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Sample records for frs reporting criteria

  1. Nuclear Safety Reporting Criteria | Department of Energy

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

    Reporting Criteria Nuclear Safety Reporting Criteria January 1, 2012 Nuclear Safety Noncompliances Associated With Occurrences (DOE Order 232.2) These tables provide the criteria ...

  2. Security Enforcement Reporting Criteria | Department of Energy

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

    This document provides information and criteria for reporting classified information ... be found in the Office of Health, Safety and Security's Enforcement Coordinator Handbook. ...

  3. Worker Safety and Health Reporting Criteria | Department of Energy

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

    Worker Safety and Health Reporting Criteria Worker Safety and Health Reporting Criteria January 1, 2012 Worker Safety and Health Noncompliances Associated With Occurrences(DOE Order 232.2) These tables provide the criteria for reporting worker safety and health noncompliances into the Department of Energy's Noncompliance Tracking System (NTS). A more detailed description of the NTS reporting criteria and expectations can be found in the Office of Health, Safety and Security's Enforcement

  4. Development of subsidence damage criteria. Final report

    SciTech Connect (OSTI)

    Bhattacharya, S.; Singh, M.M.

    1985-10-01

    In the process of coal mining it is certain that some degree of disturbance of the overlying strata and consequent subsidence of the surface will result. The problem of land subsidence has faced engineers and geologists for many years and, when widespread movements and damage to surface structures occurred, systematic investigations were undertaken. The term subsidence, as used in the report, implies the total phenomenon of surface effects associated with the mining of minerals, and not only vertical displacement of the surface as is sometimes inferred in the literature.

  5. Reportable Nuclide Criteria for ORNL Waste Management Activities - 13005

    SciTech Connect (OSTI)

    McDowell, Kip; Forrester, Tim; Saunders, Mark Edward

    2013-01-01

    The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed a reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of this criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration.

  6. Reportable Nuclide Criteria for ORNL Radioactive Waste Management Activities - 13005

    SciTech Connect (OSTI)

    McDowell, Kip; Forrester, Tim; Saunders, Mark

    2013-07-01

    The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of these criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration. (authors)

  7. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    SciTech Connect (OSTI)

    Not Available

    1993-03-01

    The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III.

  8. Water quality criteria for colored smokes: Solvent Yellow 33, Final report. [Contains glossary

    SciTech Connect (OSTI)

    Davidson, K.A.; Hovatter, P.S.

    1987-11-01

    The available data on the environmental fate, aquatic toxicity, and mammalian toxicity of Solvent Yellow 33, a quinoline dye used in colored smoke grenades, were reviewed. The US Environmental Protection Agency (USEPA) guidelines were used in an attempt to generate water quality criteria for the protection of aquatic life and its use and of human health. 87 refs., 2 figs., 13 tabs.

  9. Aspects of Apache's Acquisition of Mariner Energy and Selected Devon Energy Assets

    Reports and Publications (EIA)

    2010-01-01

    The Energy Information Administration reviews mergers, acquisitions, and alliances by companies that are respondents to Form EIA-28 (Financial Reporting System (FRS)), or that result in a company that meets the FRS reporting criteria.

  10. Criteria for choosing among competing alternatives for ATBM defenses. Final report

    SciTech Connect (OSTI)

    1995-05-01

    The Center for Strategic and International Studies (CSIS) established an executive review panel to assess the paper written by Peter Zimmerman. The panel consisted of experts on theater missile defenses, U.S. relations with former Soviet Union/Russia, the ABM compliance issues. The panel was NOT able to reach a consensus on the issues raised by the paper. NOR was it able to validate the criteria developed therein. A majority of the panel took exception to many to the facts, findings, and conclusions of the paper. The major points under dispute are: the characterization of the threat, the definition of technical risk, system performance requirements, limits on ATBM systems imposed by the ABM Treaty, Congressional views, cost and IOC dates. The issues are discussed in detail in this review.

  11. K Basin sludge packaging design criteria (PDC) and safety analysis report for packaging (SARP) approval plan

    SciTech Connect (OSTI)

    Brisbin, S.A.

    1996-03-06

    This document delineates the plan for preparation, review, and approval of the Packaging Design Crieteria for the K Basin Sludge Transportation System and the Associated on-site Safety Analysis Report for Packaging. The transportation system addressed in the subject documents will be used to transport sludge from the K Basins using bulk packaging.

  12. Geology and recognition criteria for uranium deposits of the quartz-pebble conglomerate type. Final report

    SciTech Connect (OSTI)

    Button, A.; Adams, S.S.

    1981-03-01

    This report is concerned with Precambrian uraniferous conglomerates. This class of deposit has been estimated to contain between approximately 16 and 35 percent of the global uranium reserve in two rather small areas, one in Canada, the other in South Africa. Similar conglomerates, which are often gold-bearing, are, however, rather widespread, being found in parts of most Precambrian shield areas. Data have been synthesized on the geologic habitat and character of this deposit type. The primary objective has been to provide the most relevant geologic observations in a structural fashion to allow resource studies and exploration to focus on the most prospective targets in the shortest possible time.

  13. First report on non-thermal plasma reactor scaling criteria and optimization models

    SciTech Connect (OSTI)

    Rosocha, L.A.; Korzekwa, R.A.

    1998-01-13

    The purpose of SERDP project CP-1038 is to evaluate and develop non-thermal plasma (NTP) reactor technology for Department of Defense (DoD) air emissions control applications. The primary focus is on oxides of nitrogen (NO{sub x}) and a secondary focus on hazardous air pollutants (HAPs), especially volatile organic compounds (VOCs). Example NO{sub x} sources are jet engine test cells (JETCs) and diesel engine powered electrical generators. Example VOCs are organic solvents used in painting, paint stripping, and parts cleaning. To design and build NTP reactors that are optimized for particular DoD applications, one must understand the basic decomposition chemistry of the target compound(s) and how the decomposition of a particular chemical species depends on the air emissions stream parameters and the reactor operating parameters. This report is intended to serve as an overview of the subject of reactor scaling and optimization and will discuss the basic decomposition chemistry of nitric oxide (NO) and two representative VOCs, trichloroethylene and carbon tetrachloride, and the connection between the basic plasma chemistry, the target species properties, and the reactor operating parameters (in particular, the operating plasma energy density). System architecture, that is how NTP reactors can be combined or ganged to achieve higher capacity, will also be briefly discussed.

  14. Evaluation Criteria

    Broader source: Energy.gov [DOE]

    Applications must meet the basic eligibility criteria. Final decisions regarding eligibility and compliance will be made by the Office of Energy Efficiency and Renewable Energy (EERE).

  15. Regulatory Analysis on Criteria

    Office of Scientific and Technical Information (OSTI)

    Regulatory Analysis on Criteria for the Release of Patients Administered Radio active Material Final Report Manuscript Completed April 1996 Date Published: February 1997 S . Schneider, S . A. McGuire Division of Regulatory Applications Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 DISCLArmER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency

  16. Technical Qualification Program Accreditation Objectives and Criteria |

    Energy Savers [EERE]

    Department of Energy Objectives and Criteria Technical Qualification Program Accreditation Objectives and Criteria The program clearly identifies and documents the process used to demonstrate employee technical competence. PDF icon TQP Accreditation Objectives and Criteria More Documents & Publications Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 Technical

  17. Membership Criteria: Better Buildings Residential Network | Department of

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

    Energy Membership Criteria: Better Buildings Residential Network Membership Criteria: Better Buildings Residential Network Membership Criteria: Better Buildings Residential Network of the U.S. Department of Energy. PDF icon Membership Criteria More Documents & Publications Better Buildings Residential Network Orientation Better Buildings Residential Network Reporting and Benefits FAQ How Can the Network Meet Your Needs?

  18. Acceptance Criteria - Hanford Site

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

    G and I clarified requirements throughout the appendices. Appendix I, Table I-1 in the Waste Acceptance Criteria for the "Payload Container Description" removed "208-L (55 gal)...

  19. Fire protection design criteria

    SciTech Connect (OSTI)

    1997-03-01

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

  20. Societal-Equity-Enhancing Criteria and Facility-Host Incentives Supporting Five Key Elements in the January 2012 Blue Ribbon Commission Report - 13015

    SciTech Connect (OSTI)

    Eriksson, Leif G.; Dials, George E.; George, Critz H.

    2013-07-01

    In February 2009, the Obama Administration announced it would abandon USA's only candidate SNF/HLW-disposal facility since 1987. In 2010, all related activities were stopped and the Blue Ribbon Commission on America's Nuclear Future was established 'to recommend a new strategy for managing the back end of the nuclear fuel cycle', which it did in January 2012, emphasizing eight key elements. However, Key Element 1, 'A new, consent-based approach to siting future nuclear facilities', is qualitative/indeterminate rather than quantitative/measurable. It is thus highly-susceptible to semantic permutations that could extend rather than, as intended, expedite the siting of future nuclear facilities unless it also defines: a) Whose consent is needed?; and b) What constitutes consent? The following 'generic', radiation-risk- and societal-equity-based criteria address these questions: 1. Identify areas affected by projected radiation and other health risks from: a. The proposed nuclear facility (facility stakeholders); and b. The related nuclear-materials-transportation routes (transportation stakeholders); then 2. Surround each stakeholder area with a buffer zone and use this enlarged foot print to identify: a. Stakeholder hosts; and b. Areas not hosting any stakeholder category (interested parties). 3. Define 'consent-based' as being at least 60 percent of the 'population' in the respective stakeholder category and apply this yardstick to both 'in favor' and 'against' votes. Although criteria 1 and 2 also need facility-based definitions to make Key Element 1 measurable, the described siting approach, augmented by related facility-host incentives, would expedite the schedule and reduce the cost for achieving Key Elements 4-6 and 8, politics permitting. (authors)

  1. Criteria for the recognition of pedogenic/supergene and nonpedogenic/hypogene deposits and their relationship to the origin of calcite/opal deposits at Yucca Mountain. Special report No. 14

    SciTech Connect (OSTI)

    Hill, C.A.; Schluter, C.M.; Monger, H.C.

    1993-10-01

    This study is part of the research program of the Yucca Mountain Project intended to provide the State of Nevada with a detailed assessment of the geology and geochemistry of Yucca Mountain and adjacent regions. The purpose of this report is to try and establish criteria for the recognition of pedogenic/supergene deposits of calcite/opal versus non-pedogenic/hypogene deposits of calcite/opal. Far from being of esoteric concern, this subject is of paramount importance to the pedogenic-hypogene debate which rages around the suitability of Yucca Mountain as a high-level radioactive waste repository site.

  2. Fusion Blanket Coolant Section Criteria, Methodology, and Results...

    Office of Scientific and Technical Information (OSTI)

    Fusion Blanket Coolant Section Criteria, Methodology, and Results Citation Details ... DOE Contract Number: AC52-07NA27344 Resource Type: Technical Report Research Org: Lawrence ...

  3. Summary of the Advanced Reactor Design Criteria (ARDC) Phase 1 Activities, including the development of the Final Report and the Advanced Reactor Technology Training

    SciTech Connect (OSTI)

    Holbrook, Mark R.

    2015-04-01

    Provide summary of the Phase 1 activities (Develop Final Report and Conduct Advanced Reactor Technology Training) that were completed in Fiscal Year 2015.

  4. Criteria for the development and use of the methodology for environmentally-acceptable fossil energy site evaluation and selection. Volume 2. Final report

    SciTech Connect (OSTI)

    Eckstein, L.; Northrop, G.; Scott, R.

    1980-02-01

    This report serves as a companion document to the report, Volume 1: Environmentally-Acceptable Fossil Energy Site Evaluation and Selection: Methodology and Users Guide, in which a methodology was developed which allows the siting of fossil fuel conversion facilities in areas with the least environmental impact. The methodology, known as SELECS (Site Evaluation for Energy Conversion Systems) does not replace a site specific environmental assessment, or an environmental impact statement (EIS), but does enhance the value of an EIS by thinning down the number of options to a manageable level, by doing this in an objective, open and selective manner, and by providing preliminary assessment and procedures which can be utilized during the research and writing of the actual impact statement.

  5. Geology and recognition criteria for veinlike uranium deposits of the lower to middle Proterozoic unconformity and strata-related types. Final report

    SciTech Connect (OSTI)

    Dahlkamp, F.J.; Adams, S.S.

    1981-01-01

    The discovery of the Rabbit Lake deposit, Saskatchewan, in 1968 and the East Alligator Rivers district, Northern Territory, Australia, in 1970 established the Lower-Middle Proterozoic veinlike-type deposits as one of the major types of uranium deposits. The term veinlike is used in order to distinguish it from the classical magmatic-hydrothermal vein or veintype deposits. The veinlike deposits account for between a quarter and a third of the Western World's proven uranium reserves. Lower-Middle Proterozoic veinlike deposits, as discussed in this report include several subtypes of deposits, which have some significantly different geologic characteristics. These various subtypes appear to have formed from various combinations of geologic processes ranging from synsedimentary uranium precipitation through some combination of diagenesis, metamorphism, metasomatism, weathering, and deep burial diagenesis. Some of the deposit subtypes are based on only one or two incompletely described examples; hence, even the classification presented in this report may be expected to change. Geologic characteristics of the deposits differ significantly between most districts and in some cases even between deposits within districts. Emphasis in this report is placed on deposit descriptions and the interpretations of the observers.

  6. Performance Criteria and Evaluation System

    Energy Science and Technology Software Center (OSTI)

    1992-06-18

    The Performance Criteria and Evaluation System (PCES) was developed in order to make a data base of criteria accessible to radiation safety staff. The criteria included in the package are applicable to occupational radiation safety at DOE reactor and nonreactor nuclear facilities, but any data base of criteria may be created using the Criterion Data Base Utiliity (CDU). PCES assists personnel in carrying out oversight, line, and support activities.

  7. IHE material qualification tests description and criteria

    SciTech Connect (OSTI)

    Slape, R J

    1984-06-01

    This report describes the qualification tests presently being used at Pantex Plant, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory that are required by the Department of Energy prior to the approval for an explosive as an Insensitive High Explosive (IHE) material. The acceptance criteria of each test for IHE qualification is also discussed. 5 references, 10 figures.

  8. FHR Generic Design Criteria

    SciTech Connect (OSTI)

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

    2012-06-01

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

  9. FHR Generic Design Criteria

    SciTech Connect (OSTI)

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

    2012-06-15

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

  10. EXPO Award Criteria - Hanford Site

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

    Award Criteria About Us Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO EXPO Award Criteria Email Email Page | Print Print Page |Text Increase Font Size Decrease Font Size WRPS won the awards for Most Interactive and Best Overall booth! WRPS won the awards for Most Interactive and Best Overall booth! WCH won the award

  11. FTCP Assessment Guidance and Criteria

    Broader source: Energy.gov [DOE]

    This document establishes the guidance and criteria for conducting internal and independent Federal Technical Capability Assessments within the Department. The requirements of this document are applicable to those organizations having safety responsibilities for defense nuclear facilities. This includes both headquarters and field organizations. Regardless of the type of assessment conducted, the objectives and criteria within this document are used as a basis for the assessment. Use of consistent objectives and criteria is necessary to establish baselines and to track and trend performance.

  12. (Basic radiation protection criteria). Final report

    SciTech Connect (OSTI)

    Ney, W.R.

    1982-12-03

    Progress in the following areas directly related to nuclear waste management is summarized: (1) a radiation protection system based on risk per rad of dose; (2) assessment of the accumulation and biological significance of industrial waste discharges and estimation of concentrations present in the environment; (3) assessment of exposure resulting from nuclear power; (4) internal emitter standards; (5) human radiation exposure experience; (6) the identification of national needs related to the estimation of exposure of the public from ionizing radiation; and (7) acceptable risk for management of radioactive waste. (ACR)

  13. Electronic Records Management Software Applications Design Criteria...

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

    Electronic Records Management Software Applications Design Criteria Standard Electronic Records Management Software Applications Design Criteria Standard This Standard is reissued ...

  14. A review of proposed Glen Canyon Dam interim operating criteria

    SciTech Connect (OSTI)

    LaGory, K.; Hlohowskyj, I.; Tomasko, D.; Hayse, J.; Durham, L.

    1992-04-01

    Three sets of interim operating criteria for Glen Canyon Dam on the Colorado River have been proposed for the period of November 1991, to the completion of the record of decision for the Glen Canyon Dam environmental impact statement (about 1993). These criteria set specific limits on dam releases, including maximum and minimum flows, up-ramp and down-ramp rates, and maximum daily fluctuation. Under the proposed interim criteria, all of these parameters would be reduced relative to historical operating criteria to protect downstream natural resources, including sediment deposits, threatened and endangered fishes, trout, the aquatic food base, and riparian plant communities. The scientific bases of the three sets of proposed operating criteria are evaluated in the present report:(1) criteria proposed by the Research/Scientific Group, associated with the Glen Canyon Environmental Studies (GCES); (2) criteria proposed state and federal officials charged with managing downstream resources; and (3) test criteria imposed from July 1991, to November 1991. Data from Phase 1 of the GCES and other sources established that the targeted natural resources are affected by dam operations, but the specific interim criteria chosen were not supported by any existing studies. It is unlikely that irreversible changes to any of the resources would occur over the interim period if historical operating criteria remained in place. It is likely that adoption of any of the sets of proposed interim operating criteria would reduce the levels of sediment transport and erosion below Glen Canyon Dam; however, these interim criteria could result in some adverse effects, including the accumulation of debris at tributary mouths, a shift of new high-water-zone vegetation into more flood-prone areas, and further declines in vegetation in the old high water zone.

  15. Evaluation Criteria for PDIL Proposal

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

    Criteria for PDIL Proposal The selection/decision criteria used by the NCPV Business Development Team are the following: 1. Quality and Relevance of the Proposed Technical Plan (30%) * Technology impact with industry and likelihood of success. Demonstrated benefits of success to both the proposer and NREL to meet the DOE SunShot goals. * Proposed task descriptions and time line. Clear demonstration of entrance and exit strategies in the PDIL. * Extent to which the Proposer and NREL can rapidly

  16. Assessment B - Program Criteria | Department of Energy

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

    B - Program Criteria Assessment B - Program Criteria PDF icon Microsoft Word - Assessment-B-ProgramCriteria More Documents & Publications ATTACHMENT A - CHECKLIST FOR SELF ASSESSMENT Assessment C-Site Visit Protocol EERE Program Management Guide - Chapter 2

  17. Guidelines Establishing Criteria for Excluding Buildings from...

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

    by the Energy Policy Act of 2005 Guidelines Establishing Criteria for Excluding ... This document contains the Guidelines Establishing Criteria for Excluding Buildings from ...

  18. Durability-Based Design Criteria for a Chopped-Glass-Fiber Automotive Structural Composite

    SciTech Connect (OSTI)

    Battiste, R.L.; Corum, J.M.; Ren, W.; Ruggles, M.B.

    1999-11-01

    This report provides recommended durability-based design criteria for a chopped-glass-fiber reinforced polymeric composite for automotive structural applications. The criteria closely follow the framework of an earlier criteria document for a continuous-strand-mat (CSM) glass-fiber reference composite. Together these design criteria demonstrate a framework that can be adapted for future random-glass-fiber composites for automotive structural applications.

  19. Los Alamos Waste Acceptance Criteria | Department of Energy

    Energy Savers [EERE]

    Waste Acceptance Criteria Los Alamos Waste Acceptance Criteria This document was used to determine facts and conditions during the Department of Energy Accident Investigation Board's investigation into the radiological release event at the Waste Isolation Pilot Plant. Additional documents referenced and listed in the Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014, report in Attachment F. Bibliography and References, are available on various public

  20. Fusion Blanket Coolant Section Criteria, Methodology, and Results

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Fusion Blanket Coolant Section Criteria, Methodology, and Results Citation Details In-Document Search Title: Fusion Blanket Coolant Section Criteria, Methodology, and Results The focus of this LDRD was to explore potential Li alloys that would meet the tritium breeding and blanket cooling requirements but with reduced chemical reactivity, while maintaining the other attractive features of pure Li breeder/coolant. In other fusion approaches (magnetic

  1. NIF Functional Requirements and Primary Criteria Rev. 1.8 September...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: NIF Functional Requirements and Primary Criteria Rev. 1.8 September 2006 Citation Details In-Document Search Title: NIF Functional Requirements and Primary ...

