE Directives, Delegations, and Requirements

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

    O 420.1C Chg 1, Facility Safety by Pranab Guha Functional areas: DNFSB, Defense Nuclear Facility Safety and Health Requirement, Facility Safety, Requires Crosswalk When Revised, ...

  14. Role of alkyl alcohol on viscosity of silica-based chemical gels for decontamination of highly radioactive nuclear facilities

    SciTech Connect (OSTI)

    Choi, B. S.; Yoon, S. B.; Jung, C. H.; Lee, K. W.; Moon, J. K.

    2012-07-01

    Silica-based chemical gel for the decontamination of nuclear facilities was prepared by using fumed silica as a viscosifier, a 0.5 M Ce (IV) solution dissolved in concentrated nitric acid as a chemical decontamination agent, and tripropylene glycol butyl ether (TPGBE) as a co-viscosifier. A new effective strategy for the preparation of the chemical gel was investigated by introducing the alkyl alcohols as organic solvents to effectively dissolve the co-viscosifier. The mixture solution of the co-viscosifier and alkyl alcohols was more effective in the control of viscosity than that of the co-viscosifier only in gel. Here, the alkyl alcohols played a key role as an effective dissolution solvent for the co-viscosifier in the preparation of the chemical gel, resulting in a reducing of the amount of the co-viscosifier and gel time compared with that of the chemical gel prepared without the alkyl alcohols. It was considered that the alkyl alcohols contributed to the effective dissolution of the co-viscosifier as well as the homogeneous mixing in the formation of the gel, while the co-viscosifier in an aqueous media of the chemical decontamination agent solution showed a lower solubility. The decontamination efficiency of the chemical gels prepared in this work using a multi-channel analyzer (MCA) showed a high decontamination efficiency of over ca. 94% and ca. 92% for Co-60 and Cs-137 contaminated on surface of the stainless steel 304, respectively. (authors)

  15. Facility Safety

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

    2013-06-21

    DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and approval formally document the basis for DOE, concluding that a facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Therefore, it is appropriate to formally require implementation of the review methodology and criteria contained in DOE-STD-1104.

  16. Facility Disposition Safety Strategy RM

    Office of Environmental Management (EM)

    ... facility and nuclear safety requirements defined in 10 CFR 830, Nuclear Safety Management, and worker safety requirements defined in 10 CFR 851, Worker Safety and Health Program. ...

  17. Facility Safety | Department of Energy

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

    Department of Energy's (DOE) Office of Nuclear Facility Safety works proactively with headquarters and field offices to foster continuous improvement and nuclear safety excellence. ...

  18. Fuel Conditioning Facility Electrorefiner Process Model

    SciTech Connect (OSTI)

    DeeEarl Vaden

    2005-10-01

    The Fuel Conditioning Facility at the Idaho National Laboratory processes spent nuclear fuel from the Experimental Breeder Reactor II using electro-metallurgical treatment. To process fuel without waiting for periodic sample analyses to assess process conditions, an electrorefiner process model predicts the composition of the electrorefiner inventory and effluent streams. For the chemical equilibrium portion of the model, the two common methods for solving chemical equilibrium problems, stoichiometric and non stoichiometric, were investigated. In conclusion, the stoichiometric method produced equilibrium compositions close to the measured results whereas the non stoichiometric method did not.

  19. The Process, Methods and Tool Used To Integrate Safety During Design of a Category 2 Nuclear Facility

    Broader source: Energy.gov [DOE]

    Presenter: Lynn J. Harkey, SDIT Project Engineer, Uranium Processing Facility Project, B&W Y-12 Track 5-2

  20. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1B: Citations with abstracts, sections 10 through 16

    SciTech Connect (OSTI)

    1997-09-01

    This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

  1. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1A: Citations with abstracts, sections 1 through 9

    SciTech Connect (OSTI)

    1997-09-01

    This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

  2. CRAD, Assessment Criteria and Guidelines for Determining the Adequacy of Software Used in the Safety Analysis and Design of Defense Nuclear Facilities

    Office of Energy Efficiency and Renewable Energy (EERE)

    These guidelines and criteria provide a consistent overall framework for assessment of the processes that are currently in place to ensure that the software being used in the safety analysis and design of the SSCs in defense nuclear facilities is adequate. These reviews will be conducted only on software that is currently in use, not on software that was previously used as part of a safety analysis and design process.

  3. DOE-STD-1050-93; DOE Standard Guideline to Good Practices For Planning, Scheduling, and Coordination of Maintenance at DOE Nuclear Facilities

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

    0-93 March 1993 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR PLANNING, SCHEDULING, AND COORDINATION OF MAINTENANCE AT DOE NUCLEAR FACILITIES U.S. Department of Energy AREA MNTY Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62 Oak Ridge, TN 37831. Available to the

  4. DOE-STD-1053-93; DOE Standard Guideline to Good Practices For Control of Maintenance Activities at DOE Nuclear Facilities

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

    3-93 March 1993 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR CONTROL OF MAINTENANCE ACTIVITIES AT DOE NUCLEAR FACILITIES U.S. Department of Energy AREA MNTY Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831. Available to the public from the

  5. Conceptual design report: Nuclear materials storage facility renovation. Part 5, Structural/seismic investigation. Section A report, existing conditions calculations/supporting information

    SciTech Connect (OSTI)

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. Based upon US Department of Energy (DOE) Albuquerque Operations (DOE/Al) Office and LANL projections, storage space limitations/restrictions will begin to affect LANL`s ability to meet its missions between 1998 and 2002.

  6. ARM - Facility News Article

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

    January 15, 2008 [Facility News] ARM Mobile Facility Completes Field Campaign in Germany Bookmark and Share Researchers will study severe precipitation events that occurred in August and October 2007, stalling Rhine River traffic and causing flooding in portions of Germany. (Image source: DW-WORLD.DE) Operations at the ARM Mobile Facility (AMF) site in Heselbach, Germany, officially came to a close on January 1, 2008. As one of several measurement "supersites" situated throughout the

  7. Transition duct with divided upstream and downstream portions

    SciTech Connect (OSTI)

    McMahan, Kevin Weston; LeBegue, Jeffrey Scott; Maldonado, Jaime Javier; Dillard, Daniel Jackson; Flanagan, James Scott

    2015-07-14

    Turbine systems are provided. In one embodiment, a turbine system includes a transition duct comprising an inlet, an outlet, and a duct passage extending between the inlet and the outlet and defining a longitudinal axis, a radial axis, and a tangential axis. The outlet of the transition duct is offset from the inlet along the longitudinal axis and the tangential axis. The duct passage includes an upstream portion extending from the inlet and a downstream portion extending from the outlet. The turbine system further includes a rib extending from an outer surface of the duct passage, the rib dividing the upstream portion and the downstream portion.

  8. Method of non-destructively inspecting a curved wall portion

    DOE Patents [OSTI]

    Fong, James T.

    1996-01-01

    A method of non-destructively inspecting a curved wall portion of a large and thick walled vessel for a defect by computed tomography is provided. A collimated source of radiation is placed adjacent one side of the wall portion and an array of detectors for the radiation is placed on the other side adjacent the source. The radiation from the source passing through the wall portion is then detected with the detectors over a limited angle, dependent upon the curvature of the wall of the vessel, to obtain a dataset. The source and array are then coordinately moved relative to the wall portion in steps and a further dataset is obtained at each step. The plurality of datasets obtained over the limited angle is then processed to produce a tomogram of the wall portion to determine the presence of a defect therein. In a preferred embodiment, the curved wall portion has a center of curvature so that the source and the array are positioned at each step along a respective arc curved about the center. If desired, the detector array and source can be reoriented relative to a new wall portion and an inspection of the new wall portion can be easily obtained. Further, the source and detector array can be indexed in a direction perpendicular to a plane including the limited angle in a plurality of steps so that by repeating the detecting and moving steps at each index step, a three dimensional image can be created of the wall portion.