  2. Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant |

    Office of Environmental Management (EM)

    Department of Energy The documents included in this listing are additional references not included in the Phase 2 Radiological Release at the Waste Isolation Pilot Plant, Attachment F: Bibliography and References report. The documents were examined and used to develop the final report. PDF icon Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

  3. Accident analysis and DOE criteria

    SciTech Connect (OSTI)

    Graf, J.M.; Elder, J.C.

    1982-01-01

    In analyzing the radiological consequences of major accidents at DOE facilities one finds that many facilities fall so far below the limits of DOE Order 6430 that compliance is easily demonstrated by simple analysis. For those cases where the amount of radioactive material and the dispersive energy available are enough for accident consequences to approach the limits, the models and assumptions used become critical. In some cases the models themselves are the difference between meeting the criteria or not meeting them. Further, in one case, we found that not only did the selection of models determine compliance but the selection of applicable criteria from different chapters of Order 6430 also made the difference. DOE has recognized the problem of different criteria in different chapters applying to one facility, and has proceeded to make changes for the sake of consistency. We have proposed to outline the specific steps needed in an accident analysis and suggest appropriate models, parameters, and assumptions. As a result we feed DOE siting and design criteria will be more fairly and consistently applied.

  4. Criteria and Review Approach Documents | Department of Energy

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

    Criteria and Review Approach Documents Criteria and Review Approach Documents CRAD Type Criteria and Review Approach Document List

  5. Criteria Review and Approach Documents | Department of Energy

    Energy Savers [EERE]

    Criteria Review and Approach Documents Criteria Review and Approach Documents CRAD Type Criteria Review and Approach Document List...

  6. Nuclear Reactor Safety Design Criteria

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

    1993-01-19

    The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Supersedes DOE 5480.1, dated 1-19-93. Certified 11-18-10.

  7. Photovoltaic module certification/laboratory accreditation criteria development: Implementation handbook

    SciTech Connect (OSTI)

    Osterwald, C.R. [National Renewable Energy Laboratory, Golden, CO (United States); Hammond, R.L.; Wood, B.D.; Backus, C.E.; Sears, R.L. [Arizona State Univ., Tempe, AZ (United States); Zerlaut, G.A. [SC-International, Inc., Tempe, AZ (United States); D`Aiello, R.V. [RD Associates, Tempe, AZ (United States)

    1996-08-01

    This document covers the second phase of a two-part program. Phase I provided an overview of the structure and function of typical product certification/laboratory accreditation programs. This report (Phase H) provides most of the draft documents that will be necessary for the implementation of a photovoltaic (PV) module certification/laboratory accreditation program. These include organizational documents such as articles of incorporation, bylaws, and rules of procedure, as well as marketing and educational program documents. In Phase I, a 30-member criteria development committee was established to guide, review and reach a majority consensus regarding criteria for a PV certification/laboratory accreditation program. Committee members represented PV manufacturers, end users, standards and codes organizations, and testing laboratories. A similar committee was established for Phase II; the criteria implementation committee consisted of 29 members. Twenty-one of the Phase I committee members also served on the Phase II committee, which helped to provide program continuity during Phase II.

  8. Protocol, Inspection Criteria - April 23, 2008 | Department of...

    Energy Savers [EERE]

    Protocol, Inspection Criteria - April 23, 2008 Protocol, Inspection Criteria - April 23, 2008 April 23, 2008 Inspection Criteria, Activities, and Lines of Inquiry, April 23, 2008...

  9. Proposal Writing Guidelines and Scoring Criteria

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

    when the reasons for choosing a specific beamline are clearly stated, e.g., unique features, required resolution, higher flux, etc. Criteria for Evaluating the Scientific...

  10. Nevada National Security Site Waste Acceptance Criteria

    National Nuclear Security Administration (NNSA)

    Nevada National Security Site Waste Acceptance Criteria Prepared by U.S. Department of Energy National Nuclear Security Administration Nevada Field Office Environmental...

  11. Vermont Small Hydropower Assistance Program Screening Criteria...

    Open Energy Info (EERE)

    LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: Vermont Small Hydropower Assistance Program Screening Criteria Summary and Application InstructionsPermitting...

  12. Application Content and Evaluation Criteria/Process

    Broader source: Energy.gov [DOE]

    Presentation on Application Content and Evaluation Criteria/Process presented at the PEM fuel cell pre-solicitation meeting held May 26, 2005 in Arlington, VA.

  13. Range Design Criteria- June 4, 2012

    Broader source: Energy.gov [DOE]

    This document contains the currently-approved firearms "Range Design Criteria" referred to on DOE O 473.3, Protection Program Operations

  14. WPN 99-7- WAP Eligibility Criteria

    Office of Energy Efficiency and Renewable Energy (EERE)

    To provide states with guidance on the interpretation of certain eligibility criteria for use in the low-income Weatherization Assistance Program.

  15. Evolving treatment plan quality criteria from institution-specific experience

    SciTech Connect (OSTI)

    Ruan, D.; Shao, W.; DeMarco, J.; Tenn, S.; King, C.; Low, D.; Kupelian, P.; Steinberg, M.

    2012-05-15

    Purpose: The dosimetric aspects of radiation therapy treatment plan quality are usually evaluated and reported with dose volume histogram (DVH) endpoints. For clinical practicality, a small number of representative quantities derived from the DVH are often used as dose endpoints to summarize the plan quality. National guidelines on reference values for such quantities for some standard treatment approaches are often used as acceptance criteria to trigger treatment plan review. On the other hand, treatment prescription and planning approaches specific to each institution warrants the need to report plan quality in terms of practice consistency and with respect to institution-specific experience. The purpose of this study is to investigate and develop a systematic approach to record and characterize the institution-specific plan experience and use such information to guide the design of plan quality criteria. In the clinical setting, this approach will assist in (1) improving overall plan quality and consistency and (2) detecting abnormal plan behavior for retrospective analysis. Methods: The authors propose a self-evolving methodology and have developed an in-house prototype software suite that (1) extracts the dose endpoints from a treatment plan and evaluates them against both national standard and institution-specific criteria and (2) evolves the statistics for the dose endpoints and updates institution-specific criteria. Results: The validity of the proposed methodology was demonstrated with a database of prostate stereotactic body radiotherapy cases. As more data sets are accumulated, the evolving institution-specific criteria can serve as a reliable and stable consistency measure for plan quality and reveals the potential use of the ''tighter'' criteria than national standards or projected criteria, leading to practice that may push to shrink the gap between plans deemed acceptable and the underlying unknown optimality. Conclusions: The authors have developed a rationale to improve plan quality and consistency, by evolving the plan quality criteria from institution-specific experience, complementary to national standards. The validity of the proposed method was demonstrated with a prototype system on prostate stereotactic body radiotherapy (SBRT) cases. The current study uses direct and indirect DVH endpoints for plan quality evaluation, but the infrastructure proposed here applies to general outcome data as well. The authors expect forward evaluation together with intelligent update based on evidence-based learning, which will evolve the clinical practice for improved efficiency, consistency, and ultimately better treatment outcome.

  16. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    SciTech Connect (OSTI)

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  17. Reports

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

    Reports Reports Individual Permit reports are prepared annually to facilitate public review of activities for the previous year. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Individual Permit for Storm Water Reports Annual Report 2015 (pdf) 2014 (pdf) 2013 (pdf) Submittal Letter (pdf) 2012 (pdf) Submittal Letter (pdf) 2011 (pdf) Background Metals and Radioactivity Report Background Metals Concentrations and

  18. Analysis of the impact of safeguards criteria

    SciTech Connect (OSTI)

    Mullen, M.F.; Reardon, P.T.

    1981-01-01

    As part of the US Program of Technical Assistance to IAEA Safeguards, the Pacific Northwest Laboratory (PNL) was asked to assist in developing and demonstrating a model for assessing the impact of setting criteria for the application of IAEA safeguards. This report presents the results of PNL's work on the task. The report is in three parts. The first explains the technical approach and methodology. The second contains an example application of the methodology. The third presents the conclusions of the study. PNL used the model and computer programs developed as part of Task C.5 (Estimation of Inspection Efforts) of the Program of Technical Assistance. The example application of the methodology involves low-enriched uranium conversion and fuel fabrication facilities. The effects of variations in seven parameters are considered: false alarm probability, goal probability of detection, detection goal quantity, the plant operator's measurement capability, the inspector's variables measurement capability, the inspector's attributes measurement capability, and annual plant throughput. Among the key results and conclusions of the analysis are the following: the variables with the greatest impact on the probability of detection are the inspector's measurement capability, the goal quantity, and the throughput; the variables with the greatest impact on inspection costs are the throughput, the goal quantity, and the goal probability of detection; there are important interactions between variables. That is, the effects of a given variable often depends on the level or value of some other variable. With the methodology used in this study, these interactions can be quantitatively analyzed; reasonably good approximate prediction equations can be developed using the methodology described here.

  19. Facility Representative Program, Criteria & Review Approach Documents

    Broader source: Energy.gov [DOE]

    This page provides Criteria Review and Approach Documents (CRADS) to assist Facility Representatives. Please submit your CRADS for posting by sending them to the HQ FR Program Manager. Please include the subject, date, and a contact person.

  20. Generalized Lawson Criteria for Inertial Confinement Fusion

    SciTech Connect (OSTI)

    Tipton, Robert E.

    2015-08-27

    The Lawson Criterion was proposed by John D. Lawson in 1955 as a general measure of the conditions necessary for a magnetic fusion device to reach thermonuclear ignition. Over the years, similar ignition criteria have been proposed which would be suitable for Inertial Confinement Fusion (ICF) designs. This paper will compare and contrast several ICF ignition criteria based on Lawson’s original ideas. Both analytical and numerical results will be presented which will demonstrate that although the various criteria differ in some details, they are closely related and perform similarly as ignition criteria. A simple approximation will also be presented which allows the inference of each ignition parameter directly from the measured data taken on most shots fired at the National Ignition Facility (NIF) with a minimum reliance on computer simulations. Evidence will be presented which indicates that the experimentally inferred ignition parameters on the best NIF shots are very close to the ignition threshold.

  1. Natural phenomena hazards site characterization criteria

    SciTech Connect (OSTI)

    Not Available

    1994-03-01

    The criteria and recommendations in this standard shall apply to site characterization for the purpose of mitigating Natural Phenomena Hazards (wind, floods, landslide, earthquake, volcano, etc.) in all DOE facilities covered by DOE Order 5480.28. Criteria for site characterization not related to NPH are not included unless necessary for clarification. General and detailed site characterization requirements are provided in areas of meteorology, hydrology, geology, seismology, and geotechnical studies.

  2. Electronic Records Management Software Applications Design Criteria

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

    Standard | Department of Energy Electronic Records Management Software Applications Design Criteria Standard Electronic Records Management Software Applications Design Criteria Standard This Standard is reissued under the authority of DoD Directive 5015.2, "Department of DefenseRecords Management Program," March 6, 2000, (Reference (a)) which provides implementing and procedural guidance on the management of records in the Department of Defense. PDF icon Electronic Records

  3. NITRATE DESTRUCTION LITERATURE SURVEY AND EVALUATION CRITERIA

    SciTech Connect (OSTI)

    Steimke, J.

    2011-02-01

    This report satisfies the initial phase of Task WP-2.3.4 Alternative Sodium Recovery Technology, Subtask 1; Develop Near-Tank Nitrate/Nitrite Destruction Technology. Some of the more common anions in carbon steel waste tanks at SRS and Hanford Site are nitrate which is corrosive, and nitrite and hydroxide which are corrosion inhibitors. At present it is necessary to periodically add large quantities of 50 wt% caustic to waste tanks. There are three primary reasons for this addition. First, when the contents of salt tanks are dissolved, sodium hydroxide preferentially dissolves and is removed. During the dissolution process the concentration of free hydroxide in the tank liquid can decrease from 9 M to less than 0.2 M. As a result, roughly half way through the dissolution process large quantities of sodium hydroxide must be added to the tank to comply with requirements for corrosion control. Second, hydroxide is continuously consumed by reaction with carbon dioxide which occurs naturally in purge air used to prevent buildup of hydrogen gas inside the tanks. The hydrogen is generated by radiolysis of water. Third, increasing the concentration of hydroxide increases solubility of some aluminum compounds, which is desirable in processing waste. A process that converts nitrate and nitrite to hydroxide would reduce certain costs. (1) Less caustic would be purchased. (2) Some of the aluminum solid compounds in the waste tanks would become more soluble so less mass of solids would be sent to High Level Vitrification and therefore it would be not be necessary to make as much expensive high level vitrified product. (3) Less mass of sodium would be fed to Saltstone at SRS or Low Level Vitrification at Hanford Site so it would not be necessary to make as much low level product. (4) At SRS less nitrite and nitrate would be sent to Defense Waste Processing Facility (DWPF) so less formic acid would be consumed there and less hydrogen gas would be generated. This task involves literature survey of technologies to perform the nitrate to hydroxide conversion, selection of the most promising technologies, preparation of a flowsheet and design of a system. The most promising technologies are electrochemical reduction of nitrates and chemical reduction with hydrogen or ammonia. The primary reviewed technologies are listed and they aredescribed in more detail later in the report: (1) Electrochemical destruction; (2) Chemical reduction with agents such as ammonia, hydrazine or hydrogen; (3) Hydrothermal reduction process; and (4) Calcination. Only three of the technologies on the list have been demonstrated to generate usable amounts of caustic; electrochemical reduction and chemical reduction with ammonia, hydrazine or hydrogen and hydrothermal reduction. Chemical reduction with an organic reactant such as formic acid generates carbon dioxide which reacts with caustic and is thus counterproductive. Treatment of nitrate with aluminum or other active metals generates a solid product. High temperature calcination has the potential to generate sodium oxide which may be hydrated to sodium hydroxide, but this is unproven. The following criteria were developed to evaluate the most suitable option. The numbers in brackets after the criteria are relative weighting factors to account for importance: (1) Personnel exposure to radiation for installation, routine operation and maintenance; (2) Non-radioactive safety issues; (3) Whether the technology generates caustic and how many moles of caustic are generated per mole of nitrate plus nitrite decomposed; (4) Whether the technology can handle nitrate and nitrite at the concentrations encountered in waste; (5) Maturity of technology; (6) Estimated annual cost of operation (labor, depreciation, materials, utilities); (7) Capital cost; (8) Selectivity to nitrogen as decomposition product (other products are flammable and/or toxic); (9) Impact of introduced species; (10) Selectivity for destruction of nitrate vs. nitrite; and (11) Cost of deactivation and demolition. Each technology was given a score from one

  4. NIF Functional Requirements and Primary Criteria Rev. 1.8 September 2006

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Technical Report: NIF Functional Requirements and Primary Criteria Rev. 1.8 September 2006 Citation Details In-Document Search Title: NIF Functional Requirements and Primary Criteria Rev. 1.8 September 2006 Authors: Patterson, R ; Samuelson, S Publication Date: 2014-09-29 OSTI Identifier: 1165807 Report Number(s): LLNL-TR-661755 DOE Contract Number: DE-AC52-07NA27344 Resource Type: Technical Report Research Org: Lawrence Livermore National Laboratory

  5. DOE Standard: Fire protection design criteria

    SciTech Connect (OSTI)

    Not Available

    1999-07-01

    The development of this Standard reflects the fact that national consensus standards and other design criteria do not comprehensively or, in some cases, adequately address fire protection issues at DOE facilities. This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, National Fire Protection Association (NFPA) Codes and Standards, and any other applicable DOE construction criteria. This Standard replaces certain mandatory fire protection requirements that were formerly in DOE 5480.7A, ``Fire Protection``, and DOE 6430.1A, ``General Design Criteria``. It also contains the fire protection guidelines from two (now canceled) draft standards: ``Glove Box Fire Protection`` and ``Filter Plenum Fire Protection``. (Note: This Standard does not supersede the requirements of DOE 5480.7A and DOE 6430.1A where these DOE Orders are currently applicable under existing contracts.) This Standard, along with the criteria delineated in Section 3, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities.

  6. Waste acceptance criteria for the Waste Isolation Pilot Plant. Revision 4

    SciTech Connect (OSTI)

    Not Available

    1991-12-01

    This Revision 4 of the Waste Acceptance Criteria (WAC), WIPP-DOE-069, identifies and consolidates existing criteria and requirements which regulate the safe handling and preparation of Transuranic (TRU) waste packages for transportation to and emplacement in the Waste Isolation Pilot Plant (WIPP). This consolidation does not invalidate any existing certification of TRU waste to the WIPP Operations and Safety Criteria (Revision 3 of WIPP-DOE--069) and/or Transportation: Waste Package Requirements (TRUPACT-II Safety Analysis Report for Packaging [SARP]). Those documents being consolidated, including Revision 3 of the WAC, currently support the Test Phase.

  7. Facility Energy Management Guidelines and Criteria for Energy...

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

    Facility Energy Management Guidelines and Criteria for Energy and Water Evaluations in Covered Facilities Facility Energy Management Guidelines and Criteria for Energy and Water ...

  8. Criteria and Guidelines for the Federal Energy and Water Management...

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

    Criteria and Guidelines for the Federal Energy and Water Management Awards Criteria and Guidelines for the Federal Energy and Water Management Awards Document outlines the 2016 ...

  9. Statistical criteria for characterizing irradiance time series.

    SciTech Connect (OSTI)

    Stein, Joshua S.; Ellis, Abraham; Hansen, Clifford W.

    2010-10-01

    We propose and examine several statistical criteria for characterizing time series of solar irradiance. Time series of irradiance are used in analyses that seek to quantify the performance of photovoltaic (PV) power systems over time. Time series of irradiance are either measured or are simulated using models. Simulations of irradiance are often calibrated to or generated from statistics for observed irradiance and simulations are validated by comparing the simulation output to the observed irradiance. Criteria used in this comparison should derive from the context of the analyses in which the simulated irradiance is to be used. We examine three statistics that characterize time series and their use as criteria for comparing time series. We demonstrate these statistics using observed irradiance data recorded in August 2007 in Las Vegas, Nevada, and in June 2009 in Albuquerque, New Mexico.

  10. Hanford Site solid waste acceptance criteria

    SciTech Connect (OSTI)

    Ellefson, M.D.

    1998-07-01

    Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities.

  11. Hanford Site Solid Waste Acceptance Criteria

    SciTech Connect (OSTI)

    Not Available

    1993-11-17

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

  12. Nevada Test Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2005-10-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  13. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-07-01

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

  14. History and Evolution of the Johnson Criteria.

    SciTech Connect (OSTI)

    Sjaardema, Tracy A.; Smith, Collin S.; Birch, Gabriel Carisle

    2015-07-01

    The Johnson Criteria metric calculates probability of detection of an object imaged by an optical system, and was created in 1958 by John Johnson. As understanding of target detection has improved, detection models have evolved to better model additional factors such as weather, scene content, and object placement. The initial Johnson Criteria, while sufficient for technology and understanding at the time, does not accurately reflect current research into target acquisition and technology. Even though current research shows a dependence on human factors, there appears to be a lack of testing and modeling of human variability.

  15. Aseismic design criteria for uranium enrichment plants

    SciTech Connect (OSTI)

    Beavers, J.E.