  9. Facility Safety | Department of Energy

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

    Facility Safety Facility Safety In addition to establishing nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities, the U.S. Department of Energy's (DOE) Office of Nuclear Facility Safety works proactively with headquarters and field offices to foster continuous improvement and nuclear safety excellence. In addition, the Office provides high quality, customer-oriented assistance that enables improved DOE program and field

  10. A benchmark comparison of predicted x-ray and neutron doses for a nuclear effects test in the Laboratory Microfusion Facility

    SciTech Connect (OSTI)

    Beller, D.E. ); Tobin, M.T. ); Lorence, L.J. )

    1990-09-18

    An intermediate step in the development of inertial confinement fusion (ICF) for power production will be the development and testing of a high-gain facility. One concept being considered for this facility is the Laboratory Microfusion Facility (LMF). Other projected applications of the LMF include high-energy-density physics experiments and nuclear effects testing. At the Air Force Institute of Technology (AFIT), Lawrence Livermore National Laboratory (LLNL), and Sandia National Laboratories Albuquerque (SNLA), we have been studying the use of the LMF for nuclear effects experiments. Because of the amount of energy that will be released in a high-gain ICF test and the size of the LMF, test objects could be any size from very small electronic components to large systems; and nuclear effects in the LMF may include thermal radiation, x-rays, electromagnetic pulse, gamma rays, neutrons, or others. At AFIT, LLNL, and SNLA we have been investigating a test to expose systems to high-energy x-ray pulses, and have completed predictions of x-ray fluence, dose, etc. in various conceptual LMF reactors. However, comparison of our results is more meaningful if our prediction methods produce the same results for the same design. To establish a basis for comparison, we set up a simple benchmark problem and we each computed x-ray and neutron transport. The model and codes are described and the results are compared and discussed.

  11. About the Facility

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

    National Solar Thermal Test Facility Nuclear Energy Systems LaboratoryBrayton Lab Photovoltaic Systems Evaluation Laboratory PV Regional Test Centers Scaled Wind Farm ...

  12. Facility Safety

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

    2012-12-04

    The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. Cancels DOE O 420.1B, DOE G 420.1-2 and DOE G 420.1-3.

  13. Facility Safety

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

    1995-10-13

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

  14. Analysis of a Nuclear Accident: Fission and Activation Product Releases from the Fukushima Daiichi Nuclear Facility as Remote Indicators of Source Identification, Extent of Release, and State of Damaged Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Schwantes, Jon M.; Orton, Christopher R.; Clark, Richard A.

    2012-09-10

    Measurements of several radionuclides within environmental samples taken from the Fukushima Daiichi nuclear facility and reported on the Tokyo Electric Power Company website following the recent tsunami-initiated catastrophe were evaluated for the purpose of identifying the source term, reconstructing the release mechanisms, and estimating the extent of the release. 136Cs/137Cs and 134Cs/137Cs ratios identified Units 1-3 as the major source of radioactive contamination to the surface soil close to the facility. A trend was observed between the fraction of the total core inventory released for a number of fission product isotopes and their corresponding Gibbs Free Energy of formation for the primary oxide form of the isotope, suggesting that release was dictated primarily by chemical volatility driven by temperature and reduction potential within the primary containment vessels of the vented reactors. The absence of any major fractionation beyond volatilization suggested all coolant had evaporated by the time of venting. High estimates for the fraction of the total inventory released of more volatile species (Te, Cs, I) indicated the damage to fuel bundles was likely extensive, minimizing any potential containment due to physical migration of these species through the fuel matrix and across the cladding wall. 238Pu/239,240Pu ratios close-in and at 30 km from the facility indicated that the damaged reactors were the major contributor of Pu to surface soil at the source but that this contribution likely decreased rapidly with distance from the facility. The fraction of the total Pu inventory released to the environment from venting units 1 and 3 was estimated to be ~0.003% based upon Pu/Cs isotope ratios relative to the within-reactor modeled inventory prior to venting and was consistent with an independent model evaluation that considered chemical volatility based upon measured fission product release trends. Significant volatile radionuclides within the spent fuel

  15. nuclear

    National Nuclear Security Administration (NNSA)

    2%2A en U.S-, Japan Exchange Best Practices on Nuclear Emergency Response http:nnsa.energy.govmediaroompressreleasesu.s-japan-exchange-best-practices-nuclear-emergency-respon...

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  17. Nuclear and Radiological Material Security | National Nuclear...

    National Nuclear Security Administration (NNSA)

    This includes NNSA's work to advance physical protection standards for nuclear facilities and to strengthen nuclear safeguards, which are criteria for the physical security and the ...

  18. Climax Granite, Nevada Test Site, as a host for a rock mechanics test facility related to the geologic disposal of high level nuclear wastes

    SciTech Connect (OSTI)

    Heuze, F.E.

    1981-02-01

    This document discusses the potential of the Climax pluton, at the Nevada Test Site, as the host for a granite mechanics test facility related to the geologic disposal of high-level nuclear waste. The Climax granitic pluton has been the site of three nuclear weapons effects tests: Hard Hat, Tiny Tot, and Piledriver. Geologic exploration and mapping of the granite body were performed at the occasion of these tests. Currently, it is the site Spent Fuel Test (SFT-C) conducted in the vicinity of and at the same depth as that of the Piledriver drifts. Significant exploration, mapping, and rock mechanics work have been performed and continue at this Piledriver level - the 1400 (ft) level - in the context of SFT-C. Based on our technical discussions, and on the review of the significant geological and rock mechanics work already achieved in the Climax pluton, based also on the ongoing work and the existing access and support, it is concluded that the Climax site offers great opportunities for a rock mechanics test facility. It is not claimed, however, that Climax is the only possible site or the best possible site, since no case has been made for another granite test facility in the United States. 12 figures, 3 tables.

  19. nuclear controls

    National Nuclear Security Administration (NNSA)

    which "international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and...

  20. Silica substrate or portion formed from oxidation of monocrystalline silicon

    DOE Patents [OSTI]

    Matzke, Carolyn M.; Rieger, Dennis J.; Ellis, Robert V.

    2003-07-15

    A method is disclosed for forming an inclusion-free silica substrate using a monocrystalline silicon substrate as the starting material and oxidizing the silicon substrate to convert it entirely to silica. The oxidation process is performed from both major surfaces of the silicon substrate using a conventional high-pressure oxidation system. The resulting product is an amorphous silica substrate which is expected to have superior etching characteristics for microfabrication than conventional fused silica substrates. The present invention can also be used to convert only a portion of a monocrystalline silicon substrate to silica by masking the silicon substrate and locally thinning a portion the silicon substrate prior to converting the silicon portion entirely to silica. In this case, the silica formed by oxidizing the thinned portion of the silicon substrate can be used, for example, as a window to provide optical access through the silicon substrate.

  1. DEVELOPMENT OF A MULTI-LOOP FLOW AND HEAT TRANSFER FACILITY FOR ADVANCED NUCLEAR REACTOR THERMAL HYDRAULIC AND HYBRID ENERGY SYSTEM STUDIES

    SciTech Connect (OSTI)

    James E. O'Brien; Piyush Sabharwall; SuJong Yoon

    2001-09-01

    A new high-temperature multi-fluid, multi-loop test facility for advanced nuclear applications is under development at the Idaho National Laboratory. The facility will include three flow loops: high-temperature helium, molten salt, and steam/water. Molten salts have been identified as excellent candidate heat transport fluids for primary or secondary coolant loops, supporting advanced high temperature and small modular reactors (SMRs). Details of some of the design aspects and challenges of this facility, which is currently in the conceptual design phase, are discussed. A preliminary design configuration will be presented, with the required characteristics of the various components. The loop will utilize advanced high-temperature compact printed-circuit heat exchangers (PCHEs) operating at prototypic intermediate heat exchanger (IHX) conditions. The initial configuration will include a high-temperature (750¬įC), high-pressure (7 MPa) helium loop thermally integrated with a molten fluoride salt (KF-ZrF4) flow loop operating at low pressure (0.2 MPa) at a temperature of ~450¬įC. Experiment design challenges include identification of suitable materials and components that will withstand the required loop operating conditions. Corrosion and high temperature creep behavior are major considerations. The facility will include a thermal energy storage capability designed to support scaled process heat delivery for a variety of hybrid energy systems and grid stabilization strategies. Experimental results obtained from this research will also provide important data for code ve

  2. U.S. Energy Secretary Moniz and Chinese Atomic Energy Authority Open New Nuclear Security Training Facility

    Broader source: Energy.gov [DOE]

    U.S. Secretary of Energy Ernest Moniz, accompanied by senior officials from the Department of Energy’s National Nuclear Security Administration (DOE/NNSA), the Department of Defense, and a host of international VIPs, participated with the China Atomic Energy Authority (CAEA) to commission China’s new nuclear security Center of Excellence (COE).

  3. Process Flow Chart for Immobilizing of Radioactive High Concentration Sodium Hydroxide Product from the Sodium Processing Facility at the BN-350 Nuclear power plant in Aktau, Kazakhstan

    SciTech Connect (OSTI)

    Burkitbayev, M.; Omarova, K.; Tolebayev, T.; Galkin, A.; Bachilova, N.; Blynskiy, A.; Maev, V.; Wells, D.; Herrick, A.; Michelbacher, J.

    2008-07-01

    This paper describes the results of a joint research investigations carried out by the group of Kazakhstan, British and American specialists in development of a new material for immobilization of radioactive 35% sodium hydroxide solutions from the sodium coolant processing facility of the BN-350 nuclear power plant. The resulting solid matrix product, termed geo-cement stone, is capable of isolating long lived radionuclides from the environment. The physico-mechanical properties of geo-cement stone have been investigated and the flow chart for its production verified in a full scale experiments. (author)

  4. An Application of the SSHAC Level 3 Process to the Probabilistic Seismic Hazard Analysis for Nuclear Facilities at the Hanford Site, Eastern Washington, USA

    SciTech Connect (OSTI)

    Coppersmith , Kevin J.; Bommer, Julian J.; Bryce, Robert W.; Mcduffie, Stephen M.; Lisle, Greg A.

    2013-08-22

    Under the sponsorship of the US Department of Energy (DOE) and the electric utility Energy Northwest, the Pacific Northwest National Laboratory (PNNL) is conducting a probabilistic seismic hazard analysis (PSHA) within the framework of a SSHAC Level 3 procedure (Senior Seismic Hazard Analysis Committee; Budnitz et al., 1997). Specifically, the project is being conducted following the guidelines and requirements specified in NUREG-2117 (USNRC, 2012b) and consistent with approach given in the American Nuclear Standard ANSI/ANS-2.29-2008 Probabilistic Seismic Hazard Analysis. The collaboration between DOE and Energy Northwest is spawned by the needs of both organizations for an accepted PSHA with high levels of regulatory assurance that can be used for the design and safety evaluation of nuclear facilities. DOE committed to this study after performing a ten-year review of the existing PSHA, as required by DOE Order 420.1C. The study will also be used by Energy Northwest as a basis for fulfilling the NRC’s 10CFR50.54(f) requirement that the western US nuclear power plants conduct PSHAs in conformance with SSHAC Level 3 procedures. The study was planned and is being carried out in conjunction with a project Work Plan, which identifies the purpose of the study, the roles and responsibilities of all participants, tasks and their associated schedules, Quality Assurance (QA) requirements, and project deliverables. New data collection and analysis activities are being conducted as a means of reducing the uncertainties in key inputs to the PSHA. It is anticipated that the results of the study will provide inputs to the site response analyses at multiple nuclear facility sites within the Hanford Site and at the Columbia Generating Station.

  5. Facility Safety - DOE Directives, Delegations, and Requirements

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

    Alamos Site Office | National Nuclear Security Administration | (NNSA) Facility Representative, Technical Area (TA-55) Plutonium Facility, Los Alamos Site Office John Krepps John Krepps June 2010 U.S. Department of Energy Facility Representative of the Year John Krepps, a facility representative for the National Nuclear Security Administration's (NNSA) Los Alamos Site Office, received the Department of Energy's top award for oversight of nuclear and non-nuclear facilities. Krepps, a Los

  6. CSER-98-002: Criticality analysis for the storage of special nuclear material sources and standards in the WRAP facility

    SciTech Connect (OSTI)

    GOLDBERG, H.J.

    1999-05-18

    The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirements of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility.

  7. User Facilities | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Facilities User Facilities Print Text Size: A A A FeedbackShare Page The Nuclear Physics program supports the following national scientific user facilities: Argonne Tandem ...

  8. Risk-based Prioritization of Facility Decommissioning and Environmental Restoration Projects in the National Nuclear Legacy Liabilities Program at the Chalk River Laboratory - 13564

    SciTech Connect (OSTI)

    Nelson, Jerel G.; Kruzic, Michael; Castillo, Carlos; Pavey, Todd; Alexan, Tamer; Bainbridge, Ian

    2013-07-01

    Chalk River Laboratory (CRL), located in Ontario Canada, has a large number of remediation projects currently in the Nuclear Legacy Liabilities Program (NLLP), including hundreds of facility decommissioning projects and over one hundred environmental remediation projects, all to be executed over the next 70 years. Atomic Energy of Canada Limited (AECL) utilized WorleyParsons to prioritize the NLLP projects at the CRL through a risk-based prioritization and ranking process, using the WorleyParsons Sequencing Unit Prioritization and Estimating Risk Model (SUPERmodel). The prioritization project made use of the SUPERmodel which has been previously used for other large-scale site prioritization and sequencing of facilities at nuclear laboratories in the United States. The process included development and vetting of risk parameter matrices as well as confirmation/validation of project risks. Detailed sensitivity studies were also conducted to understand the impacts that risk parameter weighting and scoring had on prioritization. The repeatable prioritization process yielded an objective, risk-based and technically defendable process for prioritization that gained concurrence from all stakeholders, including Natural Resources Canada (NRCan) who is responsible for the oversight of the NLLP. (authors)

  9. Nuclear Safety Regulatory Framework

    Energy Savers [EERE]

    Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural ...

  10. Nuclear Controls Checklist

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

    Nuclear Controls Yes No 1) Is your Facility involved in the research on or development, design, manufacture, construction, testing or maintenance of any nuclear explosive ...

  11. 2013 Nuclear Workforce Development ...

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

    Practice in Nuclear Medicine Radiopharmacy Patient Care Medical Imaging & Computers Moderator: Deborah M. Gibbs, MEd, PET, CNMT Lead Nuclear Medicine PET Facility...

  12. Biosafety Facilities - DOE Directives, Delegations, and Requirements

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

    5, Biosafety Facilities by David Freshwater Functional areas: Defense Nuclear Facility Safety and Health Requirement, Safety and Security, The Guide assists DOENNSA field elements...

  13. REGULATORY STRATEGIES TO MINIMIZE GENERATION OF REGULATED WASTES FROM CLEANUP, CONTINUED USE OR DECOMMISSIONING OF NUCLEAR FACILITIES CONTAMINATED WITH POLYCHLORINATED BIPHENYLS (PCBS) - 11198

    SciTech Connect (OSTI)

    Lowry, N.