    1980-01-01

    In this paper technological, economical, and safety issues of aseismic design of uranium enrichment plants are presented. The role of management in the decision making process surrounding these issues is also discussed. The resolution of the issues and the decisions made by management are controlling factors in developing aseismic design criteria for any facility. Based on past experience in developing aseismic design criteria for the GCEP various recommendations are made for future enrichment facilities, and since uranium enrichment plants are members of the nuclear fuel cycle the discussion and recommendations presented herein are applicable to other nonreactor nuclear facilities.

  16. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    SciTech Connect (OSTI)

    NNSA /NSO Waste Management Project

    2008-06-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

  17. CRAD, Safety Systems Inspection Criteria- December 17, 2012

    Broader source: Energy.gov [DOE]

    Safety Systems Inspection Criteria in implementing Integrated Safety Management, (HSS CRAD 45-11, Rev. 3)

  18. Nuclear Safety Research and Development Annual Report, December 2014 |

    Energy Savers [EERE]

    Reporting Criteria Nuclear Safety Reporting Criteria January 1, 2012 Nuclear Safety Noncompliances Associated With Occurrences (DOE Order 232.2) These tables provide the criteria for reporting nuclear safety noncompliances into the Department of Energy's Noncompliance Tracking System (NTS). A more detailed description of the NTS reporting criteria and expectations can be found in the Office of Health, Safety and Security's Enforcement Coordinator Handbook. PDF icon Nuclear Safety Reporting

  19. REPORT

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

    DOE/NV/11718-387 ECOLOGICAL MONITORING AND COMPLIANCE PROGRAM FISCAL YEAR 1999 REPORT December 1999 Prepared by Ecological Services P.O. Box 98521 Las Vegas, NV 89193-8521 DISCLAIMER STATEMENT Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof or its contractors or subcontractors.

  20. Packaging design criteria for the MCO cask

    SciTech Connect (OSTI)

    Edwards, W.S.

    1996-04-29

    Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins (including possibly 700 additional elements from PUREX, N Reactor, and 327 Laboratory). The basin water, particularly in the K East Basin, contains significant quantities of dissolved nuclear isotopes and radioactive fuel corrosion particles. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the 100 K Area to a Canister Storage Building (CSB) in the 200 East area. In order to initiate K Basin cleanup on schedule, the two-year fuel-shipping campaign must begin by December 1997. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multiple Canister Overpacks.

  1. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2010-09-03

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  2. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2011-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  3. Application Content and Evaluation Criteria/Process

    Energy Savers [EERE]

    Evaluation Criteria/Process Reginald Tyler Golden Field Office Office of Hydrogen, Fuel Cells and Infrastructure Technologies Application Content o Separate Applications for Each Major Topic o Title Should Identify the Topic Area o Application - SF 424 o Budget File - SF 424A o Project Summary - 1 page, non-proprietary Project Narrative o Provide clear description of the technical concept and how you plan to accomplish the work. o Include a description of the relevance of and justification for

  4. Functional Area Criteria & Review Approach Documents

    Broader source: Energy.gov [DOE]

    CRADS provided on this page are provided as examples of functional area Objectives and Criteria used to evaluate how requirements are meet. They are only examples and should not be utilized as is. In accordance with DOE Standard 3006-2010, CRADs should be developed by team members to reflect the specifics of the proposed review (i.e., breadth and depth) as defined in the approved Plan of Action.

  5. Proposal Writing Guidelines and Scoring Criteria

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

    Proposal Writing Guidelines and Scoring Criteria Print Principal Investigator The proposal form asks for the names and contact information of the experiment leader completing the form and the Principal Investigator (PI). The PI is the leader and the individual responsible for the group, and the experiment leader is often the person completing the proposal form. In this way the ALS would like to encourage postdocs and students to gain experience in submitting proposals as the experiment leader,

  6. Acceptance Criteria Framework for Autonomous Biological Detectors

    SciTech Connect (OSTI)

    Dzenitis, J M

    2006-12-12

    The purpose of this study was to examine a set of user acceptance criteria for autonomous biological detection systems for application in high-traffic, public facilities. The test case for the acceptance criteria was the Autonomous Pathogen Detection System (APDS) operating in high-traffic facilities in New York City (NYC). However, the acceptance criteria were designed to be generally applicable to other biological detection systems in other locations. For such detection systems, ''users'' will include local authorities (e.g., facility operators, public health officials, and law enforcement personnel) and national authorities [including personnel from the Department of Homeland Security (DHS), the BioWatch Program, the Centers for Disease Control and Prevention (CDC), and the Federal Bureau of Investigation (FBI)]. The panel members brought expertise from a broad range of backgrounds to complete this picture. The goals of this document are: (1) To serve as informal guidance for users in considering the benefits and costs of these systems. (2) To serve as informal guidance for developers in understanding the needs of users. In follow-up work, this framework will be used to systematically document the APDS for appropriateness and readiness for use in NYC.

  7. Guidelines Establishing Criteria for Excluding Buildings from...

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

    ... Agencies should report aggregate energy consumption in excluded buildings for each energy type in the reporting units listed below: Electricity Fuel Oil Natural Gas LPGPropane ...

  8. Machine plumbness criteria: Interim technology release

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    The objective of this technology release is to define the maximum allowable deviation from plumb of the centrifuge machine and to recommend machine installation techniques to achieve the specified criteria. The centrifuge feature used as a reference for plumbness is the casing centerline as defined by a line drawn between the theoretical centers of the top and bottom flange faces. In practice, this measurement is accomplished by using specified casing flange diameters or bolt patterns as the reference points. The criterion adopted for GCEP is that each machine shall be plumb within 0.5 in. over the length of the casing as initially installed. Over a long period of time the plumbness is allowed to degrade to 1.0 in. This standard should be achievable using the currently planned installation techniques and within a time limit consistent with GCEP operational objectives. For development testing, centrifuge machines are meticulously adjusted using a plumb bob to achieve a plumbness with 1/8 in. About one to two days are required to complete the installation. This level of effort is justified for a development machine especially where baseline data is being gathered. A more reasonable standard with a corresponding reduction in installation time is required for GCEP. The specified criteria of 0.5 in. maximum out-of-plumb at time of installation and 1.0 in., ultimate, are believed to be a reasonable compromise. Machine design features or operating modes that are dependent on vertical alignment were examined to assess the impact of the selected plumbness criteria. Machine performance and design requirements are defined in the applicable technology release documents.

  9. 309 Facility deactivation and decommisioning Criteria Completion Check Lists

    SciTech Connect (OSTI)

    Cornwell, B.C.

    1996-02-01

    To facilitate and track completion of the 309 Facility turnover criteria completion an Applicability Matrix and Criteria Completion Check Lists were prepared. The applicability matrix documents the required turnover criteria for a given area in the facility or scope of work. The applicable criteria is selected for 16 different areas. For each area a completion checklist is provided to document completion of a requirement by WHC and the Environmental Restoration Contractor.

  10. Bioenergy and Food Security Criteria and Indicators (BEFSCI)...

    Open Energy Info (EERE)

    URI: cleanenergysolutions.orgcontentbioenergy-and-food-security-criteria- Language: English Policies: Deployment Programs DeploymentPrograms: Technical Assistance This...

  11. Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

    SciTech Connect (OSTI)

    Mertz, G.

    1999-12-16

    This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements.

  12. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2012-02-28

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  13. FRACTURE FAILURE CRITERIA OF SOFC PEN STRUCTURE

    SciTech Connect (OSTI)

    Liu, Wenning N.; Sun, Xin; Khaleel, Mohammad A.; Qu, Jianmin

    2007-04-30

    Thermal stresses and warpage of the PEN are unavoidable due to the temperature changes from the stress-free sintering temperature to room temperature and mismatch of the coefficients of thermal expansion (CTE) of various layers in the PEN structures of solid oxide fuel cells (SOFC) during the PEN manufacturing process. In the meantime, additional mechanical stresses will also be created by mechanical flattening during the stack assembly process. The porous nature of anode and cathode in the PEN structures determines presence of the initial flaws and crack on the interfaces of anode/electrolyte/cathode and in the interior of the materials. The sintering/assembling induced stresses may cause the fracture failure of PEN structure. Therefore, fracture failure criteria for SOFC PEN structures is developed in order to ensure the structural integrity of the cell and stack of SOFC. In this paper, the fracture criteria based on the relationship between the critical energy release rate and critical curvature and maximum displacement of the warped cells caused by the temperature changes as well as mechanical flattening process is established so that possible failure of SOFC PEN structures may be predicted deterministically by the measurement of the curvature and displacement of the warped cells.

  14. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    none,

    2013-06-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE hazardous and non-hazardous non-radioactive classified waste DOE low-level radioactive waste (LLW) DOE mixed low-level waste (MLLW) U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  15. Radiological risk evaluation for risk-based design criteria of the multiple canister overpack packaging

    SciTech Connect (OSTI)

    Green, J.R., Westinghouse Hanford

    1996-07-18

    The Multiple Canister Overpack (MCO) cask will be used in the transportation of irradiated nuclear fuel from the K Basins to a Canister Storage Building. This report presents the radiological risk evaluation, which is used in the development of the design criteria for the MCO cask. The radiological risk evaluation ensures compliance with the onsite transportation safety program.

  16. Technical guidance for siting criteria development

    SciTech Connect (OSTI)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

    1982-12-01

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

  17. A review of macroscopic ductile failure criteria.

    SciTech Connect (OSTI)

    Corona, Edmundo; Reedlunn, Benjamin

    2013-09-01

    The objective of this work was to describe several of the ductile failure criteria com- monly used to solve practical problems. The following failure models were considered: equivalent plastic strain, equivalent plastic strain in tension, maximum shear, Mohr- Coulomb, Wellman's tearing parameter, Johnson-Cook and BCJ MEM. The document presents the main characteristics of each failure model as well as sample failure predic- tions for simple proportional loading stress histories in three dimensions and in plane stress. Plasticity calculations prior to failure were conducted with a simple, linear hardening, J2 plasticity model. The resulting failure envelopes were plotted in prin- cipal stress space and plastic strain space, where the dependence on stress triaxiality and Lode angle are clearly visible. This information may help analysts select a ductile fracture model for a practical problem and help interpret analysis results.

  18. Audit Report: IG-0613 | Department of Energy

    Energy Savers [EERE]

    PDF icon Audit Report: IG-0613 More Documents & Publications EIS-0200-SA-03: Supplement Analysis EIS-0026-SA-06: Supplement Analysis Transuranic Waste Acceptance Criteria for the ...

  19. Facility Energy Management Guidelines and Criteria for Energy and Water

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

    Evaluations in Covered Facilities | Department of Energy Facility Energy Management Guidelines and Criteria for Energy and Water Evaluations in Covered Facilities Facility Energy Management Guidelines and Criteria for Energy and Water Evaluations in Covered Facilities Guidelines and criteria describe meeting requirements within Section 432 of the Energy Independence and Security Act of 2007 (EISA 2007), including defining facilities covered by the provision, designating facility energy

  20. Department of Energy Announces More Stringent Energy Efficient Criteria for

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

    ENERGY STAR® Dishwashers | Department of Energy Stringent Energy Efficient Criteria for ENERGY STAR® Dishwashers Department of Energy Announces More Stringent Energy Efficient Criteria for ENERGY STAR® Dishwashers March 2, 2006 - 11:39am Addthis More Efficient Dishwashers Estimated to Save Consumers over $26 Million Annually WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced more stringent energy efficient criteria for dishwashers carrying the ENERGY STAR® label that

  1. Department of Energy Announces Tougher Criteria for ENERGY STAR® Clothes

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

    Washers | Department of Energy Tougher Criteria for ENERGY STAR® Clothes Washers Department of Energy Announces Tougher Criteria for ENERGY STAR® Clothes Washers March 30, 2005 - 11:09am Addthis New Standards Estimated to Save Consumers over $52.8 Million Annually WASHINGTON, D.C. - In a continuing effort to improve America's energy conservation, the U.S. Department of Energy today announced more stringent criteria for clothes washers carrying the ENERGY STAR® label. The new, tougher

  2. Energy Department Announces More Stringent Criteria for ENERGY STAR®

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

    Refrigerators | Department of Energy More Stringent Criteria for ENERGY STAR® Refrigerators Energy Department Announces More Stringent Criteria for ENERGY STAR® Refrigerators August 3, 2007 - 2:55pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced increased energy efficient criteria for refrigerators carrying the ENERGY STAR® label. In order to qualify, full-size refrigerators must be a minimum of 20 percent more efficient than current federal energy efficiency

  3. Readiness Review Training- Development of Criteria And Review Approach Documents

    Broader source: Energy.gov [DOE]

    Slides used for November 8-9, 2010 Readiness Review Training - Development of Criteria And Review Approach Documents at the Idaho National Laboratory.

  4. CO - Floodplain Stormwater and Criteria Manual | Open Energy...

    Open Energy Info (EERE)

    This webpage provides the floodplain stormwater and criteria in Colorado. Author Colorado Water Conservation Board - Department of Natural Resources Published Colorado Water...

  5. Criteria and Indicators for Sustainable Woodfuels | Open Energy...

    Open Energy Info (EERE)

    Type: Guidemanual Website: www.fao.orgdocrep012i1673ei1673e00.pdf Criteria and Indicators for Sustainable Woodfuels Screenshot References: Sustainable Woodfuels1...

  6. Vermont Agency of Commerce and Community Development's Criteria...

    Open Energy Info (EERE)

    case-by-case basis and focus on direct and indirect impacts of a substantial nature. Use of these criteria further implements any applicable state and federal review...

  7. Natural Phenomena Hazard Analysis and Design Criteria for Department...

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

    20-2012, Natural Phenomena Hazard Analysis and Design Criteria for Department of Energy Facilities by Diane Johnson This Department of Energy (DOE) Standard (STD)-1020-2012,...

  8. Oregon Procedure and Criteria for Hazardous Waste Treatment,...

    Open Energy Info (EERE)

    Procedure and Criteria for Hazardous Waste Treatment, Storage or Disposal Permits Fact Sheet Jump to: navigation, search OpenEI Reference LibraryAdd to library Permitting...

  9. Texas PUCT Substantive Rule 25.101, Certification Criteria, Electric...

    Open Energy Info (EERE)

    Help Apps Datasets Community Login | Sign Up Search Page Edit with form History Texas PUCT Substantive Rule 25.101, Certification Criteria, Electric Substantive Rules Jump...

  10. MERGING CRITERIA FOR GIANT IMPACTS OF PROTOPLANETS

    SciTech Connect (OSTI)

    Genda, H.; Kokubo, E.; Ida, S.

    2012-01-10

    At the final stage of terrestrial planet formation, known as the giant impact stage, a few tens of Mars-sized protoplanets collide with one another to form terrestrial planets. Almost all previous studies on the orbital and accretional evolution of protoplanets in this stage have been based on the assumption of perfect accretion, where two colliding protoplanets always merge. However, recent impact simulations have shown that collisions among protoplanets are not always merging events, that is, two colliding protoplanets sometimes move apart after the collision (hit-and-run collision). As a first step toward studying the effects of such imperfect accretion of protoplanets on terrestrial planet formation, we investigated the merging criteria for collisions of rocky protoplanets. Using the smoothed particle hydrodynamic method, we performed more than 1000 simulations of giant impacts with various parameter sets, such as the mass ratio of protoplanets, {gamma}, the total mass of two protoplanets, M{sub T}, the impact angle, {theta}, and the impact velocity, v{sub imp}. We investigated the critical impact velocity, v{sub cr}, at the transition between merging and hit-and-run collisions. We found that the normalized critical impact velocity, v{sub cr}/v{sub esc}, depends on {gamma} and {theta}, but does not depend on M{sub T}, where v{sub esc} is the two-body escape velocity. We derived a simple formula for v{sub cr}/v{sub esc} as a function of {gamma} and {theta} (Equation (16)), and applied it to the giant impact events obtained by N-body calculations in the previous studies. We found that 40% of these events should not be merging events.

  11. A Framework for Human Performance Criteria for Advanced Reactor Operational Concepts

    SciTech Connect (OSTI)

    Jacques V Hugo; David I Gertman; Jeffrey C Joe

    2014-08-01

    This report supports the determination of new Operational Concept models needed in support of the operational design of new reactors. The objective of this research is to establish the technical bases for human performance and human performance criteria frameworks, models, and guidance for operational concepts for advanced reactor designs. The report includes a discussion of operating principles for advanced reactors, the human performance issues and requirements for human performance based upon work domain analysis and current regulatory requirements, and a description of general human performance criteria. The major findings and key observations to date are that there is some operating experience that informs operational concepts for baseline designs for SFR and HGTRs, with the Experimental Breeder Reactor-II (EBR-II) as a best-case predecessor design. This report summarizes the theoretical and operational foundations for the development of a framework and model for human performance criteria that will influence the development of future Operational Concepts. The report also highlights issues associated with advanced reactor design and clarifies and codifies the identified aspects of technology and operating scenarios.

  12. Summary of the Advanced Reactor Design Criteria (ARDC) Phase 2 Activities

    SciTech Connect (OSTI)

    Holbrook, Mark Raymond

    2015-09-01

    This report provides an end-of-year summary reflecting the progress and status of proposed regulatory design criteria for advanced non-LWR designs in accordance with the Level 3 milestone in M3AT-15IN2001017 in work package AT-15IN200101. These criteria have been designated as ARDC, and they provide guidance to future applicants for addressing the GDC that are currently applied specifically to LWR designs. The report provides a summary of Phase 2 activities related to the various tasks associated with ARDC development and the subsequent development of example adaptations of ARDC for Sodium Fast Reactor (SFR) and modular High Temperature Gas-cooled Reactor (HTGR) designs.

  13. Labs21 Environmental Performance Criteria: Toward 'LEED (trademark) for Labs'

    SciTech Connect (OSTI)

    Mathew, Paul; Sartor, Dale; Lintner, William; Wirdzek, Phil

    2002-10-14

    Laboratory facilities present a unique challenge for energy efficient and sustainable design, with their inherent complexity of systems, health and safety requirements, long-term flexibility and adaptability needs, energy use intensity, and environmental impacts. The typical laboratory is about three to five times as energy intensive as a typical office building and costs about three times as much per unit area. In order to help laboratory stakeholders assess the environmental performance of their laboratories, the Labs21 program, sponsored by the US Environmental Protection Agency and the US Department of Energy, is developing the Environmental Performance Criteria (EPC), a point-based rating system that builds on the LEED(TM) rating system. Currently, LEED(TM) is the primary tool used to rate the sustainability of commercial buildings. However, it lacks some attributes essential to encouraging the application of sustainable design principles to laboratory buildings. Accordingly, the EPC has additions and modifications to the prerequisites and credits in each of the six sections of LEED(TM). It is being developed in a consensus-based approach by a diverse group of architects, engineers, consulting experts, health & safety personnel and facilities personnel. This report describes the EPC version 2.0, highlighting the underlying technical issues, and describes implications for the development of a LEED version for Laboratories.

  14. Low-level-waste-form criteria

    SciTech Connect (OSTI)

    Barletta, R.E.; Davis, R.E.