    2010-11-05

    Disposal costs for liquid PCB radioactive waste are among the highest of any category of regulated waste. The high cost is driven by the fact that disposal options are extremely limited. Toxic Substances Control Act (TSCA) regulations require most liquids with PCBs at concentration of {ge} 50 parts-per-million to be disposed by incineration or equivalent destructive treatment. Disposal fees can be as high as $200 per gallon. This figure does not include packaging and the cost to transport the waste to the disposal facility, or the waste generator's labor costs for managing the waste prior to shipment. Minimizing the generation of liquid radioactive PCB waste is therefore a significant waste management challenge. PCB spill cleanups often generate large volumes of waste. That is because the removal of PCBs typically requires the liberal use of industrial solvents followed by a thorough rinsing process. In a nuclear facility, the cleanup process may be complicated by the presence of radiation and other occupational hazards. Building design and construction features, e.g., the presence of open grating or trenches, may also complicate cleanup. In addition to the technical challenges associated with spill cleanup, selection of the appropriate regulatory requirements and approach may be challenging. The TSCA regulations include three different sections relating to the cleanup of PCB contamination or spills. EPA has also promulgated a separate guidance policy for fresh PCB spills that is published as Subpart G of 40 CFR 761 although it is not an actual regulation. Applicability is based on the circumstances of each contamination event or situation. Other laws or regulations may also apply. Identification of the allowable regulatory options is important. Effective communication with stakeholders, particularly regulators, is just as important. Depending on the regulatory path that is taken, cleanup may necessitate the generation of large quantities of regulated waste

  14. NEAC Facilities Subcommittee Report

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

    Facilities Subcommittee Report Presentation to the NEAC Committee 12/11/2015 John I. Sackett Facilities Subcommittee Members * John Ahearne * Dana Christensen * Tom Cochran * Mike Corradini * Dave Hill * Hussein Khalil * Andy Klein * Paul Murray * John Sackett, chair Subcommittee Objectives * The objective of our deliberations has been to help DOE-NE develop a means to identify, prioritize and make available those facilities important to Nuclear Energy Research and Development. - All facilities

  15. Social impacts of hazardous and nuclear facilities and events: Implications for Nevada and the Yucca Mountain high-level nuclear waste repository; [Final report

    SciTech Connect (OSTI)

    Freudenburg, W.R.; Carter, L.F.; Willard, W.; Lodwick, D.G.; Hardert, R.A.; Levine, A.G.; Kroll-Smith, S.; Couch, S.R.; Edelstein, M.R.

    1992-05-01

    Social impacts of a nuclear waste repository are described. Various case studies are cited such as Rocky Flats Plant, the Feed Materials Production Center, and Love Canal. The social impacts of toxic contamination, mitigating environmental stigma and loss of trust are also discussed.

  16. Applications of nuclear reaction analysis to metal hydride film characterization at the GEND 200 KeV accelerator facility

    SciTech Connect (OSTI)

    Malbrough, D.J.; Becker, R.H.

    1985-01-01

    Nuclear reaction analysis (NRA) is a quantitative analytical technique that usually involves the use of MeV ion beams and resonant nuclear reactions to non-destructively probe materials for elemental content and depth profiles. Low energy, non-resonant nuclear reactions can also be exploited for NRA and procedures have been developed for using the GEND 200-KeV accelerator to characterize neutron generator components by that technique. The procedures involve the detection and analysis of fusion reaction products generated by the interactions of deuteron beams with light elements in metal hydride films. A description of the accelerator system is presented along with some of the unique NRA procedures that have recently been developed for its use. The system is used to measure neutron output efficiencies of metal deuterides and tritides by the associated particle technique (APT) and accurate neutron yield measurements have been made for a number of materials for which data was formerly not available.

  17. Proof of Concept Experiments of the Multi-Isotope Process Monitor: An Online, Nondestructive, Near Real-Time Monitor for Spent Nuclear Fuel Reprocessing Facilities

    SciTech Connect (OSTI)

    Orton, Christopher R.; Fraga, Carlos G.; Christensen, Richard; Schwantes, Jon M.

    2012-04-21

    Operators, national regulatory agencies and the IAEA will require the development of advanced technologies to efficiently control and safeguard nuclear material at increasingly large-scale nuclear recycling facilities. Ideally, the envisioned technologies would be capable of non-destructive, near-real-time (NRT), autonomous process monitoring. This paper describes results from proof-of-principle experiments designed to test the Multi-Isotope Process (MIP) Monitor, a novel approach to safeguarding reprocessing facilities. The MIP Monitor combines the detection of intrinsic gamma ray signatures emitted from process solutions with multivariate analysis to detect off-normal conditions in process streams nondestructively and in NRT. Commercial spent nuclear fuel of various irradiation histories was dissolved and separated using a PUREX-based batch solvent extraction. Extractions were performed at various nitric acid concentrations to mimic both normal and off-normal industrial plant operating conditions. Principal Component Analysis (PCA) was applied to the simulated gamma spectra to investigate pattern variations as a function of acid concentration, burnup and cooling time. Partial Least Squares (PLS) regression was applied to attempt to quantify both the acid concentration and burnup of the dissolved spent fuel during the initial separation stage of recycle. The MIP Monitor demonstrated sensitivity to induced variations of acid concentration, including the distinction of {+-} 1.3 M variation from normal process conditions by way of PCA. Acid concentration was predicted using measurements from the organic extract and PLS resulting in predictions with <0.7 M relative error. Quantification of burnup levels from dissolved fuel spectra using PLS was demonstrated to be within 2.5% of previously measured values.

  18. Safeguards Options for Natural Uranium Conversion Facilities ? A Collaborative Effort between the U.S. Department of Energy (DOE) and the National Nuclear Energy Commission of Brazil (CNEN)

    SciTech Connect (OSTI)

    Raffo-Caiado, Ana Claudia; Begovich, John M; Ferrada, Juan J

    2008-01-01

    In 2005, the National Nuclear Energy Commission of Brazil (CNEN) and the U.S. Department of Energy (DOE) agreed on a collaborative effort to evaluate measures that can strengthen the effectiveness of international safeguards at a natural uranium conversion plant (NUCP). The work was performed by DOE's Oak Ridge National Laboratory and CNEN. A generic model of an NUCP was developed and typical processing steps were defined. The study, completed in early 2007, identified potential safeguards measures and evaluated their effectiveness and impacts on operations. In addition, advanced instrumentation and techniques for verification purposes were identified and investigated. The scope of the work was framed by the International Atomic Energy Agency's (IAEA's) 2003 revised policy concerning the starting point of safeguards at uranium conversion facilities. Before this policy, only the final products of the uranium conversion plant were considered to be of composition and purity suitable for use in the nuclear fuel cycle and, therefore, subject to AEA safeguards control. DOE and CNEN have explored options for implementing the IAEA policy, although Brazil understands that the new policy established by the IAEA is beyond the framework of the Quadripartite Agreement of which it is one of the parties, together with Argentina, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, and the IAEA. This paper highlights the findings of this joint collaborative effort and identifies technical measures to strengthen international safeguards in NUCPs.

  19. Proof of Concept Simulations of the Multi-Isotope Process Monitor: An Online, Nondestructive, Near-Real-Time Safeguards Monitor for Nuclear Fuel Reprocessing Facilities

    SciTech Connect (OSTI)

    Orton, Christopher R.; Fraga, Carlos G.; Christensen, Richard; Schwantes, Jon M.