    1982-01-01

    Efforts in five areas are reported: technical considerations for a high-integrity container for resin wastes; permissible radionuclide loadings for organic ion exchange resin wastes; technical factors affecting low-level waste form acceptance requirements of the proposed 10 CFR 61 and draft BTP; modeling of groundwater transport; and analysis of soils from low-level waste disposal sites (Barnwell, Hanford, and Sheffield). (DLC)

  15. Guidance for Developing Principal Design Criteria for Advanced (Non-Light Water) Reactors

    SciTech Connect (OSTI)

    Holbrook, Mark; Kinsey, Jim

    2015-03-01

    In July 2013, the US Department of Energy (DOE) and US Nuclear Regulatory Commission (NRC) established a joint initiative to address a key portion of the licensing framework essential to advanced (non-light water) reactor technologies. The initiative addressed the “General Design Criteria for Nuclear Power Plants,” Appendix A to10 Code of Federal Regulations (CFR) 50, which were developed primarily for light water reactors (LWRs), specific to the needs of advanced reactor design and licensing. The need for General Design Criteria (GDC) clarifications in non-LWR applications has been consistently identified as a concern by the industry and varied stakeholders and was acknowledged by the NRC staff in their 2012 Report to Congress1 as an area for enhancement. The initiative to adapt GDC requirements for non-light water advanced reactor applications is being accomplished in two phases. Phase 1, managed by DOE, consisted of reviews, analyses and evaluations resulting in recommendations and deliverables to NRC as input for NRC staff development of regulatory guidance. Idaho National Laboratory (INL) developed this technical report using technical and reactor technology stakeholder inputs coupled with analysis and evaluations provided by a team of knowledgeable DOE national laboratory personnel with input from individual industry licensing consultants. The DOE national laboratory team reviewed six different classes of emerging commercial reactor technologies against 10 CFR 50 Appendix A GDC requirements and proposed guidance for their adapted use in non-LWR applications. The results of the Phase 1 analysis are contained in this report. A set of draft Advanced Reactor Design Criteria (ARDC) has been proposed for consideration by the NRC in the establishment of guidance for use by non-LWR designers and NRC staff. The proposed criteria were developed to preserve the underlying safety bases expressed by the original GDC, and recognizing that advanced reactors may take advantage of various new passive and inherent safety features different from those associated with LWRs.

  16. Building America Best Practices Series Volume 8: Builders Challenge Quality Criteria Support Document

    SciTech Connect (OSTI)

    Baechler, Michael C.; Bartlett, Rosemarie; Gilbride, Theresa L.

    2010-11-01

    The U.S. Department of Energy (DOE) has posed a challenge to the homebuilding industry—to build 220,000 high-performance homes by 2012. Through the Builders Challenge, participating homebuilders will have an easy way to differentiate their best energy-performing homes from other products in the marketplace, and to make the benefits clear to buyers. This document was prepared by Pacific Northwest National Laboratory for DOE to provide guidance to U.S. home builders who want to accept the challenge. To qualify for the Builders Challenge, a home must score 70 or less on the EnergySmart Home Scale (E-Scale). The E-scale is based on the well-established Home Energy Rating System (HERS) index, developed by the Residential Energy Services Network (RESNET). The E-scale allows homebuyers to understand – at a glance – how the energy performance of a particular home compares with the performance of others. To learn more about the index and HERS Raters, visit www.natresnet.org. Homes also must meet the Builders Challenge criteria described in this document. To help builders meet the Challenge, guidance is provided in this report for each of the 29 criteria. Included with guidance for each criteria are resources for more information and references for relevant codes and standards. The Builders Challenge Quality Criteria were originally published in Dec. 2008. They were revised and published as PNNL-18009 Rev 1.2 in Nov. 2009. This is version 1.3, published Nov 2010. Changes from the Nov 2009 version include adding a title page and updating the Energy Star windows critiera to the Version 5.0 criteria approved April 2009 and effective January 4, 2010. This document and other information about the Builders Challenge is available on line at www.buildingamerica.gov/challenge.

  17. Federal Energy and Water Management Awards Criteria Briefing Webinar

    Broader source: Energy.gov [DOE]

    Webinar provides an overview of the 2015 Federal Energy and Water Management Awards criteria and eligibility requirements, as well as tips on how to prepare nomination narratives to achieve better scores.

  18. February 23, 2016 Webinar - Multi-Criteria Decisional Analyses...

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

    Practice (CoP) Webinar - February 23, 2016 - Multi-Criteria Decisional Analyses: Methodology and Case Studies (Dr. Igor Linkov and Mr. Matthew Bates, U.S. Army Corps of Engineers). ...

  19. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    SciTech Connect (OSTI)

    1982-07-01

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

  20. Entanglement criteria via concave-function uncertainty relations

    SciTech Connect (OSTI)

    Huang Yichen

    2010-07-15

    A general theorem as a necessary condition for the separability of quantum states in both finite and infinite dimensional systems, based on concave-function uncertainty relations, is derived. Two special cases of the general theorem are stronger than two known entanglement criteria based on the Shannon entropic uncertainty relation and the Landau-Pollak uncertainty relation, respectively; other special cases are able to detect entanglement where some famous entanglement criteria fail.

  1. Strain-Based Acceptance Criteria for Energy-Limited Events

    SciTech Connect (OSTI)

    Spencer D. Snow; Dana K. Morton

    2009-07-01

    The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code was primarily written with stress-based acceptance criteria. These criteria are applicable to force, displacement, and energy-controlled loadings and ensure a factor of safety against failure. However, stress-based acceptance criteria are often quite conservative for one time energy-limited events such as accidental drops and impacts. For several years, the ASME Working Group on Design of Division 3 Containments has been developing the Design Articles for Section III, Division 3, “Containments for Transportation and Storage of Spent Nuclear Fuel and High-Level Radioactive Material and Waste,” and has wanted to establish strain-based acceptance criteria for accidental drops of containments. This Division 3 working group asked the Working Group on Design Methodology (WGDM) to assist in developing these strain-based acceptance criteria. This paper discusses the current proposed strain-based acceptance criteria, associated limitations of use, its background development, and the current status.

  2. 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.

  3. NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

    SciTech Connect (OSTI)

    1981-04-01

    At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

  4. Methods for verifying compliance with low-level radioactive waste acceptance criteria

    SciTech Connect (OSTI)

    NONE

    1993-09-01

    This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility`s WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator`s waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits.

  5. Anticipating Potential Waste Acceptance Criteria for Defense Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Rechard, R.P.; Lord, M.E.; Stockman, C.T.; McCurley, R.D.

    1997-12-31

    The Office of Environmental Management of the U.S. Department of Energy is responsible for the safe management and disposal of DOE owned defense spent nuclear fuel and high level waste (DSNF/DHLW). A desirable option, direct disposal of the waste in the potential repository at Yucca Mountain, depends on the final waste acceptance criteria, which will be set by DOE`s Office of Civilian Radioactive Waste Management (OCRWM). However, evolving regulations make it difficult to determine what the final acceptance criteria will be. A method of anticipating waste acceptance criteria is to gain an understanding of the DOE owned waste types and their behavior in a disposal system through a performance assessment and contrast such behavior with characteristics of commercial spent fuel. Preliminary results from such an analysis indicate that releases of 99Tc and 237Np from commercial spent fuel exceed those of the DSNF/DHLW; thus, if commercial spent fuel can meet the waste acceptance criteria, then DSNF can also meet the criteria. In large part, these results are caused by the small percentage of total activity of the DSNF in the repository (1.5%) and regulatory mass (4%), and also because commercial fuel cladding was assumed to provide no protection.

  6. Title 44 Part 60 Criteria for Land Management and Use | Open...

    Open Energy Info (EERE)

    Title 44 Part 60 Criteria for Land Management and UseLegal Abstract Sets forth the criteria by which the Federal Insurance Administrator will determine the adequacy...

  7. Falcon: automated optimization method for arbitrary assessment criteria

    DOE Patents [OSTI]

    Yang, Tser-Yuan; Moses, Edward I.; Hartmann-Siantar, Christine

    2001-01-01

    FALCON is a method for automatic multivariable optimization for arbitrary assessment criteria that can be applied to numerous fields where outcome simulation is combined with optimization and assessment criteria. A specific implementation of FALCON is for automatic radiation therapy treatment planning. In this application, FALCON implements dose calculations into the planning process and optimizes available beam delivery modifier parameters to determine the treatment plan that best meets clinical decision-making criteria. FALCON is described in the context of the optimization of external-beam radiation therapy and intensity modulated radiation therapy (IMRT), but the concepts could also be applied to internal (brachytherapy) radiotherapy. The radiation beams could consist of photons or any charged or uncharged particles. The concept of optimizing source distributions can be applied to complex radiography (e.g. flash x-ray or proton) to improve the imaging capabilities of facilities proposed for science-based stockpile stewardship.

  8. How to Apply the National Register Criteria for Evaluation

    Broader source: Energy.gov [DOE]

    The National Register of Historic Places is the official list of properties recognized to have national, state, or local significance in American history, architecture, archaeology, engineering, and culture. To guide the selection of properties included in the National Register, the National Park Service (NPS) has developed the National Register Criteria for Evaluation. This bulletin explains how the NPS applies these criteria in evaluating the wide range of properties that may be significant in local, state, and national history. It should be used by anyone who must decide if a particular property qualifies for the National Register.

  9. Photovoltaic module certification/laboratory accreditation criteria development

    SciTech Connect (OSTI)

    Osterwald, C.R. [National Renewable Energy Lab., Golden, CO (United States); Hammond, R.L.; Wood, B.D.; Backus, C.E.; Sears, R.L. [Arizona State Univ., Tempe, AZ (United States); Zerlaut, G.A. [SC-International Inc., Phoenix, AZ (United States); D`Aiello, R.V. [RD Associates, Tempe, AZ (United States)

    1995-04-01

    This document provides an overview of the structure and function of typical product certification/laboratory accreditation programs. The overview is followed by a model program which could serve as the basis for a photovoltaic (PV) module certification/laboratory accreditation program. The model covers quality assurance procedures for the testing laboratory and manufacturer, third-party certification and labeling, and testing requirements (performance and reliability). A 30-member Criteria Development Committee was established to guide, review, and reach a majority consensus regarding criteria for a PV certification/laboratory accreditation program. Committee members represented PV manufacturers, end users, standards and codes organizations, and testing laboratories.

  10. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA, JUNE 2006

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE

    2006-06-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  11. Durability-Based Design Criteria for a Quasi-Isotropic Carbon-Fiber Automotive Composite

    SciTech Connect (OSTI)

    Corum, J.M.

    2002-04-17

    This report provides recommended durability-based design properties and criteria for a quasi-isotropic carbon-fiber composite for possible automotive structural applications. The composite, which was made by a rapid molding process suitable for high-volume automotive applications, consisted of continuous Thornel T300 fibers (6K tow) in a Baydur 420 IMR urethane matrix. The reinforcement was in the form of four {+-}45{sup o} stitch-bonded mats in the following layup: [0/90{sup o}/{+-}45{sup o}]{sub S}. This material is the second in a progression of three candidate thermoset composites to be characterized and modeled as part of an Oak Ridge National Laboratory project entitled Durability of Carbon-Fiber Composites. The overall goal of the project, which is sponsored by the U.S. Department of Energy's Office of Advanced Automotive Technologies and is closely coordinated with the industry Automotive Composites Consortium, is to develop durability-driven design data and criteria to assure the long-term integrity of carbon-fiber-based composite systems for large automotive structural components. This document is in two parts. Part I provides the design criteria, and Part 2 provides the underlying experimental data and models. The durability issues addressed include the effects on deformation, strength, and stiffness of cyclic and sustained loads, operating temperature, automotive fluid environments, and low-energy impacts (e.g., tool drops and kickups of roadway debris). Guidance is provided for design analysis, time-dependent allowable stresses, rules for cyclic loadings, and damage tolerance design guidance, including the effects of holes. Chapter 6 provides a brief summary of the design criteria.

  12. SOIL VAPOR EXTRACTION SYSTEM DESIGN: A CASE STUDY COMPARING VACUUM AND POREGAS VELOCITY CUTOFF CRITERIA

    SciTech Connect (OSTI)

    Dixon, K; Ralph Nichols, R

    2006-07-24

    Soil vapor extraction (SVE) systems are typically designed based on the results of a vadose zone pumping test (transient or steady state) using a pressure criteria to establish the zone of influence (ZOI). A common problem associated with pressure based SVE design is overestimating the ZOI of the extraction well. The vacuum criteria commonly used to establish the boundary of the ZOI results in large areas with very low pore velocities and thus long cleanup times. As a result, design strategies based upon critical pore gas velocity (CPGV) have increased in popularity. The CPGV is used in an effort to loosely incorporate the effects of mass transfer limitations into the design of SVE systems. Critical pore gas velocity designs use a minimum pore gas velocity rather than minimum vacuum to identify the extent of the treatment zone of an SVE system. The CPGV is typically much larger than the pore gas velocity at the perimeter of vacuum based (ZOI) designs resulting in shorter cleanup times. In this paper, we report the results of testing performed at the Savannah River Site (SRS) to determine the influence of a vapor extraction well based upon both a pressure and pore gas velocity design criteria. Results from this testing show that a SVE system designed based upon a CPGV is more robust and will have shorter cleanup times due to increased flow throughout the treatment zone. Pressure based SVE design may be appropriate in applications where soil gas containment is the primary objective; however, in cases where the capture and removal of contaminated soil gas is the primary objective, CPGV is a better design criteria.

  13. Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

    Broader source: Energy.gov [DOE]

    Supporting Technical Document for the Radiological Release Accident Investigation Report (Phase II Report)

  14. Data Quality Objectives for WTP Feed Acceptance Criteria - 12043

    SciTech Connect (OSTI)

    Arakali, Aruna V.; Benson, Peter A.; Duncan, Garth; Johnston, Jill C.; Lane, Thomas A.; Matis, George; Olson, John W.; Banning, Davey L.; Greer, Daniel A.; Seidel, Cary M.; Thien, Michael G.

    2012-07-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is under construction for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (contract no. DE-AC27-01RV14136). The plant when completed will be the world's largest nuclear waste treatment facility. Bechtel and URS are tasked with designing, constructing, commissioning, and transitioning the plant to the long term operating contractor to process the legacy wastes that are stored in underground tanks (from nuclear weapons production between the 1940's and the 1980's). Approximately 56 million gallons of radioactive waste is currently stored in these tanks at the Hanford Site in southeastern Washington. There are three major WTP facilities being constructed for processing the tank waste feed. The Pretreatment (PT) facility receives feed where it is separated into a low activity waste (LAW) fraction and a high level waste (HLW) fraction. These fractions are transferred to the appropriate (HLW or LAW) facility, combined with glass former material, and sent to high temperature melters for formation of the glass product. In addition to PT, HLW and LAW, other facilities in WTP include the Laboratory (LAB) for analytical services and the Balance of Facilities (BOF) for plant maintenance, support and utility services. The transfer of staged feed from the waste storage tanks and acceptance in WTP receipt vessels require data for waste acceptance criteria (WAC) parameters from analysis of feed samples. The Data Quality Objectives (DQO) development was a joint team effort between WTP and Tank Operations Contractor (TOC) representatives. The focus of this DQO effort was to review WAC parameters and develop data quality requirements, the results of which will determine whether or not the staged feed can be transferred from the TOC to WTP receipt vessels. The approach involved systematic planning for data collection consistent with EPA guidance for the seven-step DQO process. Data quality requirements for sample collection and analysis of all WAC parameters were specified during the DQO process. There were eighteen key parameters identified with action limits to ensure the feed transfer and receipt would not exceed plant design, safety, permitting, and processing requirements. The remaining WAC parameters were grouped in the category for obtaining data according to WTP contract specifications, regulatory reporting requirements, and for developing the feed campaign processing sequence. (authors)

  15. Waste acceptance criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    NONE

    1996-04-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

  16. Criteria Review and Approach Documents, National Nuclear Security Administration

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2A "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of National Nuclear Security Administration Criteria Review and Approach Documents (CRADS). CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs.

  17. Criteria & Review Approach Documents, National Nuclear Security Administration

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2A "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of a table of National Nuclear Security Administration Criteria Review and Approach Documents (CRADS) with links to the CRADs. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs.

  18. Interim performance criteria for photovoltaic energy systems. [Glossary included

    SciTech Connect (OSTI)

    DeBlasio, R.; Forman, S.; Hogan, S.; Nuss, G.; Post, H.; Ross, R.; Schafft, H.

    1980-12-01

    This document is a response to the Photovoltaic Research, Development, and Demonstration Act of 1978 (P.L. 95-590) which required the generation of performance criteria for photovoltaic energy systems. Since the document is evolutionary and will be updated, the term interim is used. More than 50 experts in the photovoltaic field have contributed in the writing and review of the 179 performance criteria listed in this document. The performance criteria address characteristics of present-day photovoltaic systems that are of interest to manufacturers, government agencies, purchasers, and all others interested in various aspects of photovoltaic system performance and safety. The performance criteria apply to the system as a whole and to its possible subsystems: array, power conditioning, monitor and control, storage, cabling, and power distribution. They are further categorized according to the following performance attributes: electrical, thermal, mechanical/structural, safety, durability/reliability, installation/operation/maintenance, and building/site. Each criterion contains a statement of expected performance (nonprescriptive), a method of evaluation, and a commentary with further information or justification. Over 50 references for background information are also given. A glossary with definitions relevant to photovoltaic systems and a section on test methods are presented in the appendices. Twenty test methods are included to measure performance characteristics of the subsystem elements. These test methods and other parts of the document will be expanded or revised as future experience and needs dictate.

  19. Durability-based design criteria for an automotive structural composite

    SciTech Connect (OSTI)

    Corum, J.M.; Battiste, R.L.; Brinkman, C.R.; Ren, W.; Ruggles, M.B.; Yahr, G.T.

    1998-11-01

    Before composite structures can be widely used in automotive applications, their long-term durability must be assured. The Durability of Lightweight Composite Structures Project at Oak Ridge National Laboratory was established by the US Department of Energy to help provide that assurance. The project is closely coordinated with the Automotive Composites Consortium. The experimentally-based, durability-driven design criteria described in this paper are the result of the initial project thrust. The criteria address a single reference composite, which is an SRIM (Structural Reaction Injection Molded) polyurethane, reinforced with continuous strand, swirl-mat E-glass fibers. The durability issues addressed include the effects of cyclic and sustained loadings, temperature, automotive fluid environments, and low-energy impacts (e.g., tool drops and roadway kickups) on strength, stiffness, and deformation. The criteria provide design analysis guidance, a multiaxial strength criterion, time-independent and time-dependent allowable stresses, rules for cyclic loading, and damage tolerance design guidance. Environmental degradation factors and the degrading effects of prior loadings are included. Efforts are currently underway to validate the criteria by application to a second random-glass-fiber composite. Carbon-fiber composites are also being addressed.

  20. Design Criteria for Bagless Transfer System (BTS) Packaging System

    SciTech Connect (OSTI)

    RISENMAY, H.R.

    2000-04-26

    This document provides the criteria for the design and installation of a Bagless Transfer System (BTS); Blend, Sieve and Balance Equipment; and Supercritical Fluid Extraction System (SFE). The project consists of 3 major modules: (1) Bagless Transfer System (BTS) Module; (2) Blend, Sieve and Balance Equipment; and (3) Supercritical Fluid Extraction (SFE) Module.

  1. Earthquake design criteria for small hydro projects in the Philippines

    SciTech Connect (OSTI)

    Martin, P.P.; McCandless, D.H.; Asce, M.

    1995-12-31

    The definition of the seismic environment and seismic design criteria of more than twenty small hydro projects in the northern part of the island of Luzon in the Philippines took a special urgency on the wake of the Magnitude 7.7 earthquake that shook the island on July 17, 1990. The paper describes the approach followed to determine design shaking level criteria at each hydro site consistent with the seismic environment estimated at that same site. The approach consisted of three steps: (1) Seismicity: understanding the mechanisms and tectonic features susceptible to generate seismicity and estimating the associated seismicity levels, (2) Seismic Hazard: in the absence of an accurate historical record, using statistics to determine the expected level of ground shaking at a site during the operational 100-year design life of each Project, and (3) Criteria Selection: finally and most importantly, exercising judgment in estimating the final proposed level of shaking at each site. The resulting characteristics of estimated seismicity and seismic hazard and the proposed final earthquake design criteria are provided.

  2. Criteria and Guidelines for the Federal Energy and Water Management Awards

    Broader source: Energy.gov [DOE]

    Document outlines the 2015 criteria and guidelines for the Federal Energy and Water Management Awards.

  3. Multi-attribute criteria applied to electric generation energy system analysis LDRD.

    SciTech Connect (OSTI)

    Kuswa, Glenn W.; Tsao, Jeffrey Yeenien; Drennen, Thomas E.; Zuffranieri, Jason V.; Paananen, Orman Henrie; Jones, Scott A.; Ortner, Juergen G.; Brewer, Jeffrey D.; Valdez, Maximo M.

    2005-10-01

    This report began with a Laboratory-Directed Research and Development (LDRD) project to improve Sandia National Laboratories multidisciplinary capabilities in energy systems analysis. The aim is to understand how various electricity generating options can best serve needs in the United States. The initial product is documented in a series of white papers that span a broad range of topics, including the successes and failures of past modeling studies, sustainability, oil dependence, energy security, and nuclear power. Summaries of these projects are included here. These projects have provided a background and discussion framework for the Energy Systems Analysis LDRD team to carry out an inter-comparison of many of the commonly available electric power sources in present use, comparisons of those options, and efforts needed to realize progress towards those options. A computer aid has been developed to compare various options based on cost and other attributes such as technological, social, and policy constraints. The Energy Systems Analysis team has developed a multi-criteria framework that will allow comparison of energy options with a set of metrics that can be used across all technologies. This report discusses several evaluation techniques and introduces the set of criteria developed for this LDRD.

  4. Summary of comments received from workshops on radiological criteria for decommissioning

    SciTech Connect (OSTI)

    Caplin, J.; Page, G.; Smith, D.; Wiblin, C.

    1994-01-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for site cleanup and decommissioning of NRC-licensed facilities. Open public meetings were held during 1993 in Chicago, IL, San Francisco, CA, Boston, MA, Dallas, TX, Philadelphia, PA, Atlanta, GA, and Washington, DC. Interested parties were invited to provide input on the rulemaking issues before the NRC staff develops a draft proposed rule. This report summarizes 3,635 comments categorized from transcripts of the seven workshops and 1,677 comments from 100 NRC docketed letters from individuals and organizations. No analysis or response to the comments is included. The comments reflect a broad spectrum of viewpoints on the issues related to radiological criteria for site cleanup and decommissioning. The NRC also held public meetings on the scope of the Generic Environmental Impact Statement (GEIS) during July 1993. The GEIS meetings were held in Washington, DC., San Francisco, CA, Oklahoma City, OK, and Cleveland, OH. Related comments from these meetings were reviewed and comments which differed substantially from those from the workshops are also summarized in the body of the report. A summary of the comments from the GEIS scoping meetings is included as an Appendix.

  5. Guide to nondestructive assay standards: Preparation criteria, availability, and practical considerations

    SciTech Connect (OSTI)

    Stewart, J.E.; Hsue, S.T.; Sampson, T.E.

    1997-10-01

    For certification and measurement control, nondestructive assay (NDA) instruments and methods used for verification measurement of special nuclear materials (SNMs) require calibrations based on certified reference materials (CRMs), or working reference materials (WRMs), traceable to the national system of measurements, and adequately characteristic of the unknowns. The Department of Energy Office of Safeguards and Security is sponsoring production of a comprehensive guide to preparation of NDA standards. The scope of the report includes preparation criteria, current availability of CRMs and WRMs, practical considerations for preparation and characterization, and an extensive bibliography. In preparing the report, based primarily on experience at Los Alamos, we have found that standards preparation is highly dependent on the particular NDA method being applied. We therefore include sections that contain information specific to commonly used neutron and gamma-ray NDA techniques. 16 refs., 4 figs., 2 tabs.

  6. Guide to nondestructive assay standards: Preparation criteria, availability, and practical considerations

    SciTech Connect (OSTI)

    Hsue, S.T.; Stewart, J.E.; Sampson, T.E.; Butler, G.W.; Rudy, C.R.; Rinard, P.M.

    1997-10-01

    For certification and measurement control, nondestructive assay (NDA) instruments and methods used for verification measurements of special nuclear materials (SNMs) require calibrations based on certified reference materials (CRMs), or working reference materials (WRMs), traceable to the national system of measurements, and adequately characteristic of the unknowns. The Department of Energy Office of Safeguards and Security is sponsoring production of a comprehensive guide to preparation of NDA standards. The scope of the report includes preparation criteria, current availability of CRMs and WRMs, practical considerations for preparation and characterization, and an extensive bibliography. In preparing the report, based primarily on experience at Los Alamos, they have found that standards preparation is highly dependent on the particular NDA method being applied. They therefore include sections that contain information specific to commonly used neutron and gamma-ray NDA techniques. They also present approaches that are alternatives to, or minimize requirements for physical standards.

  7. Self-Consistent Criteria for Evaluation of Neutron Interaction

    SciTech Connect (OSTI)

    Henry H.F,Newlon C.E.,Knight J.R.

    2007-08-02

    New safe interaction criteria for containers of fissionable materials handled at the Oak Ridge Gaseous Diffusion Plant have been developed on the basis of an interaction theory using the basic concepts of a safe solid angle subtended by interacting containers, and the multiplication factor as determined by two-group theory for an individually safe containers The calculated results agree satisfactorily with experimental data obtained with identical interacting units involving both cylinders and slabs containing highly enriched uranium, the core compositions of which were varied between H/U-235 atomic ratios of 44.3 and 337. The application of the derived interaction criteria to items containing material with low moderation or low U-235 assay, and to containers for which nuclear safety is dependent upon control of the U-235 mass or U-235 concentration is discussed.

  8. Development of thermal performance criteria for residential passive solar buildings

    SciTech Connect (OSTI)

    Sabatiuk, P.A.; Cassel, D.E.; McCabe, M.; Scarbrough, C.

    1980-01-01

    In support of the development of thermal performance criteria for residential passive solar buildings, thermal design characteristics and anticipated performance for 266 projects in the HUD Passive Residential Design Competition and the HUD Cycle 5 Demonstration Program were analyzed. These passive residences are located in all regions of the United States requiring space heating, and they represent a variety of passive solar system types including direct gain, indirect gain, and solarium (isolated gain) systems. The results of this statistical analysis are being used to develop proposed minimum acceptable levels of thermal performance for passive solar buildings for the residential performance criteria. A number of performance measures were examined, including net solar contribution, solar fraction, and auxiliary energy use. These and other design and climate-related parameters were statistically correlated using the DATAPLOT computer program and standard statistical analysis techniques.

  9. Berkeley Lab scientists develop criteria for $20 million energy challenge

    ScienceCinema (OSTI)

    Walker, Iain

    2013-05-29

    Berkeley Labs Iain Walker and his colleagues in environmental energy research helped the Siebel Foundation develop the criteria for its Energy Free Home Challenge, which comes with a $20 million global incentive prize. The Challenge is a competition to create a new generation of systems and technologies for practical homes that realize a net-zero, non-renewable energy footprint without increasing the cost of ownership. It is open to everyone everywhere ? university teams to handymen and hobbyists.

  10. UNDERSTANDING SEISMIC DESIGN CRITERIA FOR JAPANESE NUCLEAR POWER PLANTS

    Office of Scientific and Technical Information (OSTI)

    UNDERSTANDING SEISMIC DESIGN CRITERIA FOR JAPANESE NUCLEAR POWER PLANTS Y.J. Park and C.H. Hofmayer Brookhaven National Laboratory Upton, Long Island, New York 11973 J.F. Costello U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ABSTRACT This paper summarizes the results of recent survey studies on the seismic design practice for nuclear power plants in Japan. The seismic design codes and standards for both nuclear as well as non- nuclear structures have been reviewed and summarized.

  11. Berkeley Lab scientists develop criteria for $20 million energy challenge

    SciTech Connect (OSTI)

    Walker, Iain

    2009-01-01

    Berkeley Labs Iain Walker and his colleagues in environmental energy research helped the Siebel Foundation develop the criteria for its Energy Free Home Challenge, which comes with a $20 million global incentive prize. The Challenge is a competition to create a new generation of systems and technologies for practical homes that realize a net-zero, non-renewable energy footprint without increasing the cost of ownership. It is open to everyone everywhere university teams to handymen and hobbyists.

  12. Evaluation of ISDP Batch 2 Qualification Compliance to 512-S, DWPF, Tank Farm, and Saltstone Waste Acceptance Criteria

    SciTech Connect (OSTI)

    Shafer, A.

    2010-05-05

    The purpose of this report is to document the acceptability of the second macrobatch (Salt Batch 2) of Tank 49H waste to H Tank Farm, DWPF, and Saltstone for operation of the Interim Salt Disposition Project (ISDP). Tank 49 feed meets the Waste Acceptance Criteria (WAC) requirements specified by References 11, 12, and 13. Salt Batch 2 material is qualified and ready to be processed through ARP/MCU to the final disposal facilities.

  13. Structural Design Criteria for Anion Hosts: Strategies for Achieving Anion Shape Recognition through the Complementary Placement of Urea Donor Groups

    SciTech Connect (OSTI)

    Hay, Benjamin P.; Firman, Timothy K.; Moyer, Bruce A.

    2005-02-16

    The arrangement of urea ligands about different shaped anions has been evaluated with electronic structure calculations. Geometries and binding energies are reported for urea complexes with Cl{sup -}, NO{sub 3}{sup -}, and ClO{sub 4}{sup -}. The results yield new insight into the nature of urea-anion interactions and provide structural criteria for the deliberate design of anion selective receptors containing two or more urea donor groups.

  14. A new approach to criteria for health risk assessment

    SciTech Connect (OSTI)

    Spickett, Jeffery; Katscherian, Dianne; Goh, Yang Miang

    2012-01-15

    Health Impact Assessment (HIA) is a developing component of the overall impact assessment process and as such needs access to procedures that can enable more consistent approaches to the stepwise process that is now generally accepted in both EIA and HIA. The guidelines developed during this project provide a structured process, based on risk assessment procedures which use consequences and likelihood, as a way of ranking risks to adverse health outcomes from activities subjected to HIA or HIA as part of EIA. The aim is to assess the potential for both acute and chronic health outcomes. The consequences component also identifies a series of consequences for the health care system, depicted as expressions of financial expenditure and the capacity of the health system. These more specific health risk assessment characteristics should provide for a broader consideration of health consequences and a more consistent estimation of the adverse health risks of a proposed development at both the scoping and risk assessment stages of the HIA process. - Highlights: Black-Right-Pointing-Pointer A more objective approach to health risk assessment is provided. Black-Right-Pointing-Pointer An objective set of criteria for the consequences for chronic and acute impacts. Black-Right-Pointing-Pointer An objective set of criteria for the consequences on the health care system. Black-Right-Pointing-Pointer An objective set of criteria for event frequency that could impact on health. Black-Right-Pointing-Pointer The approach presented is currently being trialled in Australia.

  15. Comments received on proposed rule on radiological criteria for decommissioning and related documents

    SciTech Connect (OSTI)

    Page, G.; Caplin, J.; Smith, D.

    1996-03-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC-licensed facilities. As a part of this action, the Commission published in the Federal Register (59 FR 43200), on August 22, 1994, a proposed rule on radiological criteria for decommissioning, soliciting comments both on the rule as proposed and on certain specific items as identified in its supplementary statement of considerations. A draft Generic Environmental Impact Statement (GEIS) in support of the rule, also published in August 1994 as NUREG-1496, along with its Appendix A (NUREG-1501), were also made available for comment. A staff working draft on regulatory guidance (NUREG-1500)was also made available. This report summarizes the 1,309 comments on the proposed rule and supplementary items and the 311 comments on the GEIS as excerpted from 101 docketed letters received associated in the Federal/Register notice. Comments from two NRC/Agreement-States meetings are also summarized.

  16. Wind load comparison for the ASCE standard 7 and the Hanford site design criteria

    SciTech Connect (OSTI)

    Giller, R.A., Westinghouse Hanford

    1996-07-16

    This document provides calculations and discussions to compare Hanford Site wind load criteria with the current national standard for wind loads (ASCE 7, 1995). Site criteria uses the 1988 edition ASCE 7.

  17. Experimental aspects of an investigation of macroscopic ductile failure criteria

    SciTech Connect (OSTI)

    Soo Hoo, M.S.; Benzley, S.E.; Priddy, T.G.

    1981-03-01

    Experimental results for the ductile failure of 7075-T651 aluminum are presented. Four separate shapes were tested to investigate the importance that macroscopic effective shear stress, hydrostatic stress, and plastic strain play in describing ductile failure of materials. The specimens used were: thin wall torsion tubes to create a state of pure shear, uniform hollow tubes to create a state of uniaxial stress; hour-glass shaped hollow tubes to create a state of biaxial stress; and notched round bars to create a state of triaxial stress. Two proposed ductile failure criteria are discussed in conjunction with the experimental results presented.

  18. DOE-STD-1066-99; Fire Protection Design Criteria

    Energy Savers [EERE]

    6-99 July 1999 Superseding DOE-STD-1066-97 DOE STANDARD FIRE PROTECTION DESIGN CRITERIA U.S. Department of Energy AREA FIRP Washington, D.C. 20585 DISTRIBUTION STATEMENT. Approved for public release; distribution is unlimited. This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce,

  19. Criteria for the evaluation of a dilute decontamination demonstration

    SciTech Connect (OSTI)

    FitzPatrick, V.F.; Divine, J.R.; Hoenes, G.R.; Munson, L.F.; Card, C.J.

    1981-12-01

    This document provides the prerequisite technical information required to evaluate and/or develop a project to demonstrate the dilute chemical decontamination of the primary coolant system of light water reactors. The document focuses on five key areas: the basis for establishing programmatic prerequisites and the key decision points that are required for proposal evaluation and/or RFP (Request for Proposal) issuance; a technical review of the state-of-the-art to identify the potential impacts of a reactor's primary-system decontamination on typical BWR and PWR plants; a discussion of the licensing, recertification, fuel warranty, and institutional considerations and processes; a preliminary identification and development of the selection criteria for the reactor and the decontamination process; and a preliminary identification of further research and development that might be required.

  20. Fusion Blanket Coolant Section Criteria, Methodology, and Results

    SciTech Connect (OSTI)

    DeMuth, J. A.; Meier, W. R.; Jolodosky, A.; Frantoni, M.; Reyes, S.

    2015-10-02

    The focus of this LDRD was to explore potential Li alloys that would meet the tritium breeding and blanket cooling requirements but with reduced chemical reactivity, while maintaining the other attractive features of pure Li breeder/coolant. In other fusion approaches (magnetic fusion energy or MFE), 17Li- 83Pb alloy is used leveraging Pb’s ability to maintain high TBR while lowering the levels of lithium in the system. Unfortunately this alloy has a number of potential draw-backs. Due to the high Pb content, this alloy suffers from very high average density, low tritium solubility, low system energy, and produces undesirable activation products in particular polonium. The criteria considered in the selection of a tritium breeding alloy are described in the following section.

  1. Methods and criteria for safety analysis (FIN L2535)

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    In response to the NRC request for a proposal dated October 20, 1992, Westinghouse Savannah River Company (WSRC) submit this proposal to provide contractural assistance for FIN L2535, ``Methods and Criteria for Safety Analysis,`` as specified in the Statement of Work attached to the request for proposal. The Statement of Work involves development of safety analysis guidance for NRC licensees, arranging a workshop on this guidance, and revising NRC Regulatory Guide 3.52. This response to the request for proposal offers for consideration the following advantages of WSRC in performing this work: Experience, Qualification of Personnel and Resource Commitment, Technical and Organizational Approach, Mobilization Plan, Key Personnel and Resumes. In addition, attached are the following items required by the NRC: Schedule II, Savannah River Site - Job Cost Estimate, NRC Form 189, Project and Budget Proposal for NRC Work, page 1, NRC Form 189, Project and Budget Proposal for NRC Work, page 2, Project Description.

  2. Labs21 environmental performance criteria Version 2.0

    SciTech Connect (OSTI)

    Mathew, Paul A.

    2002-10-01

    Laboratory facilities present a unique challenge for energy efficient and sustainable design, with their inherent complexity of systems, health and safety requirements, long-term flexibility and adaptability needs, energy use intensity, and environmental impacts. The typical laboratory is about five times as energy intensive as a typical office building and costs about three times as much per unit area. The Labs21 Environmental Performance Criteria (EPC) is a rating system for use by laboratory building project stakeholders to assess the environmental performance of laboratory facilities. Currently, the U.S. Green Building Council's LEED{trademark} Rating System is the primary tool used. However, LEED{trademark} was designed for U.S. commercial office buildings and as such, lacks some attributes essential to the sustainable design of this unique and complex building type. To facilitate widespread use and to avoid ''re-inventing the wheel'' this effort builds on the existing LEED{trademark} Rating System 2.0.

  3. Final Report - Spent Nuclear Fuel Retrieval System Manipulator System Cold Validation Testing

    SciTech Connect (OSTI)

    D.R. Jackson; G.R. Kiebel

    1999-08-24

    Manipulator system cold validation testing (CVT) was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington. The FRS will be used to retrieve and repackage K-Basin Spent Nuclear Fuel (SNF) currently stored in old K-Plant storage basins. The FRS is required to retrieve full fuel canisters from the basin; clean the fuel elements inside the canister to remove excessive uranium corrosion products (or sludge); remove the contents from the canisters; and sort the resulting debris, scrap, and fuel for repackaging. The fuel elements and scrap will be collected in fuel storage and scrap baskets in preparation for loading into a multi canister overpack (MCO), while the debris is loaded into a debris bin and disposed of as solid waste. The FRS is composed of three major subsystems. The Manipulator Subsystem provides remote handling of fuel, scrap, and debris; the In-Pool Equipment subsystem performs cleaning of fuel and provides a work surface for handling materials; and the Remote Viewing Subsystem provides for remote viewing of the work area by operators. There are two complete and identical FRS systems, one to be installed in the K-West basin and one to be installed in the K-East basin. Another partial system will be installed in a cold test facility to provide for operator training.

  4. Criteria for Evaluation of Nuclear Facility Training Programs

    Office of Environmental Management (EM)

    ... IAEA-TECHNICAL REPORT SERIES No. 380, NUCLEAR POWER PLANT PERSONNEL TRAINING AND ITS ... be organized Page 15Section 7 Any safety violations observed during the ...

  5. Enforcement Guidance Supplement 03-02: Revision to Occurrence Report-Based Noncompliance Tracking System Reporting Criteria

    Broader source: Energy.gov [DOE]

    Section 1.3 of the Operational Procedures for Enforcement, published in June 1998, provides the opportunity for the Office of Price-Anderson Enforcement (OE) to periodically issue clarifying guidance regarding the processes used in its enforcement activities. OE typically issues such guidance in the form of Enforcement Guidance Supplements (EGS), which provide information or recommendations only and impose no requirements or actions on Department of Energy (DOE) contractors.

  6. Metalcasting competitiveness research. Final report

    SciTech Connect (OSTI)

    Piwonka, T.S.

    1994-08-01

    This report comprises eleven separate reports: prediction of non- metallic particle distribution, electromagnetic separation of inclusions from molten Al alloy, clean steel castings, waste stream identification and treatment, elastic wave lithotripsy for removal of ceramic from investment castings, metal penetration in sand molds, mold-metal interface gas composition, improved Alloy 718, specifications for iron oxide additions to no-bake sands, criteria functions for defect prediction, and computer-aided cooling curve analysis.

  7. Concepts and criteria for evaluating topsoil substitutes: The Texas experience

    SciTech Connect (OSTI)

    Askenasy, P.; Senkayi, A.L.; Joseph, W.L.