    2011-02-11

    The International Atomic Energy Agency (IAEA) will require the development of advanced technologies to effectively safeguard nuclear material at increasingly large-scale nuclear recycling facilities. Ideally, the envisioned technologies would be capable of nondestructive, near-real-time, autonomous process monitoring. This paper describes recent results from model simulations designed to test the Multi-Isotope Process (MIP) monitor, a novel approach to safeguarding reprocessing plants. The MIP monitor combines the detection of intrinsic gamma ray signatures emitted from process solutions with multivariate analysis to detect off-normal conditions in process streams nondestructively and in near-real-time. Three computer models including ORIGEN-ARP, AMUSE, and SYNTH were used in series to predict spent nuclear fuel composition, estimate element partitioning during separation, and simulate spectra from product and raffinate streams using a variety of gamma detectors, respectively. Simulations were generated for fuel with various irradiation histories and under a variety of plant operating conditions. Principal component analysis (PCA) was applied to the simulated gamma spectra to investigate pattern variations as a function of acid concentration, burnup, and cooling time. Hierarchical cluster analysis (HCA) and partial least squares (PLS) were also used in the analysis. The MIP monitor was found to be sensitive to induced variations of several operating parameters including distinguishing ¬Ī2.5% variation from normal process acid concentrations. The ability of PLS to predict burnup levels from simulated spectra was also demonstrated to be within 3.5% of measured values.

  20. Workshop materials from the 2nd international training course on physical protection of nuclear facilities and materials, Module 13

    SciTech Connect (OSTI)

    Martin, F. P.

    1980-04-01

    This course is intended for representatives of countries where nuclear power is being developed and whose responsibilities include the preparation of regulation and the design and evaluation of physical protection systems. This is the second of two volumes; the first volume is SAND-79-1090. (DLC)

  1. Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility

    SciTech Connect (OSTI)

    Not Available

    1992-07-01

    Volume 4 contains the following appendices: nuclear reactors at educational institutions in the United States; data sheets for nuclear reactors at educational institutions in the United States(operational reactors and shut-down reactors); supplemental data for Fort St. Vrain spent fuel; supplemental data for Peach Bottom 1 spent fuel; and supplemental data for Fast Flux Test Facility.

  2. Grout Isolation and Stabilization of Structures and Materials within Nuclear Facilities at the U.S. Department of Energy, Hanford Site, Summary - 12309

    SciTech Connect (OSTI)

    Phillips, S.J.; Phillips, M.; Etheridge, D.; Chojnacki, D.W.; Herzog, C.B.; Matosich, B.J.; Steffen, J.M.; Sterling, R.T.; Flaucher, R.H.; Lloyd, E.R.

    2012-07-01

    Per regulatory agreement and facility closure design, U.S. Department of Energy Hanford Site nuclear fuel cycle structures and materials require in situ isolation in perpetuity and/or interim physicochemical stabilization as a part of final disposal or interim waste removal, respectively. To this end, grout materials are being used to encase facilities structures or are being incorporated within structures containing hazardous and radioactive contaminants. Facilities where grout materials have been recently used for isolation and stabilization include: (1) spent fuel separations, (2) uranium trioxide calcining, (3) reactor fuel storage basin, (4) reactor fuel cooling basin transport rail tanker cars and casks, (5) cold vacuum drying and reactor fuel load-out, and (6) plutonium fuel metal finishing. Grout components primarily include: (1) portland cement, (2) fly ash, (3) aggregate, and (4) chemical admixtures. Mix designs for these typically include aggregate and non aggregate slurries and bulk powders. Placement equipment includes: (1) concrete piston line pump or boom pump truck for grout slurry, (2) progressive cavity and shearing vortex pump systems, and (3) extendable boom fork lift for bulk powder dry grout mix. Grout slurries placed within the interior of facilities were typically conveyed utilizing large diameter slick line and the equivalent diameter flexible high pressure concrete conveyance hose. Other facilities requirements dictated use of much smaller diameter flexible grout conveyance hose. Placement required direct operator location within facilities structures in most cases, whereas due to radiological dose concerns, placement has also been completed remotely with significant standoff distances. Grout performance during placement and subsequent to placement often required unique design. For example, grout placed in fuel basin structures to serve as interim stabilization materials required sufficient bearing i.e., unconfined compressive strength, to

  3. Moving hydrocarbons through portions of tar sands formations with a fluid

    DOE Patents [OSTI]

    Stegemeier, George Leo; Mudunuri, Ramesh Raju; Vinegar, Harold J.; Karanikas, John Michael; Jaiswal, Namit; Mo, Weijian

    2010-05-18

    A method for treating a tar sands formation is disclosed. The method includes heating a first portion of a hydrocarbon layer in the formation from one or more heaters located in the first portion. The heat is controlled to increase a fluid injectivity of the first portion. A drive fluid and/or an oxidizing fluid is injected and/or created in the first portion to cause at least some hydrocarbons to move from a second portion of the hydrocarbon layer to a third portion of the hydrocarbon layer. The second portion is between the first portion and the third portion. The first, second, and third portions are horizontally displaced from each other. The third portion is heated from one or more heaters located in the third portion. Hydrocarbons are produced from the third portion of the formation. The hydrocarbons include at least some hydrocarbons from the second portion of the formation.

  4. Utility of Social Modeling for Proliferation Assessment - Enhancing a Facility-Level Model for Proliferation Resistance Assessment of a Nuclear Enegry System

    SciTech Connect (OSTI)

    Coles, Garill A.; Brothers, Alan J.; Gastelum, Zoe N.; Olson, Jarrod; Thompson, Sandra E.

    2009-10-26

    The Utility of Social Modeling for Proliferation Assessment project (PL09-UtilSocial) investigates the use of social and cultural information to improve nuclear proliferation assessments, including nonproliferation assessments, Proliferation Resistance (PR) assessments, safeguards assessments, and other related studies. These assessments often use and create technical information about a host State and its posture towards proliferation, the vulnerability of a nuclear energy system (NES) to an undesired event, and the effectiveness of safeguards. This objective of this project is to find and integrate social and technical information by explicitly considering the role of cultural, social, and behavioral factors relevant to proliferation; and to describe and demonstrate if and how social science modeling has utility in proliferation assessment. This report describes a modeling approach and how it might be used to support a location-specific assessment of the PR assessment of a particular NES. The report demonstrates the use of social modeling to enhance an existing assessment process that relies on primarily technical factors. This effort builds on a literature review and preliminary assessment performed as the first stage of the project and compiled in PNNL-18438. [ T his report describes an effort to answer questions about whether it is possible to incorporate social modeling into a PR assessment in such a way that we can determine the effects of social factors on a primarily technical assessment. This report provides: 1. background information about relevant social factors literature; 2. background information about a particular PR assessment approach relevant to this particular demonstration; 3. a discussion of social modeling undertaken to find and characterize social factors that are relevant to the PR assessment of a nuclear facility in a specific location; 4. description of an enhancement concept that integrates social factors into an existing, technically

  5. TA-55: LANL Plutonium-Processing Facilities

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

    Facilities ¬Ľ TA-55: LANL Plutonium-Processing Facilities TA-55: LANL Plutonium-Processing Facilities TA-55 supports a wide range of national security programs that involve stockpile stewardship, plutonium processing, nuclear materials stabilization, materials disposition, nuclear forensics, nuclear counter-terrorism, and nuclear energy. ...the only fully operational, full capability plutonium facility in the nation. National Security At the Los Alamos National Laboratory (LANL), virtually all

  6. Nuclear Safety Information | Department of Energy

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

    Nuclear Safety Information Nuclear Safety Information Idaho National Laboratory's Advanced Test Reactor (ATR) | April 8, 2009 Idaho National Laboratory's Advanced Test Reactor (ATR) | April 8, 2009 Nuclear Facilities List and Map Nuclear Safety Regulatory Framework Summary Pamphlet, Nuclear Safety at the Department of Energy External Nuclear Safety Links Nuclear Regulatory Commission (NRC) Defense Nuclear Facilities Safety Board Contact Tom Staker

  7. Analysis of a Nuclear Accident: Fission and Activation Product Releases from the Fukushima Daiichi Nuclear Facility as Remote Indicators of Source Identification, Extent of Release, and State of Damaged Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Schwantes, Jon M.; Orton, Christopher R.; Clark, Richard A.