    1997-12-31

    Presented in this paper are: (1) historical background, (2) Federal and State regulatory basis and authority, and (3) justification for selected criteria and parameters which are currently used to evaluate the quality of topsoil-substitute materials and postmine soils in Texas. The specific parameters and concepts discussed include (1) acid- and toxic-forming materials (AFM and TFM), (2) quantification procedures for AFM and TFM, (3) procedures used to identify topsoil substitutes that are {open_quotes}equal to or more suitable than{close_quotes} existing premine native soils, and (4) current interpretations of what is meant by {open_quotes}the best available material to support revegetation{close_quotes} of surface-mined areas. To support these interpretations, reference is made throughout the paper to relevant sections of the (1) Texas Coal Mining Regulations (TCMR), (2) Surface Mining Control and Reclamation Act (SMCRA), and (3) Federal regulations promulgated by the Office of Surface Mining (OSM) to implement SMCRA. The success of the Texas reclamation program, as indicated by the quality of the reclaimed soils is also discussed. This success is partly attributed to the rigorous application of the quantification concepts and parameters discussed in this paper.

  8. U.S. Department of Energy Implements Criteria for ENERGY STAR® Water

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

    Heaters | Department of Energy Criteria for ENERGY STAR® Water Heaters U.S. Department of Energy Implements Criteria for ENERGY STAR® Water Heaters April 1, 2008 - 2:48pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced new ENERGY STAR® criteria for water heaters, the first in the history of the program. According to DOE projections, by the end of the fifth year in effect, the new water heater criteria are expected to save Americans approximately $780 million

  9. DOE-STD-101-92; Compilation of Nuclear Safety Criteria Potential...

    Energy Savers [EERE]

    Criteria Classification of Structures, Components, Equipment and Systems Wind and Tornado Loadings Water Level ... RADIOACTIVE WASTE MANAGEMENT RADIATION PROTECTION 8.1 Assuring ...

  10. WSRC-MS-94-0605 Wall Thinning Acceptance Criteria for Degraded...

    Office of Scientific and Technical Information (OSTI)

    was developed during the course of work under Contract No. ... South Carolina 29802 ABSTRACT As part of the structural ... The current acceptance criteria will provide first ...

  11. WIPP Status Report Waste Isolation Pilot Plant

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

    Status Report Waste Isolation Pilot Plant Page 1 of 3 Report Statistics Report Version: 2.4.3 WDS Instance: prd05.wipp.carlsbad.nm.us Generated on: June 24, 2015 7:29 AM Generated by: REPORT, WEEKLY Total Pages: 3 Selection Criteria Reporting Date (As Of): 06/20/2015 Include Detail: No WIPP Status Report REPORT, WEEKLY June 24, 2015 7:29 AM Page 2 of 3 Waste Isolation Pilot Plant As of 06/20/15 SHIPMENTS and VOLUME RECEIVED AT WIPP Site Last Week (06/07/15- 06/13/15) Current Week (06/14/15-

  12. Waste management project's alternatives: A risk-based multi-criteria assessment (RBMCA) approach

    SciTech Connect (OSTI)

    Karmperis, Athanasios C.; Sotirchos, Anastasios; Aravossis, Konstantinos; Tatsiopoulos, Ilias P.

    2012-01-15

    Highlights: Black-Right-Pointing-Pointer We examine the evaluation of a waste management project's alternatives. Black-Right-Pointing-Pointer We present a novel risk-based multi-criteria assessment (RBMCA) approach. Black-Right-Pointing-Pointer In the RBMCA the evaluation criteria are based on the quantitative risk analysis of the project's alternatives. Black-Right-Pointing-Pointer Correlation between the criteria weight values and the decision makers' risk preferences is examined. Black-Right-Pointing-Pointer Preference to the multi-criteria against the one-criterion evaluation process is discussed. - Abstract: This paper examines the evaluation of a waste management project's alternatives through a quantitative risk analysis. Cost benefit analysis is a widely used method, in which the investments are mainly assessed through the calculation of their evaluation indicators, namely benefit/cost (B/C) ratios, as well as the quantification of their financial, technical, environmental and social risks. Herein, a novel approach in the form of risk-based multi-criteria assessment (RBMCA) is introduced, which can be used by decision makers, in order to select the optimum alternative of a waste management project. Specifically, decision makers use multiple criteria, which are based on the cumulative probability distribution functions of the alternatives' B/C ratios. The RBMCA system is used for the evaluation of a waste incineration project's alternatives, where the correlation between the criteria weight values and the decision makers' risk preferences is analyzed and useful conclusions are discussed.

  13. Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE

    Energy Savers [EERE]

    Facilities (Proposed) | Department of Energy Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities (Proposed) Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities (Proposed) Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities (Proposed) Quazi Hossain, LLNL Joe Hunt, BWXT/Y-12 Robert Kennedy, RPK Consulting Carl Mazzola, Shaw Environmental, Inc. Steve McDuffie, DOE Gerald Meyers, DOE DOE Natural

  14. DOE Standard 1020- Natural Phenomena Hazard analysis and Design Criteria for DOE Facilities

    Broader source: Energy.gov [DOE]

    Department of Energy (DOE) Standard (STD)-1020-2012, Natural Phenomena Hazards Analysis and Design Criteria for DOE Facilities, provides criteria and guidance for the analysis and design of facility structures, systems, and components (SSCs) that are necessary to implement the requirements of DOE Order (O) 420.1C, Facility Safety, and to ensure that the SSCs will be able to effectively perform their intended safety functions under the effects of natural phenomena hazards (NPHs). This Standard also provides criteria and guidance for the use of industry building codes and voluntary consensus standards in the NPH analysis and design of SSCs in DOE facilities.

  15. Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria...

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

    Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities (Proposed) Quazi Hossain, LLNL Joe Hunt, BWXTY-12 Robert Kennedy, RPK Consulting Carl Mazzola, ...

  16. DOE-STD-0100T; DOE Standard Licensed Reactor Nuclear Safety Criteria...

    Energy Savers [EERE]

    ... Systems and Safety Criteria 7.2 Reactor Trip System ... RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 11.2 Liquid Waste ... Exposures Are As Low As Reasonably Achievable ...

  17. WSRC-MS-94-0605 Wall Thinning Acceptance Criteria for Degraded...

    Office of Scientific and Technical Information (OSTI)

    WSRC-MS-94-0605 Wall Thinning Acceptance Criteria for Degraded Carbon Steel Piping Systems Using FAD Methodology (U) by P. S. Lam Westinghouse Savannah River Company Savannah River ...

  18. Example Procedures for Developing Acceptance-Range Criteria for BESTEST-EX

    SciTech Connect (OSTI)

    Ron Judkoff, Ben Polly, Marcus Bianchi

    2010-08-01

    This document provides an example procedure for establishing acceptance-range criteria to assess results from software undergoing BESTEST-EX. This example method for BESTEST-EX is a modified version of the method described in HERS BESTEST.

  19. Title 43 CFR 1610.4-2 Development of Planning Criteria | Open...

    Open Energy Info (EERE)

    LibraryAdd to library Legal Document- Federal RegulationFederal Regulation: Title 43 CFR 1610.4-2 Development of Planning CriteriaLegal Abstract 1610.4-2 Development of...

  20. Test plan for: TSAP bit qualification: Temperature criteria

    SciTech Connect (OSTI)

    Ralston, G.L.

    1995-10-23

    This is the Test Plan for acquiring TSAP bit temperature performance data. Hanford Site waste tanks are currently being sampled by several methods. One of these, Rotary Mode Core Sampling (RMCS), uses a cutting bit/sample tube arrangement to obtain core samples of tank contents. Recent efforts to improve sample recovery have resulted in a new bit/sample tube design. Prior to field use, bit performance in two key areas needs to be tested. These areas are: penetration into steel plate, and a temperature rise as a function of downforce, rpm, and time. A performance test in the above two areas was conducted in August, 1995. Based on a review of that test activity, selected follow-on testing is planned to confirm data obtained in the temperature area. The results of both test activities will then be released as a single test report.

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

    SciTech Connect (OSTI)

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

    1981-09-01

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

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

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    This DOE standard gives design and evaluation criteria for natural phenomena hazards (NPH) effects as guidance for implementing the NPH mitigation requirements of DOE 5480.28. Goal of the criteria is to assure that DOE facilities can withstand the effects of earthquakes, extreme winds, tornadoes, flooding, etc. They apply to the design of new facilities and the evaluation of existing facilities; they may also be used for modification and upgrading of the latter.

  3. Nuclear Safety Research and Development Proposal Review and Prioritization and Criteria

    Energy Savers [EERE]

    Nuclear Safety Research and Development Proposal Review and Prioritization Process and Criteria Nuclear Safety Research and Development Program Office of Nuclear Safety Office of Environment, Health, Safety, and Security U.S. Department of Energy December 2015 NSR&D Proposal Review and Prioritization Process and Criteria 2 | P a g e Nuclear Safety Research and Development Program 1. Introduction Per the Department of Energy (DOE) Nuclear Safety Research and Development (NSR&D) Program

  4. Natural Phenomena Hazard Analysis and Design Criteria for Department of Energy Facilities

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

    2012-08-03

    This Department of Energy (DOE) Standard (STD)-1020-2012, Natural Phenomena Hazards Analysis and Design Criteria for DOE Facilities, provides criteria and guidance for the analysis and design of facility structures, systems, and components (SSCs) that are necessary to implement the requirements of DOE Order (O) 420.1C, Facility Safety, and to ensure that the SSCs will be able to effectively perform their intended safety functions under the effects of natural phenomena hazards (NPHs).

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

    SciTech Connect (OSTI)

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

    2008-02-28

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

  6. TMACS test procedure TP004: Reporting. Revision 4

    SciTech Connect (OSTI)

    Washburn, S.J.

    1994-08-25

    The TMACS Software Project Test Procedures translate the project`s acceptance criteria into test steps. Software releases are certified when the affected Test Procedures are successfully performed and the customers authorize installation of these changes. This Test Procedure addressed the report generation capability of the TMACS. The features to be tested are generation of the alarm history report, equipment failure report, single-shell tank report and double-shell tank report.

  7. Radiation dose assessment methodology and preliminary dose estimates to support US Department of Energy radiation control criteria for regulated treatment and disposal of hazardous wastes and materials

    SciTech Connect (OSTI)

    Aaberg, R.L.; Baker, D.A.; Rhoads, K.; Jarvis, M.F.; Kennedy, W.E. Jr.

    1995-07-01

    This report provides unit dose to concentration levels that may be used to develop control criteria for radionuclide activity in hazardous waste; if implemented, these criteria would be developed to provide an adequate level of public and worker health protection, for wastes regulated under U.S, Environmental Protection Agency (EPA) requirements (as derived from the Resource Conservation and Recovery Act [RCRA] and/or the Toxic Substances Control Act [TSCA]). Thus, DOE and the US Nuclear Regulatory Commission can fulfill their obligation to protect the public from radiation by ensuring that such wastes are appropriately managed, while simultaneously reducing the current level of dual regulation. In terms of health protection, dual regulation of very small quantities of radionuclides provides no benefit.

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

    SciTech Connect (OSTI)

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

    2008-07-01

    In August 2007, Secretary of Energy Samuel W. Bodman approved the final seismic and ground motion criteria for the Waste Treatment and Immobilization Plant (WTP) at the Department of Energy's (DOE) Hanford Site. Construction of the WTP began in 2002 based on seismic design criteria established in 1999 and a probabilistic seismic hazard analysis completed in 1996. The design criteria were reevaluated in 2005 to address questions from the Defense Nuclear Facilities Safety Board (DNFSB), resulting in an increase by up to 40% in the seismic design basis. DOE announced in 2006 the suspension of construction on the pretreatment and high-level waste vitrification facilities within the WTP to validate the design with more stringent seismic criteria. In 2007, the U.S. Congress mandated that the Secretary of Energy certify the final seismic and ground motion criteria prior to expenditure of funds on construction of these two facilities. With the Secretary's approval of the final seismic criteria in the summer of 2007, DOE authorized restart of construction of the pretreatment and high-level waste vitrification facilities. The technical basis for the certification of seismic design criteria resulted from a two-year Seismic Boreholes Project that planned, collected, and analyzed geological data from four new boreholes drilled to depths of approximately 1400 feet below ground surface on the WTP site. A key uncertainty identified in the 2005 analyses was the velocity contrasts between the basalt flows and sedimentary interbeds below the WTP. The absence of directly-measured seismic shear wave velocities in the sedimentary interbeds resulted in the use of a wider and more conservative range of velocities in the 2005 analyses. The Seismic Boreholes Project was designed to directly measure the velocities and velocity contrasts in the basalts and sediments below the WTP, reanalyze the ground motion response, and assess the level of conservatism in the 2005 seismic design criteria. The characterization and analysis effort included 1) downhole measurements of the velocity properties (including uncertainties) of the basalt/interbed sequences, 2) confirmation of the geometry of the contact between the various basalt and interbedded sediments through examination of retrieved core from the core-hole and data collected through geophysical logging of each borehole, and 3) prediction of ground motion response to an earthquake using newly acquired and historic data. The data and analyses reflect a significant reduction in the uncertainty in shear wave velocities below the WTP and result in a significantly lower spectral acceleration (i.e., ground motion). The updated ground motion response analyses and corresponding design response spectra reflect a 25% lower peak horizontal acceleration than reflected in the 2005 design criteria. These results provide confidence that the WTP seismic design criteria are conservative. (authors)

  9. The use of information technology security assessment criteria to protect specialized computer systems

    SciTech Connect (OSTI)

    Lykov, V.A.; Shein, A.V.; Piskarev, A.S.; Devaney, D.M.; Melton, R.B.; Hunteman, W.J.; Prommel, J.M.; Rothfuss, J.S.

    1997-10-01

    The purpose of this paper is to discuss the information security assessment criteria used in Russia and compare it with that used in the United States. The computer system security assessment criteria utilized by the State Technical Commission of Russia and similar criteria utilized by the US Department of Defense (TCSEC) are intended for the development and implementation of proven methods for achieving a required level of information security. These criteria are utilized, first and foremost, when conducting certification assessments of general purpose systems. The Russian Federation is creating specialized systems for nuclear material control and accountancy (MC and A) within the framework of the international laboratory-to-laboratory collaboration. Depending on the conditions in which the MC and A system is intended to operate, some of the criteria and the attendant certification requirements may exceed those established or may overlap the requirements established for attestation of such systems. In this regard it is possible to modify the certification and attestation requirements depending on the conditions in which a system will operate in order to achieve the ultimate goal--implementation of the systems in the industry.

  10. Worldwide report: Arms control, [July 26, 1986

    SciTech Connect (OSTI)

    1986-07-26

    This report contains translations/transcriptions of articles and/or broadcasts on arms control. Titles include; Soviet Spokesman Explains Far East Arms Cut; Delegation attends Society Naval Exercise; Defense Minister Queried on Military Reductions; Further on Society Force Withdrawals from Poland; Criteria of Military-Strategic Parity, Sufficiency; Further on Allegations of CW Materiel Sale to Iran; Reports on Nuclear, Chemical Warheads Denied; and others.

  11. JPRS report: Arms control, [July 11, 1989

    SciTech Connect (OSTI)

    1989-07-11

    This report contains translations/transcriptions of articles and/or broadcasts on arms control. Titles include: Soviet Spokesman Explains Far East Arms Cut; Delegation Attends Soviet Naval Exercise; Defense Minister Queried on Military Reductions; Further on Soviet Force Withdrawals from Poland; Criteria of Military-Strategic Parity, Sufficiency; Further on Allegations of CW Materiel Sale to Iran; Reports on Nuclear, Chemical Warheads Denied; and others.

  12. Worldwide report: Arms control, [19 July 1985

    SciTech Connect (OSTI)

    1985-07-19

    This report contains translations/transcriptions of articles and/or broadcasts on arms control. Titles include: Soviet Spokesman Explains Far East Arms Cut; Delegation attends Soviet Naval Exercise; Defense Minister Queried on Military Reductions; Further on Soviet Force Withdrawals from Poland; Criteria of Military-Strategic Parity, Sufficiency; Further on Allegations of CW Materiel Sale to Iran; Reports on Nuclear, Chemical Warheads Denied; and others.

  13. Suppression criteria of parasitic mode oscillations in a gyrotron beam tunnel

    SciTech Connect (OSTI)

    Kumar, Nitin; Singh, Udaybir; Sinha, A. K.; Singh, T. P.

    2011-02-15

    This paper presents the design criteria of the parasitic mode oscillations suppression for a periodic, ceramic, and copper loaded gyrotron beam tunnel. In such a type of beam tunnel, the suppression of parasitic mode oscillations is an important design problem. A method of beam-wave coupling coefficient and its mathematical formulation are presented. The developed design criteria are used in the beam tunnel design of a 42 GHz gyrotron to be developed for the Indian TOKAMAK system. The role of the thickness and the radius of the beam tunnel copper rings to obtain the developed design criteria are also discussed. The commercially available electromagnetic code CST and the electron trajectory code EGUN are used for the simulations.

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

    SciTech Connect (OSTI)

    SCHWEHR, B.A.

    1999-08-31

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

  15. Operational readiness review phase-1 final report for WRAP-1

    SciTech Connect (OSTI)

    Bowen, W., Westinghouse Hanford

    1996-12-27

    This report documents the Operational Readiness Review for WRAP-1 Phase-1 operations. The report includes all criteria, lines of inquiry with resulting Findings and Observations. The review included assessing operational capability of the organization and the computer controlled process and facility systems.

  16. How to Apply the National Register Criteria for Evaluation (NPS, 1997)

    Broader source: Energy.gov [DOE]

    The National Register of Historic Places is the official list of properties recognized to have national, state, or local significance in American history, architecture, archaeology, engineering, and culture. To guide the selection of properties included in the National Register, the National Park Service (NPS) has developed the National Register Criteria for Evaluation. This bulletin explains how the NPS applies these criteria in evaluating the wide range of properties that may be significant in local, state, and national history. It should be used by anyone who must decide if a particular property qualifies for the National Register.

  17. How to Apply the National Register Criteria for Evaluation (NPS, 1990, revised 1997)

    Broader source: Energy.gov [DOE]

    The National Register of Historic Places is the official list of properties recognized to have national, state, or local significance in American history, architecture, archaeology, engineering, and culture. To guide the selection of properties included in the National Register, the National Park Service (NPS) has developed the National Register Criteria for Evaluation. This bulletin explains how the NPS applies these criteria in evaluating the wide range of properties that may be significant in local, state, and national history. It should be used by anyone who must decide if a particular property qualifies for the National Register.

  18. Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2009-05-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

  19. Design criteria for the light duty utility arm system end effectors

    SciTech Connect (OSTI)

    Pardini, A.F.

    1995-01-03

    This document provides the criteria for the design of end effectors that will be used as part of the Light Duty Utility Arm (LDUA) System. The LDUA System consists of a deployment vehicle, a vertical positioning mast, a light duty multi-axis robotic arm, a tank riser interface and confinement, a tool interface plate, a control system, and an operations control trailer. The criteria specified in this document will apply to all end effector systems being developed for use on or with the LDUA system at the Hanford site. The requirement stipulated in this document are mandatory.

  20. Monthly Performance Report

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

    ... transition checklist, and acceptance criteria to assess ... Company (CHPRC) and Stevens Center Management. ... northward to the Waste Treatment Plant (WTP) ...

  1. Annual Reports - SRSCRO

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

    reports Annual Reports Annual Report 2015 Annual Report 2014 Annual Report 2013 Annual Report 2012 Annual Report 2011 Annual Report 2010 Annual Report 2009 Annual Report 2008...