    2011-12-05

    Evidence of the release Pu from the Fukushima Daiichi nuclear power station to the local environment and surrounding communities and estimates on fraction of total fuel inventory released

  8. DOE G 226.1-1 Federal Line Management Oversight of Department of Energy Nuclear Facilities NNSA CRADs

    Office of Environmental Management (EM)

    CONTRACTOR TRAINING AND QUALIFICATION (T&Q) OBJECTIVE T&Q.1: The Site Office has oversight processes and procedures in place and has ensured that an effective and fully compliant Training and Qualification (T&Q) safety management program (SMP) has been implemented in support of site nuclear activities. CRITERIA 1. The Site Office has developed and implemented processes and procedures to effectively oversee contractor performance in this functional area (DOE O 226.1A; DOE O 426.2;

  9. Mission analysis report - deactivation facilities at Hanford

    SciTech Connect (OSTI)

    Lund, D.P.

    1996-09-27

    This document examines the portion of the Hanford Site Cleanup Mission that deals with facility deactivation. How facilities get identified for deactivation, how they enter EM-60 for deactivation, programmatic alternatives to perform facility deactivation, the deactivation process itself, key requirements and objectives associated with the deactivation process, and deactivation planning are discussed.

  10. Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities, Sections 15-19

    SciTech Connect (OSTI)

    Schneider, K.J.

    1982-09-01

    Information is presented under the following section headings: fuel reprocessing; spent fuel and high-level and transuranic waste storage; spent fuel and high-level and transuranic waste disposal; low-level and intermediate-level waste disposal; and, transportation of radioactive materials in the nuclear fuel cycle. In each of the first three sections a description is given on the mainline process, effluent processing and waste management systems, plant layout, and alternative process schemes. Safety information and a summary are also included in each. The section on transport of radioactive materials includes information on the transportation of uranium ore, uranium ore concentrate, UF/sub 6/, PuO/sub 2/ powder, unirradiated uranium and mixed-oxide fuel assemblies, spent fuel, solidified high-level waste, contact-handled transuranic waste, remote-handled transuranic waste, and low and intermediate level nontransuranic waste. A glossary is included. (JGB)

  11. Occupational radiation exposure at commercial nuclear power reactors and other facilities 1996: Twenty-ninth annual report. Volume 18

    SciTech Connect (OSTI)

    Thomas, M.L.; Hagemeyer, D.

    1998-02-01

    This report summarizes the occupational exposure data that are maintained in the US Nuclear Regulatory Commission`s (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 1996 annual reports submitted by six of the seven categories of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Since there are no geologic repositories for high level waste currently licensed, only six categories will be considered in this report. Annual reports for 1996 were received from a total of 300 NRC licensees, of which 109 were operators of nuclear power reactors in commercial operation. Compilations of the reports submitted by the 300 licensees indicated that 138,310 individuals were monitored, 75,139 of whom received a measurable dose. The collective dose incurred by these individuals was 21,755 person-cSv (person-rem){sup 2} which represents a 13% decrease from the 1995 value. The number of workers receiving a measurable dose also decreased, resulting in the average measurable dose of 0.29 cSv (rem) for 1996. The average measurable dose is defined to be the total collective dose (TEDE) divided by the number of workers receiving a measurable dose. These figures have been adjusted to account for transient reactor workers. Analyses of transient worker data indicate that 22,348 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient workers by multiple licensees. In 1996, the average measurable dose calculated from reported was 0.24 cSv (rem). The corrected dose distribution resulted in an average measurable dose of 0.29 cSv (rem).

  12. Occupational radiation exposure at commercial nuclear power reactors and other facilities 1994. Twenty-seventh annual report

    SciTech Connect (OSTI)

    Thomas, M.L.; Hagemeyer, D.

    1996-01-01

    This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission`s (NRC) Radiation Exposure Information and Reporting System (REIRS). Annual reports for 1994 were received from a total of 303 NRC licensees, of which 109 were operators of nuclear power reactors in commercial operation. Compilations of the reports submitted by the 303 licensees indicated that 152,028 individuals were monitored, 79,780 of whom received a measurable dose. The collective dose incurred by these individuals was 24,740 person-cSv (person-rem){sup 2} which represents a 15% decrease from the 1993 value. The number of workers receiving a measurable dose also decreased, resulting in the average measurable dose of 0.31 cSv (rem) for 1994. The average measurable dose is defined to be the total collective dose (TEDE) divided by the number of workers receiving a measurable dose. These figures have been adjusted to account for transient reactor workers. In 1994, the annual collective dose per reactor for light water reactor licensees (LWRs) was 198 person-cSv (person-rem). This represents a 18% decrease from the 1993 value of 242 person-cSv (person-rem). The annual collective dose per reactor for boiling water reactors (BWRs) was 327 person-cSv (person-rem) and, for pressurized water reactors (PWRs), it was 131 person-cSv (person-rem). Analyses of transient worker data indicate that 18,178 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient workers by multiple licensees. In 1994, the average measurable dose calculated from reported data was 0.28 cSv (rem). The corrected dose distribution resulted in an average measurable dose of 0.31 cSv (rem).

  13. Nuclear Safety | Department of Energy

    Energy Savers [EERE]

    Nuclear Power Facilities (2008) Nuclear Power Facilities (2008) Nuclear Power Facilities (2008) (408.42 KB) More Documents & Publications Front-end Nuclear Facilities (2008) Financial Institution Partnership Program - Commercial Technology Renewable Energy Generation Projects Issued: October 7, 2009 Transmission Infrastructure Investment Projects (2009) of Energy

    Regulatory Commission Regulatory and Licensing Matters Nuclear Regulatory Commission Regulatory and Licensing Matters GC-52

  14. The Radiochemical Analysis of Gaseous Samples (RAGS) apparatus for nuclear diagnostics at the National Ignition Facility (invited)

    SciTech Connect (OSTI)

    Shaughnessy, D. A.; Velsko, C. A.; Jedlovec, D. R.; Yeamans, C. B.; Moody, K. J.; Tereshatov, E.; Stoeffl, W.; Riddle, A.

    2012-10-15

    The Radiochemical Analysis of Gaseous Samples (RAGS) diagnostic apparatus was recently installed at the National Ignition Facility (NIF). Following a NIF shot, RAGS is used to pump the gas load from the NIF chamber for purification and isolation of the noble gases. After collection, the activated gaseous species are counted via gamma spectroscopy for measurement of the capsule areal density and fuel-ablator mix. Collection efficiency was determined by injecting a known amount of {sup 135}Xe into the NIF chamber, which was then collected with RAGS. Commissioning was performed with an exploding pusher capsule filled with isotopically enriched {sup 124}Xe and {sup 126}Xe added to the DT gas fill. Activated xenon species were recovered post-shot and counted via gamma spectroscopy. Results from the collection and commissioning tests are presented. The performance of RAGS allows us to establish a noble gas collection method for measurement of noble gas species produced via neutron and charged particle reactions in a NIF capsule.

  15. Facilities, Partnerships, and Resources

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

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

  16. Nuclear recycling | Argonne National Laboratory

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

    Nuclear recycling Pyroprocessing facilities 1 of 8 Pyroprocessing facilities Frances Dozier conducts pyroprocessing research inside a glovebox at Argonne National Laboratory....

  17. Occupational radiation exposure at commercial nuclear power reactors and other facilities 1995: Twenty-eighth annual report. Volume 17

    SciTech Connect (OSTI)

    Thomas, M.L.; Hagemeyer, D.

    1997-01-01

    This report summarizes the occupational exposure data that are maintained in the US Nuclear Regulatory Commission`s (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 1995 annual reports submitted by six of the seven categories of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Since there are no geologic repositories for high-level waste currently licensed, only six categories will be considered in this report. In 1995, the annual collective dose per reactor for light water reactor licensees (LWRs) was 199 person-cSv (person-rem). This is the same value that was reported for 1994. The annual collective dose per reactor for boiling water reactors (BWRs) was 256 person-cSv (person-rem) and, for pressurized water reactors (PWRs), it was 170 person-cSv (person-rem). Analyses of transient worker data indicate that 17,153 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient workers by multiple licensees. In 1995, the average measurable dose calculated from reported data was 0.26 cSv (rem). The corrected dose distribution resulted in an average measurable dose of 0.32 cSv (rem).