  2. Comparison of Test Procedures and Energy Efficiency Criteria in Selected International Standards & Labeling Programs for Copy Machines, External Power Supplies, LED Displays, Residential Gas Cooktops and Televisions

    SciTech Connect (OSTI)

    Zheng, Nina; Zhou, Nan; Fridley, David

    2012-03-01

    This report presents a technical review of international minimum energy performance standards (MEPS), voluntary and mandatory energy efficiency labels and test procedures for five products being considered for new or revised MEPS in China: copy machines, external power supply, LED displays, residential gas cooktops and flat-screen televisions. For each product, an overview of the scope of existing international standards and labeling programs, energy values and energy performance metrics and description and detailed summary table of criteria and procedures in major test standards are presented.

  3. Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

    SciTech Connect (OSTI)

    Dwyer, P.A.

    1991-10-01

    This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material.

  4. Updating of Safety Criteria for Basic Diagnostic Indicators of Dam at the Sayano-Shushenskaya HPP

    SciTech Connect (OSTI)

    Gordon, L. A.; Skvortsova, A. E.

    2013-09-15

    Values of diagnostic indicators [K]-limitations placed on radial displacements and turn angles of horizontal sections of the dam - which are permitted for each upper-pool level within the range from 520 to 539 m are determined and proposed for inclusion in the Declaration of Safety. Empirical relationships used to develop safety criteria K1 and K2 are modified.

  5. Canister storage building compliance assessment SNF project NRC equivalency criteria - HNF-SD-SNF-DB-003

    SciTech Connect (OSTI)

    BLACK, D.M.

    1999-08-11

    This document presents the Project's position on compliance with the SNF Project NRC Equivalency Criteria--HNF-SD-SNF-DE-003, Spent Nuclear Fuel Project Path Forward Additional NRC Requirements. No non-compliances are shown The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion.

  6. Canister storage building compliance assessment DOE Order 6430.1A, General Design Criteria

    SciTech Connect (OSTI)

    BLACK, D.M.

    1999-08-12

    This document presents the Project's position on compliance with DOE Order 6430.1A ''General Design Criteria.'' No non-compliances are shown. The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion.

  7. Functional Design Criteria plutonium stabilization and handling (PUSH) project W-460

    SciTech Connect (OSTI)

    NELSON, D.W.

    1999-09-02

    This Functional Design Criteria (FDC) contains information to guide the design of the Stabilization and Packaging Equipment necessary to oxidize and package the remaining plutonium-bearing Special Nuclear Materials (SNM) currently in the Plutonium Finishing Plant (PFP) inventory. The FDC also guides the design of vault modifications to allow storage of 3013 packages of stabilized SNM for up to 50 years.

  8. Find Reports

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

    Reports Find Reports Most of the reports sources below are publicly accessible. Question? 667-5809 Email Unclassified Los Alamos Reports Library Catalog - Print and electronic (1943-present) Los Alamos Authors (LANL-only access) - LA-, LA-CP, and LA-UR reports (1973-present) Los Alamos Research Online - Find published versions of Los Alamos research (2006-present) Classified reports - contact the SI-RMS Technical Report Collection for an appointment: phone icon 5-4168 / email icon

  9. Site Specific Metal Criteria Developed Using Kentucky Division of Water Procedures

    SciTech Connect (OSTI)

    Kszos, L.A.; Phipps, T.L.

    1999-10-09

    Alternative limits for Cu, Ni, Pb, and Zn were developed for treated wastewater from four outfalls at a Gaseous Diffusion Plant. Guidance from the Kentucky Division of Water (KDOW) was used to (1) estimate the toxicity of the effluents using water fleas (Ceriodaphnia dubia) and fathead minnow (Pimephales promelas) larvae; (2) determine total recoverable and dissolved concentrations of Cu, Pb, Ni, and Zn ; (3) calculate ratios of dissolved metal (DM) to total recoverable metal (TRM); and (4) assess chemical characteristics of the effluents. Three effluent samples from each outfall were collected during each of six test periods; thus, a total of 18 samples from each outfall were evaluated for toxicity, DM and TRM. Subsamples were analyzed for alkalinity, hardness, pH, conductivity, and total suspended solids. Short-term (6 or 7 d), static renewal toxicity tests were conducted according to EPA methodology. Ceriodaphnia reproduction was reduced in one test of effluent from Outfall A , and effluent from Outfall B was acutely toxic to both test species during one test. However, the toxicity was not related to the metals present in the effluents. Of the 18 samples from each outfall, more than 65% of the metal concentrations were estimated quantities. With the exception of two total recoverable Cu values in Outfall C, all metal concentrations were below the permit limits and the federal water quality criteria. Ranges of TR for all outfalls were: Cd, ,0.1-0.4 {micro}g/L; Cr,1.07-3.93 {micro}g/L; Cu, 1.59-7.24 {micro}g/L; Pb, <0.1-3.20 {micro}g/L; Ni, 0.82-10.7 {micro}g/L, Zn, 4.75-67.3 {micro}g/L. DM:TRM ratios were developed for each outfall. The proportion of dissolved Cu in the effluents ranged from 67 to 82%; the proportion of dissolved Ni ranged from 84 to 91%; and the proportion of dissolved Zn ranged from 74 to 94%. The proportion of dissolved Pb in the effluents was considerably lower (37-51%). TRM and/or DM concentrations of Cu, Ni, Pb, or Zn differed significantly from outfall to outfall but the DM:TRM ratios for Cu, Ni, and Pb did not. Through the use of the KDOW method, the total recoverable metal measured in an effluent is adjusted by the proportion of dissolved metal present. The resulting alternative total recoverable metal concentration is reported in lieu of the measured total recoverable concentration for determining compliance with permit limits. For example, the monthly average permit limit for Pb in Outfall B (3 {micro}g/L) was exceeded at the Gaseous Diffusion Plant. Through the use of the KDOW method for calculating an alternative total recoverable metal concentration, 4.98 {micro}g Pb/L in Outfall B would be reported as 3.00 {micro}g/L, a difference of > 39%. Thus, the alternative, calculated total recoverable metal concentration provides the discharger with a ''cushion'' for meeting permit limits.

  10. Monthly Reports

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

    Environmental Management Monthly Reports - FY 2014 The Department of Energy Nevada Field Office Environmental Management Program creates monthly reports for the NSSAB. These...

  11. Monthly Reports

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

    Environmental Management Monthly Reports - FY 2015 The Department of Energy Nevada Field Office Environmental Management Program creates monthly reports for the NSSAB. These...

  12. Monthly Reports

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

    Environmental Management Monthly Reports - FY 2013 The Department of Energy Nevada Field Office Environmental Management Program creates monthly reports for the NSSAB. These...

  13. Monthly Reports

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

    Environmental Management Monthly Reports - FY 2012 The Department of Energy Nevada Field Office Environmental Management Program creates monthly reports for the NSSAB. These...

  14. Data Report

    Office of Legacy Management (LM)

    NDC 641 Results, Isotech Laboratories RESULTS REPORT RIN: 07081103 Site: Rulison Site Location: 35-12 Ticket Number: NDC 641 Report Date: 342008 Parameter Units Sample Date ID ...

  15. AUDIT REPORT

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

    General SUBJECT: INFORMATION: Audit Report: "Security Improvements at the Y-12 ... In June 2004, the Office of Inspector General's report on Management of the Department's ...

  16. Reporting Requirements

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

    Reporting Requirements Reporting Requirements Contacts Director Albert Migliori Deputy Franz Freibert 505 667-6879 Email Professional Staff Assistant Susan Ramsay 505 665 0858...

  17. DOE Publishes GATEWAY Report on Pedestrian Friendly Outdoor Lighting |

    Energy Savers [EERE]

    Department of Energy GATEWAY Report on Pedestrian Friendly Outdoor Lighting DOE Publishes GATEWAY Report on Pedestrian Friendly Outdoor Lighting January 9, 2014 - 12:00am Addthis The U.S. Department of Energy (DOE) has published a new GATEWAY report entitled Pedestrian Friendly Outdoor Lighting. Recognizing that pedestrian lighting has different criteria for success than street and area lighting, GATEWAY followed two pedestrian-scale lighting projects that required multiple mockups - one at

  18. DOE Publishes GATEWAY Report on Pedestrian Friendly Outdoor Lighting |

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

    Department of Energy GATEWAY Report on Pedestrian Friendly Outdoor Lighting DOE Publishes GATEWAY Report on Pedestrian Friendly Outdoor Lighting January 9, 2014 - 12:00am Addthis The U.S. Department of Energy (DOE) has published a new GATEWAY report entitled Pedestrian Friendly Outdoor Lighting. Recognizing that pedestrian lighting has different criteria for success than street and area lighting, GATEWAY followed two pedestrian-scale lighting projects that required multiple mockups - one at

  19. Financial News for Major Energy Companies

    Gasoline and Diesel Fuel Update (EIA)

    Second Quarter 2005 The "Financial News for Major Energy Companies" is issued quarterly to report recent trends in the financial performance of the major energy companies. These include the respondents to Form EIA-28 (Financial Reporting System (FRS)), with the exception of the FRS companies that do not issue quarterly earnings releases or fail to provide separate information for the company's U.S. operations. Twenty-five major energy companies reported overall net income (excluding

  20. Financial News for Major Energy Companies, Fourth Quarter 2005

    Gasoline and Diesel Fuel Update (EIA)

    Fourth Quarter 2005 Overview The "Financial News for Major Energy Companies" is issued quarterly to report recent trends in the financial performance of the major energy companies. These include the respondents to Form EIA-28 (Financial Reporting System (FRS)), with the exception of the FRS companies that do not issue quarterly earnings releases or fail to provide separate information for the company's U.S. operations. Twenty-one major energy companies 1 reported overall net income

  1. Financial News for Major Energy Companies, October - December 2004

    Gasoline and Diesel Fuel Update (EIA)

    The "Financial News for Major Energy Companies" is issued quarterly to report recent trends in the financial performance of the major energy companies. These include the respondents to Form EIA-28 (Financial Reporting System (FRS)), with the exception of the FRS companies that do not issue quarterly earnings releases or fail to provide separate information for the company's U.S. operations. Twenty-three major energy companies reported overall net income (excluding unusual items) of

  2. Development of design criteria for a high pressure vessel construction code

    SciTech Connect (OSTI)

    Mraz, G.J.

    1987-05-01

    Out of concern for public safety, most legal jurisdictions now require unfired pressure vessel construction to comply with the ASME Boiler and Pressure Vessel Code. Because the present two divisions of Section VIII of that Code are not well suited for high pressure design, a new division is needed. The currently anticipated main design criteria of the proposed division are full plastic flow or full overstrain pressure, stress intensity in the bore, fatigue, and fracture mechanics. The rules are expected to allow better utilization of high strength steels already included in the present Section VIII. At the same time materials of even higher strength are introduced. The benefits of compressive prestress are recognized. Construction methods allowing it's achievement, such as autofrettage, shrink fitting and wire winding are included. Reasons for selection of the criteria are given.

  3. SEA effectiveness criteria-equally valid in all countries? The case of Italy

    SciTech Connect (OSTI)

    Fischer, Thomas B. . E-mail: fischer@liverpool.ac.uk; Gazzola, Paola

    2006-05-15

    Recent years have seen the introduction of various sets of strategic environmental assessment (SEA) effectiveness criteria in the professional international literature. Content analysis of key international SEA publications suggest that these have been developed based on the experiences of a selected number of countries only, and to date, the question whether they are fully valid in all systems and countries world-wide has not been addressed sufficiently, yet. In this context, the paper discusses the validity of effectiveness criteria for Italy, a country from which authors have only contributed to a very limited extent to the international SEA literature. It is concluded that, particularly in the light of experiences with a 'flexible', but ineffective EIA system, in Italy SEA needs to be applied in a systematic and rigorous manner, aided by strong enforcement mechanisms.

  4. Basic criteria for formation of growth twins in high stacking fault energy metals

    SciTech Connect (OSTI)

    Yu, K. Y.; Zhang, X.; Department of Mechanical Engineering, Texas A and M University, College Station, Texas 77843 ; Bufford, D.; Chen, Y.; Liu, Y.; Wang, H.; Department of Electrical and Computer Engineering, Texas A and M University, College Station, Texas 77843

    2013-10-28

    Nanotwinned metals received significant interest lately as twin boundaries may enable simultaneous enhancement of strength, ductility, thermal stability, and radiation tolerance. However, nanotwins have been the privilege of metals with low-to-intermediate stacking fault energy (SFE). Recent scattered studies show that nanotwins could be introduced into high SFE metals, such as Al. In this paper, we examine several sputter-deposited, (111) textured Ag/Al, Cu/Ni, and Cu/Fe multilayers, wherein growth twins were observed in Al, Ni, and face-centered cubic (fcc) Fe. The comparisons lead to two important design criteria that dictate the introduction of growth twins in high SFE metals. The validity of these criteria was then examined in Ag/Ni multilayers. Furthermore, another twin formation mechanism in high SFE metals was discovered in Ag/Ni system.

  5. Criteria for the selection of corrosion inhibitors for Arctic and subsea high velocity flowlines

    SciTech Connect (OSTI)

    Dougherty, J.A.; Ahn, Y.S.

    1999-11-01

    Qualifying corrosion inhibitors for use in high velocity multiphase flowlines in arctic or subsea environments is discussed. The tests include high velocity flow loop corrosion tests, pumpability through 0.125 (0.318 cm) inch capillary at low temperatures, compatibility with Nylon 11, emulsion tendency testing, and partitioning characteristics. Laboratory and field data show the importance for using the above criteria for inhibitor selection.

  6. Development of biological criteria for the design of advanced hydropower turbines

    SciTech Connect (OSTI)

    ?ada, Glenn F.; Coutant, Charles C.; Whitney, Richard R.

    1997-03-01

    A review of the literature related to turbine-passage injury mechanisms suggests the following biological criteria should be considered in the design of new turbines: (1) pressure; (2) cavitation; (3) shear and turbulence; and (4) mechanical injury. Based on the studys review of fish behavior in relation to hydropower facilities, it provides a number of recommendations to guide both turbine design and additional research.

  7. Application of Negligible Creep Criteria to Candidate Materials for HTGR Pressure Vessels

    SciTech Connect (OSTI)

    Jetter, Robert I; Sham, Sam; Swindeman, Robert W

    2011-01-01

    Two of the proposed High Temperature Gas Reactors (HTGRs) under consideration for a demonstration plant have the design object of avoiding creep effects in the reactor pressure vessel (RPV) during normal operation. This work addresses the criteria for negligible creep in Subsection NH, Division 1 of the ASME B&PV (Boiler and Pressure Vessel) Code, Section III, other international design codes and some currently suggested criteria modifications and their impact on permissible operating temperatures for various reactor pressure vessel materials. The goal of negligible creep could have different interpretations depending upon what failure modes are considered and associated criteria for avoiding the effects of creep. It is shown that for the materials of this study, consideration of localized damage due to cycling of peak stresses results in a lower temperature for negligible creep than consideration of the temperature at which the allowable stress is governed by creep properties. In assessing the effect of localized cyclic stresses it is also shown that consideration of cyclic softening is an important effect that results in a higher estimated temperature for the onset of significant creep effects than would be the case if the material were cyclically hardening. There are other considerations for the selection of vessel material besides avoiding creep effects. Of interest for this review are (1) the material s allowable stress level and impact on wall thickness (the goal being to minimize required wall thickness) and (2) ASME Code approval (inclusion as a permitted material in the relevant Section and Subsection of interest) to expedite regulatory review and approval. The application of negligible creep criteria to two of the candidate materials, SA533 and Mod 9Cr-1Mo (also referred to as Grade 91), and to a potential alternate, normalized and tempered 2 Cr-1Mo, is illustrated and the relative advantages and disadvantages of the materials are discussed.

  8. Protective Action Criteria (PAC) with AEGLs, ERPGs, & TEELs: Rev. 29 for Chemicals of Concern- May 2016

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Temporary Emergency Exposure Limit (TEEL) data set has a new name; it is now called the Protective Action Criteria (PAC) dataset. While the PAC dataset continues to present the latest TEEL values (as developed by Doug Craig and his SCAPA team), the intent of the new name is to emphasize that the data set also includes available Acute Exposure Guideline Level (AEGL) and Emergency Response Planning Guideline (ERPG) values.

  9. DOE Standard Fire Protection Design Criteria DOE-STD-1006-97

    Energy Savers [EERE]

    6-97 March 1997 DOE STANDARD FIRE PROTECTION DESIGN CRITERIA U.S. Department of Energy AREA GDRQ Washington, D.C. 20585 DISTRIBUTION STATEMENT. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to the Department of Energy (DOE), DOE contractors and the public from the DOE Office of Worker Health and Safety, Bellemead Building, 19901 Germantown Road, Germantown, MD 20874-1290; (301) 903-4794. TABLE OF

  10. Protective Action Criteria (PAC) with AEGLs, ERPGs, & TEELs: Rev. 27 for Chemicals of Concern- March 2012

    Broader source: Energy.gov [DOE]

    The Temporary Emergency Exposure Limit (TEEL) data set has a new name; it is now called the Protective Action Criteria (PAC) dataset. While the PAC dataset continues to present the latest TEEL values (as developed by Doug Craig and his SCAPA team), the intent of the new name is to emphasize that the data set also includes available Acute Exposure Guideline Level (AEGL) and Emergency Response Planning Guideline (ERPG) values.

  11. Constraining the mSUGRA parameter space through entropy and abundance criteria

    SciTech Connect (OSTI)

    Cabral-Rosetti, Luis G.; Mondragon, Myriam; Nunez, Dario; Sussman, Roberto A.; Zavala, Jesus; Nellen, Lukas

    2007-06-19

    We explore the use of two criteria to constrain the allowed parameter space in mSUGRA models; both criteria are based in the calculation of the present density of neutralinos {chi}0 as Dark Matter in the Universe. The first one is the usual ''abundance'' criterion that requieres that present neutralino relic density complies with 0.0945 < {omega}CDMh2 < 0.1287, which are the 2{sigma} bounds according to WMAP. To calculate the relic density we use the public numerical code micrOMEGAS. The second criterion is the original idea presented in [3] that basically applies the microcanonical definition of entropy to a weakly interacting and self-gravitating gas, and then evaluate the change in entropy per particle of this gas between the freeze-out era and present day virialized structures. An 'entropy consistency' criterion emerges by comparing theoretical and empirical estimates of this entropy. One of the objetives of the work is to analyze the joint application of both criteria, already done in [3], to see if their results, using approximations for the calculations of the relic density, agree with the results coming from the exact numerical results of micrOMEGAS. The main objetive of the work is to use this method to constrain the parameter space in mSUGRA models that are inputs for the calculations of micrOMEGAS, and thus to get some bounds on the predictions for the SUSY spectra.

  12. Criteria for design of the Yucca Mountain structures, systems and components for fault displacement

    SciTech Connect (OSTI)

    Stepp, C.; Hossain, Q.; Nesbit, S.; Hardy, M.

    1995-12-31

    The DOE intends to design the Yucca Mountain high-level waste facility structures, systems and components (SSCs) for fault displacements to provide reasonable assurance that they will meet the preclosure safety performance objectives established by 10 CFR Part 60. To the extent achievable, fault displacement design of the facility will follow guidance provided in the NRC Staff Technical Position. Fault avoidance will be the primary design criterion, especially for spatially compact or clustered SSCs. When fault avoidance is not reasonably achievable, expected to be the case for most spatially extended SSCs, engineering design procedures and criteria or repair and rehabilitation actions, depending on the SSC`s importance to safety, are provided. SSCs that have radiological safety importance will be designed for fault displacements that correspond to the hazard exceedance frequency equal to their established seismic safety performance goals. Fault displacement loads are generally localized and may cause local inelastic response of SSCs. For this reason, the DOE intends to use strain-based design acceptance criteria similar to the strain-based criteria used to design nuclear plant SSCs for impact and impulsive loads.

  13. Development and implementation of seismic design and evaluation criteria for NIF

    SciTech Connect (OSTI)

    Sommer, S.C.; MacCalden, P.B.