  18. About the Facility

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

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

  19. Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

    SciTech Connect (OSTI)

    Coenenberg, J.G.

    1997-08-15

    The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

  20. Nuclear Safety | Department of Energy

    Office of Environmental Management (EM)

    Criticality Safety The Nuclear Facility Safety Program establishes and maintains the DOE requirements for nuclear criticality safety. The DOE detailed requirements for criticality ...

  1. Kauai Test Facility

    SciTech Connect (OSTI)

    Hay, R.G.

    1982-01-01

    The Kauai Test Facility (KTF) is a Department of Energy rocket launch facility operated by Sandia National Laboratories. Originally it was constructed in support of the high altitude atmospheric nuclear test phase of operation Dominic in the early 1960's. Later, the facility went through extensive improvement and modernization to become an integral part of the Safeguard C readiness to resume nuclear testing program. Since its inception and build up, in the decade of the sixties and the subsequent upgrades of the seventies, range test activities have shifted from full scale test to emphasis on research and development of materials and components, and to making high altitude scientific measurements. Primarily, the facility is intended to be utilized in support of development programs at the DOE weapons laboratories, however, other organizations may make use of the facility on a non-interface basis. The physical components at KTF and their operation are described.

  2. Environmental consequences of postulate plutonium releases from Atomics International's Nuclear Materials Development Facility (NMDF), Santa Susana, California, as a result of severe natural phenomena

    SciTech Connect (OSTI)

    Jamison, J.D.; Watson, E.C.

    1982-02-01

    Potential environmental consequences in terms of radiation dose to people are presented for postulated plutonium releases caused by severe natural phenomena at the Atomics International's Nuclear Materials Development Facility (NMDF), in the Santa Susana site, California. The severe natural phenomena considered are earthquakes, tornadoes, and high straight-line winds. Plutonium deposition values are given for significant locations around the site. All important potential exposure pathways are examined. The most likely 50-year committed dose equivalents are given for the maximum-exposed individual and the population within a 50-mile radius of the plant. The maximum plutonium deposition values likely to occur offsite are also given. The most likely calculated 50-year collective committed dose equivalents are all much lower than the collective dose equivalent expected from 50 years of exposure to natural background radiation and medical x-rays. The most likely maximum residual plutonium contamination estimated to be deposited offsite following the earthquake, and the 150-mph and 170-mph tornadoes are above the Environmental Protection Agency's (EPA) proposed guideline for plutonium in the general environment of 0.2 ..mu..Ci/m/sup 2/. The deposition values following the 110-mph and the 130-mph tornadoes are below the EPA proposed guideline.

  3. ARM - SGP Extended Facility

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

    Extended Facility SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration...

  4. ARM - SGP Intermediate Facility

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

    Intermediate Facility SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration...

  5. ARM - SGP Central Facility

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

    Central Facility SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration...

  6. Spent Nuclear Fuel Project Safety Management Plan

    SciTech Connect (OSTI)

    Garvin, L.J.

    1996-02-01

    The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities.

  7. Facility Safety Policy, Guidance & Reports | Department of Energy

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

    Facility Safety Policy, Guidance & Reports Facility Safety Policy, Guidance & Reports The Office of Nuclear Facility Safety Programs within the U.S. Department of Energy's (DOE) Environment, Health, Safety and Security organization, establishes nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities. In addition, establishes requirements for facility design and operation for facility-wide hazards that are not unique to

  8. Assessment of Nuclear Safety Culture at the Salt Waste Processing...

    Office of Environmental Management (EM)

    Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility ... of Nuclear Safety Culture at the Salt Waste Processing Facility Project Table of ...

  9. Study Builds Knowledge of Nuclear Waste Glass, Provides Insight...

    Office of Environmental Management (EM)

    Study Builds Knowledge of Nuclear Waste Glass, Provides Insight to Facility Design Study Builds Knowledge of Nuclear Waste Glass, Provides Insight to Facility Design April 14, 2016 ...

  10. Data Management Resources at the Office of Science User Facilities...

    Office of Science (SC) Website

    ... for Advanced Accelerator Experimental Tests (FACET) SLAC Link External link Accelerator Test Facility (ATF) BNL Link External link Nuclear Physics (NP) Facility Host Institution ...

  11. Solar Test Facility Upgrades Complete, Leading to Better Sandia...

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

    Test Facility Upgrades Complete, Leading to Better Sandia Capabilities to Support Power ... Applications National Solar Thermal Test Facility Nuclear Energy Systems ...

  12. Software quality assurance at the weapons engineering tritium facility

    SciTech Connect (OSTI)

    Hart, O.

    1997-11-01

    This report contains viewgraphs on the evolution of software quality assurance at the Weapons Engineering Tritium Facility in relation to DOE`s requirements for nuclear facilities.

  13. Salt Waste Processing Facility Fact Sheet | Department of Energy

    Office of Environmental Management (EM)

    Waste Management Tank Waste and Waste Processing Salt Waste Processing Facility Fact Sheet Salt Waste Processing Facility Fact Sheet Nuclear material production operations at ...

  14. Huntington Resource Recovery Facility Biomass Facility | Open...

    Open Energy Info (EERE)

    Resource Recovery Facility Biomass Facility Jump to: navigation, search Name Huntington Resource Recovery Facility Biomass Facility Facility Huntington Resource Recovery Facility...

  15. Wheelabrator Sherman Energy Facility Biomass Facility | Open...

    Open Energy Info (EERE)

    Sherman Energy Facility Biomass Facility Jump to: navigation, search Name Wheelabrator Sherman Energy Facility Biomass Facility Facility Wheelabrator Sherman Energy Facility Sector...

  16. Operational Philosophy for the Advanced Test Reactor National Scientific User Facility

    SciTech Connect (OSTI)

    J. Benson; J. Cole; J. Jackson; F. Marshall; D. Ogden; J. Rempe; M. C. Thelen

    2013-02-01

    In 2007, the Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF). At its core, the ATR NSUF Program combines access to a portion of the available ATR radiation capability, the associated required examination and analysis facilities at the Idaho National Laboratory (INL), and INL staff expertise with novel ideas provided by external contributors (universities, laboratories, and industry). These collaborations define the cutting edge of nuclear technology research in high-temperature and radiation environments, contribute to improved industry performance of current and future light-water reactors (LWRs), and stimulate cooperative research between user groups conducting basic and applied research. To make possible the broadest access to key national capability, the ATR NSUF formed a partnership program that also makes available access to critical facilities outside of the INL. Finally, the ATR NSUF has established a sample library that allows access to pre-irradiated samples as needed by national research teams.

  17. Testing and Performance Validation of a Sensitive Gamma Ray Camera Designed for Radiation Detection and Decommissioning Measurements in Nuclear Facilities-13044

    SciTech Connect (OSTI)

    Mason, John A.; Looman, Marc R.; Poundall, Adam J.; Towner, Antony C.N.; Creed, Richard; Pancake, Daniel

    2013-07-01

    This paper describes the measurements, testing and performance validation of a sensitive gamma ray camera designed for radiation detection and quantification in the environment and decommissioning and hold-up measurements in nuclear facilities. The instrument, which is known as RadSearch, combines a sensitive and highly collimated LaBr{sub 3} scintillation detector with an optical (video) camera with controllable zoom and focus and a laser range finder in one detector head. The LaBr{sub 3} detector has a typical energy resolution of between 2.5% and 3% at the 662 keV energy of Cs-137 compared to that of NaI detectors with a resolution of typically 7% to 8% at the same energy. At this energy the tungsten shielding of the detector provides a shielding ratio of greater than 900:1 in the forward direction and 100:1 on the sides and from the rear. The detector head is mounted on a pan/tile mechanism with a range of motion of ¬Ī180 degrees (pan) and ¬Ī90 degrees (tilt) equivalent to 4 ŌÄ steradians. The detector head with pan/tilt is normally mounted on a tripod or wheeled cart. It can also be mounted on vehicles or a mobile robot for access to high dose-rate areas and areas with high levels of contamination. Ethernet connects RadSearch to a ruggedized notebook computer from which it is operated and controlled. Power can be supplied either as 24-volts DC from a battery or as 50 volts DC supplied by a small mains (110 or 230 VAC) power supply unit that is co-located with the controlling notebook computer. In this latter case both power and Ethernet are supplied through a single cable that can be up to 80 metres in length. If a local battery supplies power, the unit can be controlled through wireless Ethernet. Both manual operation and automatic scanning of surfaces and objects is available through the software interface on the notebook computer. For each scan element making up a part of an overall scanned area, the unit measures a gamma ray spectrum. Multiple

  18. Listing of Defense Nuclear Facilities

    Energy Savers [EERE]

    Pilot Project Portsmouth Gaseous Diffusion Plant Paducah Gaseous Diffusion Plant Brookhaven National Laboratory Argonne National Laboratory 1 On August 23, 2010, the Nevada ...

  19. Hallam Nuclear Power Facility, NE

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

    25. Baker and Williams Warehouses, NY 1993 2008 26. Falls City, TX 1994 2009 27. Grand Junction Mill Tailings Site, CO 1994 2009 28. Monument Valley, AZ 1994 2010 29. Salton Sea ...

  20. Training of nuclear facility personnel

    SciTech Connect (OSTI)

    Not Available

    1981-04-01

    Separate abstracts are included for each of the papers presented concerning certification and standards; operations training; the human element; and non-licensed training.

  1. Nuclear reactor

    DOE Patents [OSTI]

    Thomson, Wallace B.

    2004-03-16

    A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

  2. Byron Extended Facility

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

    Byron Extended Facility Map

  3. Ashton Extended Facility

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

    Ashton Extended Facility Map

  4. User Facilities

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

    User Facilities User Facilities User facility agreements allow Los Alamos partners and other entities to conduct research at our unique facilities. In 2011, LANL hosted more than 1,200 users at CINT, LANSCE, and NHMFL. Users came from across the DOE complex, from international academia, and from industrial companies from 45 states across the U.S. Unique world-class user facilities foster rich research opportunities Through its technology transfer efforts, LANL can implement user facility

  5. TQP | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    TQP NNSA's safety office accredited and recognized for leadership in safe operation of defense nuclear facilities Part of NNSA's commitment to maintaining the nation's safe, secure, and effective nuclear deterrent are relentlessly high standards for technically capable nuclear enterprise personnel qualifications for all aspects of Defense Nuclear Facility operations. In December 2015, the Department of Energy

  6. accreditation | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    accreditation NNSA's safety office accredited and recognized for leadership in safe operation of defense nuclear facilities Part of NNSA's commitment to maintaining the nation's safe, secure, and effective nuclear deterrent are relentlessly high standards for technically capable nuclear enterprise personnel qualifications for all aspects of Defense Nuclear Facility operations. In December 2015, the Department of Energy... Savannah River Analytical Laboratories Achieve International Standard

  7. Nuclear Physics Program

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

    Nuclear Physics Program HALL A Hall A wide shot of detectors Scientists from across the country and around the world use the Thomas Jefferson National Accelerator Facility to ...

  8. Cell Prototyping Facility

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

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

  9. Central Receiver Test Facility

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

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

  10. Continuous Electron Beam Accelerator Facility (CEBAF) | U.S. DOE Office of

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

    Science (SC) Continuous Electron Beam Accelerator Facility (CEBAF) Nuclear Physics (NP) NP Home About Research Facilities User Facilities Argonne Tandem Linac Accelerator System (ATLAS) Continuous Electron Beam Accelerator Facility (CEBAF) Relativistic Heavy Ion Collider (RHIC) Project Development Isotope Program Facilities Science Highlights Benefits of NP Funding Opportunities Nuclear Science Advisory Committee (NSAC) Community Resources Contact Information Nuclear Physics U.S. Department

  11. Civilian Nuclear Program

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

    Civilian Nuclear Program Civilian Nuclear Program Los Alamos is committed to using its advanced nuclear expertise and unique facilities to meet the civilian nuclear national security demands of the future. CONTACT US Program Director Venkateswara Rao Dasari (Rao) (505) 667-5098 Email Los Alamos partners extensively with other laboratories, universities, industry, and the international nuclear community to address real-world technical challenges The Civilian Nuclear Program is the focal point for

  12. Incentives for the Department's Facility Representative Program,

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

    12/17/1998 | Department of Energy Incentives for the Department's Facility Representative Program, 12/17/1998 Incentives for the Department's Facility Representative Program, 12/17/1998 The Department's Revised Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 93-3 has once again underscored the Department's commitment to maintaining the technical capability necessary to safely manage and operate our defense nuclear facilities. Attracting and retaining highly

  13. Facilities | U.S. DOE Office of Science (SC)

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

    Facilities Nuclear Physics (NP) NP Home About Research Facilities User Facilities Project Development Isotope Program Facilities Science Highlights Benefits of NP Funding Opportunities Nuclear Science Advisory Committee (NSAC) Community Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301) 903-3833 E: Email Us More Information ¬Ľ Facilities Print Text Size: A A A FeedbackShare

  14. Cold vacuum drying facility design requirements

    SciTech Connect (OSTI)

    IRWIN, J.J.

    1999-07-01

    This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

  15. General Engineer/Physical Scientist (Facility Representative)

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will serve as an on-site senior technical representative, and Facility Representative, with responsibility for evaluating contractor environmental, nuclear...

  16. Facility Safety - DOE Directives, Delegations, and Requirements

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

    facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH)...

  17. Neutron Detectors for Detection of Nuclear Materials at LANL...

    Office of Science (SC) Website

    Neutron Detectors for Detection of Nuclear Materials at LANL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Applications of Nuclear ...

  18. User Facilities

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

    User Facilities User Facilities A new research frontier awaits! Our door is open, and we thrive on mutually beneficial partnerships and collaborations that drive innovations and new technologies. Unique world-class user facilities foster rich research opportunities Through its technology transfer efforts, Los Alamos National Laboratory can implement user facility agreements that allow its partners and other entities to conduct research at many of its unique facilities. While our largest user

  19. President Reagan Calls for a National Spent Fuel Storage Facility |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration | (NNSA) Reagan Calls for a National Spent Fuel Storage Facility President Reagan Calls for a National Spent Fuel Storage Facility Washington, DC The Reagan Administration announces a nuclear energy policy that anticipates the establishment of a facility for the storage of high-level radioactive waste and lifts the ban on commercial reprocessing of nuclear fuel

  20. Interactive Simulation of Nuclear Materials Safeguards and Security

    Energy Science and Technology Software Center (OSTI)

    1994-03-14

    THIEF is an interactive computer simulation or computer game of the safeguards and security (S&S) systems of a nuclear facility. The user is placed in the role of a non-violent insider attempting to remove special nuclear material from the facility. All portions of the S&S system that are relevant to the non-violent insider threat are included. The computer operates the S&S systems and attempts to detect the loss of the nuclear material. Both the physicalmore¬†¬Ľ protection system and the materials control and accounting system are modeled. The description of the facility and its S&S systems are defined by the user with the aid of an input module. All aspects of the facility description are provided by the user. The program has a custom graphical user interface to facilitate its use by people with limited computer experience. The custom interface also allows it to run on relatively small computer systems.¬ę¬†less