    1998-03-17

    The National Ignition Facility (NIF) is being built at the Lawrence Livermore National Laboratory (LLNL) as an international research center for inertial confinement fusion (ICF). This paper will provide an overview of NIF, review NIF seismic criteria, and briefly discuss seismic analyses of NIF optical support structures that have been performed by LLNL and the Ralph M. Parsons Company, the Architect and Engineer (A&E) for NIF. The NIF seismic design and evaluation criteria is based on provisions in DOE Standard 1020 (DOE-STD-1020), the Uniform Building Code (UBC), and the LLNL Mechanical Engineering Design Safety Standards (MEDSS). Different levels of seismic requirements apply to NIF structures, systems, and components (SSCs) based on their function. The highest level of requirements are defined for optical support structures and SSCs which could influence the performance of optical support structures, while the minimum level of requirements are Performance Category 2 (PC2) requirements in DOE-STD-1020. To demonstrate that the NIF seismic criteria is satisfied, structural analyses have been performed by LLNL and Parsons to evaluate the responses of optical support structures and other SSCs to seismic-induced forces.

  14. Operational-Condition-Independent Criteria Dedicated to Monitoring Wind Turbine Generators: Preprint

    SciTech Connect (OSTI)

    Yang, W.; Sheng, S.; Court, R.

    2012-08-01

    To date the existing wind turbine condition monitoring technologies and commercially available systems have not been fully accepted for improving wind turbine availability and reducing their operation and maintenance costs. One of the main reasons is that wind turbines are subject to constantly varying loads and operate at variable rotational speeds. As a consequence, the influences of turbine faults and the effects of varying load and speed are coupled together in wind turbine condition monitoring signals. So, there is an urgent need to either introduce some operational condition de-coupling procedures into the current wind turbine condition monitoring techniques or develop a new operational condition independent wind turbine condition monitoring technique to maintain high turbine availability and achieve the expected economic benefits from wind. The purpose of this paper is to develop such a technique. In the paper, three operational condition independent criteria are developed dedicated for monitoring the operation and health condition of wind turbine generators. All proposed criteria have been tested through both simulated and practical experiments. The experiments have shown that these criteria provide a solution for detecting both mechanical and electrical faults occurring in wind turbine generators.

  15. The criteria of fracture in the case of the leak of pressure vessels

    SciTech Connect (OSTI)

    Habil; Ziliukas, A.

    1997-04-01

    In order to forecast the break of the high pressure vessels and the network of pipes in a nuclear reactor, according to the concept of leak before break of pressure vessels, it is necessary to analyze the conditions of project, production, and mounting quality as well as of exploitation. It is also necessary to evaluate the process of break by the help of the fracture criteria. In the Ignalina Nuclear Power Plant of, in Lithuania, the most important objects of investigation are: the highest pressure pipes, made of Japanese steel 19MN5 and having an anticorrosive austenitic: coal inside, the pipes of distribution, which arc made of 08X1810T steel. The steel of the network of pipes has a quality of plasticity: therefore the only criteria of fragile is impossible to apply to. The process of break would be best described by the universal criteria of elastic - plastic fracture. For this purpose the author offers the criterion of the double parameter.

  16. Development of criteria used to establish a background environmental monitoring station

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

    Fritz, Brad G.; Barnett, J. Matthew; Snyder, Sandra F.; Bisping, Lynn E.; Rishel, Jeremy P.

    2015-03-02

    It is generally considered necessary to measure concentrations of contaminants-of-concern at a background location when conducting atmospheric environmental surveillance. This is because it is recognized that measurements of background concentrations can enhance interpretation of environmental monitoring data. Despite the recognized need for background measurements, there is little published guidance available that describes how to identify an appropriate atmospheric background monitoring location. This paper develops generic criteria that can guide the decision making process for identifying suitable locations for background atmospheric monitoring station. Detailed methods for evaluating some of these criteria are also provided and a case study for establishment ofmore » an atmospheric background surveillance station as part of an environmental surveillance program is described. While the case study focuses on monitoring for radionuclides, the approach is equally valid for any airborne constituent being monitored. The case study shows that implementation of the developed criteria can result in a good, defensible choice for a background atmospheric monitoring location.« less

  17. Impact of Environmental Compliance Costs on U.S. Refining Profitability

    Reports and Publications (EIA)

    1997-01-01

    Assesses the effects of pollution abatement requirements on the financial performance of U.S. petroleum refining and marketing operations. The analysis draws heavily on financial and operating data from the Energy Information Administration's Financial Reporting System (FRS).

  18. UMTRA project list of reportable occurrences

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    This UMTRA Project List of Reportable occurrences is provided to facilitate efficient categorization of reportable occurrences. These guidelines have been established in compliance with DOE minimum reporting requirements under DOE Order 5000.3B. Occurrences are arranged into nine groups relating to US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project operations for active sites. These nine groupings are provided for reference to determined whether an occurrence meets reporting requirement criteria in accordance with the minimum reporting requirements. Event groups and significance categories that cannot or will not occur, and that do not apply to UMTRA Project operations, are omitted. Occurrence categorization shall be as follows: Group 1. Facility Condition; Group 2. Environmental; Group 3. Personnel Safety; Group 4. Personnel Radiation Protection; Group 5. Safeguards and Security; Group 6. Transportation; Group 7. Value Basis Reporting; Group 8. Facility Status; and Group 9. Cross-Category Items.

  19. Regulatory Safety Issues in the Structural Design Criteria of ASME Section III Subsection NH and for Very High Temperatures for VHTR & GEN IV

    SciTech Connect (OSTI)

    William J. O’Donnell; Donald S. Griffin

    2007-05-07

    The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA); and to identify the material models, design criteria, and analysis methods that need to be added to the ASME Code to cover the unresolved safety issues. Subsection NH was originally developed to provide structural design criteria and limits for elevated-temperature design of Liquid Metal Fast Breeder Reactor (LMFBR) systems and some gas-cooled systems. The U.S. Nuclear Regulatory Commission (NRC) and its Advisory Committee for Reactor Safeguards (ACRS) reviewed the design limits and procedures in the process of reviewing the Clinch River Breeder Reactor (CRBR) for a construction permit in the late 1970s and early 1980s, and identified issues that needed resolution. In the years since then, the NRC and various contractors have evaluated the applicability of the ASME Code and Code Cases to high-temperature reactor designs such as the VHTGRs, and identified issues that need to be resolved to provide a regulatory basis for licensing. This Report describes: (1) NRC and ACRS safety concerns raised during the licensing process of CRBR , (2) how some of these issues are addressed by the current Subsection NH of the ASME Code; and (3) the material models, design criteria, and analysis methods that need to be added to the ASME Code and Code Cases to cover unresolved regulatory issues for very high temperature service.

  20. Criteria for initiation of delamination in quasi-static punch-shear tests of a carbon-fiber composite material.

    SciTech Connect (OSTI)

    Chin, Eric Brian; English, Shawn Allen; Briggs, Timothy

    2015-09-01

    V arious phenomenological delamination initiation criteria are analyzed in quasi - static punch - shear tests conducted on six different geometries. These six geometries are modeled and analyzed using elastic, large - deformation finite element analysis. Analysis output is post - processed to assess different delamination initiation criteria, and their applicability to each of the geometries. These criteria are compared to test results to assess whether or not they are appropriate based on what occurred in testing. Further, examinations of CT scans and ultrasonic images o f test specimens are conducted in the appendix to determine the sequence of failure in each test geometry.

  1. Costs and benefits of industrial reporting and voluntary targets for energy efficiency. A report to the Congress of the United States. Volume II: Appendices

    SciTech Connect (OSTI)

    Not Available

    1994-02-01

    This part sets forth the regulations for the Industrial Energy conservation Program established under Part E of Title III of the Act. It includes criteria and procedures for the identification of reporting corporations, reporting requirements, criteria and procedures for exemption from filing reports directly with DOE, voluntary industrial energy efficiency improvement targets and voluntary recovered materials utilization targets. The purpose of the program is to promote increased energy conservation by American industry and, as it relates to the use of recovered materials, to conserve valuable energy and scarce natural resources.

  2. Monthly Performance Report

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

    ... In addition, finalizing end user criteria took ... (-0.9M): Upgrade Waste Sampling and ... and schedule confidence to determine management reserve at the project level. ...

  3. Occurrence Reporting Causal Analysis

    Office of Environmental Management (EM)

    ... A5B1C03, Checklist LTA ... of management processes in ... low level radioactive waste containers that met appropriate waste acceptance criteria and Department ...

  4. Monthly Performance Report

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

    ... All boxes of Office of Civilian Radioactive Waste ... In addition, finalizing end user criteria took ... and schedule confidence to determine management reserve at the project level. ...

  5. EM-20 ISD Report

    Office of Environmental Management (EM)

    ... HWMA Hazardous Waste Management Act ICDF Idaho CERCLA ... Flammability Limit LLW low level waste LOFT Loss-of-Fluid Test ... and acceptance criteria afforded by ISD ...

  6. SANDIA REPORT

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

    SANDIA REPORT SAND2014-4753 Unlimited Release Printed December 2014 Analysis of 100 SGIP ... NOTICE: This report was prepared as an account of work sponsored by an agency of the ...

  7. Data Report

    Office of Legacy Management (LM)

    NDC 644 Results, Paragon Analytics RESULTS REPORT RIN: 07081112 Site: Rulison Site Location: 35-32A Ticket Number: NDC 644 Report Date: 342008 Parameter Units Sample Date ID ...

  8. Annual Report

    Energy Savers [EERE]

    Information Act report covers the Period 10012009, through 09302010, as required by 5 U.S.C. 552. I. BASIC INFORMATION REGARDING REPORT 1. Kevin T. Hagerty, Director Office...

  9. Agent review phase one report.

    SciTech Connect (OSTI)

    Zubelewicz, Alex Tadeusz; Davis, Christopher Edward; Bauer, Travis LaDell

    2009-12-01

    This report summarizes the findings for phase one of the agent review and discusses the review methods and results. The phase one review identified a short list of agent systems that would prove most useful in the service architecture of an information management, analysis, and retrieval system. Reviewers evaluated open-source and commercial multi-agent systems and scored them based upon viability, uniqueness, ease of development, ease of deployment, and ease of integration with other products. Based on these criteria, reviewers identified the ten most appropriate systems. The report also mentions several systems that reviewers deemed noteworthy for the ideas they implement, even if those systems are not the best choices for information management purposes.

  10. Development of site-specific soil cleanup criteria: New Brunswick Laboratory, New Jersey site

    SciTech Connect (OSTI)

    Veluri, V.R.; Moe, H.J.; Robinet, M.J.; Wynveen, R.A.

    1983-03-01

    The potential human exposure which results from the residual soil radioactivity at a decommissioned site is a prime concern during D and D projects. To estimate this exposure, a pathway analysis approach is often used to arrive at the residual soil radioactivity criteria. The development of such a criteria for the decommissioning of the New Brunswick Laboratory, New Jersey site is discussed. Contamination on this site was spotty and located in small soil pockets spread throughout the site area. Less than 1% of the relevant site area was contaminated. The major contaminants encountered at the site were /sup 239/Pu, /sup 241/Am, normal and natural uranium, and natural thorium. During the development of the pathway analysis to determine the site cleanup criteria, corrections for the inhomogeneity of the contamination were made. These correction factors and their effect upon the relevant pathway parameters are presented. Major pathways by which radioactive material may reach an individual are identified and patterns of use are specified (scenario). Each pathway is modeled to estimate the transfer parameters along the given pathway, such as soil to air to man, etc. The transfer parameters are then combined with dose rate conversion factors (ICRP 30 methodology) to obtain soil concentration to dose rate conversion factors (pCi/g/mrem/yr). For an appropriate choice of annual dose equivalent rate, one can then arrive at a value for the residual soil concentration. Pathway modeling, transfer parameters, and dose rate factors for the three major pathways; inhalation, ingestion and external exposure, which are important for the NBL site, are discussed.

  11. RFP Section L Technical Proposal Preparation Instruction and Section M Evaluation Criteria Templates

    Broader source: Energy.gov [DOE]

    On March 29, 2010, and April 1, 2010, fourteen draft RFP Section L Technical Proposal Preparation Instruction and Section M Evaluation Criteria templates (Past Performance, Transition, Organization Structure and Approach, Key Personnel (written proposal and oral presentation), Key Personnel (written proposal), Relevant Experience, and Environment Safety and Health) were distributed for Procurement Director (PD) and Head of Contracting Activity (HCA) review and comment. All comments received were considered and changes were made as appropriate. The final version of the fourteen aforementioned RFP Section L and M templates are available in STRIPES as part of the series of DOE-L-1024 or DOE-M-1005 clauses.

  12. Similarity criteria in calculations of the energy characteristics of a cw oxygen - iodine laser

    SciTech Connect (OSTI)

    Mezhenin, A V; Azyazov, V N

    2012-12-31

    The calculated and experimental data on the energy efficiency of a cw oxygen - iodine laser (OIL) are analysed based on two similarity criteria, namely, on the ratio of the residence time of the gas mixture in the resonator to the characteristic time of extraction of the energy stored in singlet oxygen td and on the gain-to-loss ratio {Pi}. It is shown that the simplified two-level laser model satisfactorily predicts the output characteristics of OILs with a stable resonator at {tau}{sub d} {<=} 7. Efficient energy extraction from the OIL active medium is achieved in the case of {tau}{sub d} = 5 - 7, {Pi} = 4 - 8. (lasers)

  13. Natural Phenomena Hazards Design and Evaluation Criteria for Department of Energy Facilities

    Energy Savers [EERE]

    0-2002 January 2002 Superseding DOE-STD-1020-94 April 1994 DOE STANDARD NATURAL PHENOMENA HAZARDS DESIGN AND EVALUATION CRITERIA FOR DEPARTMENT OF ENERGY FACILITIES U.S. Department of Energy AREA NPHZ Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375,

  14. DECONTAMINATION CRITERIA FOR THE FORMER KELLEX SITE (PIERPONT PROPERTY) REMEDIAL ACTION,

    Office of Legacy Management (LM)

    DECONTAMINATION CRITERIA FOR THE FORMER KELLEX SITE (PIERPONT PROPERTY) REMEDIAL ACTION, JERSEY CITY, NEW JERSEY U.S. DEPARTMENT OF ENERGY WASHINGTON, D.C. 2U545 JUNE 196B Current Federal Policy and Guidance The current guidance for Federal decisions affecting the exposure of members of the public in the U.S. remains that recommended by the Federal Radiation'Council (FRC) and issued by the President in 196U. This guidance defines the Radiation Protection Guide as "the radiation dose which

  15. U.S. Department of Energy Implements More Stringent Criteria for ENERGY STAR® Clothes Washers, Expands CFL Program

    Broader source: Energy.gov [DOE]

    WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced more stringent criteria for clothes washers and expanded the categories of compact fluorescent lightbulbs (CFL) under the ENERGY...

  16. IMPLEMENTATION OF THE SEISMIC DESIGN CRITERIA OF DOE-STD-1189-2008 APPENDIX A [FULL PAPER

    SciTech Connect (OSTI)

    OMBERG SK

    2008-05-14

    This paper describes the approach taken by two Fluor Hanford projects for implementing of the seismic design criteria from DOE-STD-1189-2008, Appendix A. The existing seismic design criteria and the new seismic design criteria is described, and an assessment of the primary differences provided. The gaps within the new system of seismic design criteria, which necessitate conduct of portions of work to the existing technical standards pending availability of applicable industry standards, is discussed. Two Hanford Site projects currently in the Control Decision (CD)-1 phase of design have developed an approach to implementation of the new criteria. Calculations have been performed to determine the seismic design category for one project, based on information available in early CD-1. The potential effects of DOE-STD-1189-2008, Appendix A seismic design criteria on the process of project alternatives analysis is discussed. Present of this work is expected to benefit others in the DOE Complex that may be implementing DOE-STD-1189-2008.

  17. Integrating multi-criteria decision analysis for a GIS-based hazardous waste landfill sitting in Kurdistan Province, western Iran

    SciTech Connect (OSTI)

    Sharifi, Mozafar Hadidi, Mosslem Vessali, Elahe Mosstafakhani, Parasto Taheri, Kamal Shahoie, Saber Khodamoradpour, Mehran

    2009-10-15

    The evaluation of a hazardous waste disposal site is a complicated process because it requires data from diverse social and environmental fields. These data often involve processing of a significant amount of spatial information which can be used by GIS as an important tool for land use suitability analysis. This paper presents a multi-criteria decision analysis alongside with a geospatial analysis for the selection of hazardous waste landfill sites in Kurdistan Province, western Iran. The study employs a two-stage analysis to provide a spatial decision support system for hazardous waste management in a typically under developed region. The purpose of GIS was to perform an initial screening process to eliminate unsuitable land followed by utilization of a multi-criteria decision analysis (MCDA) to identify the most suitable sites using the information provided by the regional experts with reference to new chosen criteria. Using 21 exclusionary criteria, as input layers, masked maps were prepared. Creating various intermediate or analysis map layers a final overlay map was obtained representing areas for hazardous waste landfill sites. In order to evaluate different landfill sites produced by the overlaying a landfill suitability index system was developed representing cumulative effects of relative importance (weights) and suitability values of 14 non-exclusionary criteria including several criteria resulting from field observation. Using this suitability index 15 different sites were visited and based on the numerical evaluation provided by MCDA most suitable sites were determined.

  18. U.S. NRC CONFIRMATORY LEVEL 1 PRA SUCCESS CRITERIA ACTIVITIES

    SciTech Connect (OSTI)

    Donald Helton; Hossein Esmaili; Robert Buell

    2011-03-01

    The U.S. Nuclear Regulatory Commission’s standardized plant analysis risk (SPAR) models are used to support a number of risk-informed initiatives. The fidelity and realism of these models are ensured through a number of processes including cross-comparison with industry models, review and use by a wide range of technical experts, and confirmatory analysis. This paper will describe a key activity in the latter arena. Specifically, this paper will describe MELCOR analyses performed to augment the technical basis for confirming or modifying specific success criteria of interest. The analyses that will be summarized provide the basis for confirming or changing success criteria in a specific 3-loop pressurized-water reactor and a Mark-I boiling-water reactor. Initiators that have been analyzed include loss-of-coolant accidents, loss of main feedwater, spontaneous steam generator tube rupture, inadvertent opening of a relief valve at power, and station blackout. For each initiator, specific aspects of the accident evolution are investigated via a targeted set of calculations (3 to 22 distinct accident analyses per initiator). Further evaluation is ongoing to extend the analyses’ conclusions to similar plants (where appropriate), with consideration of design and modeling differences on a scenario-by-scenario basis. This paper will also describe future plans.

  19. Multi-criteria assessment of socio-environmental aspects in shrinking cities. Experiences from eastern Germany

    SciTech Connect (OSTI)

    Schetke, Sophie Haase, Dagmar

    2008-10-15

    Demographic change and economic decline produce modified urban land use pattern and densities. Compared to the beginning of the 90s after the German reunification, nowadays massive housing and commercial vacancies followed by demolition and perforation come to pass in many cities of the former GDR. In consequence, a considerable surplus of urban brownfields has been created. Furthermore, the decline in the urban fabric affects social infrastructure and urban greenery of local neighbourhoods. Here, urban planning enters into 'uncharted territory' since it needs to assess the socio-environmental impact of shrinkage. In order to carry out such an evaluation quantitatively, a multi-criteria assessment scheme (MCA) was developed and applied. Firstly, we identified infrastructure and land use changes related to vacancy and demolition. Secondly, demolition scenarios for the coming 20 years were applied in order to give an idea for a long-term monitoring approach at the local district level. A multi-criteria indicator matrix quantifies the socio-environmental impact on both urban greenery and residents. Using it, we set demolition scenarios against urban 'quality of life' targets. Empirical evidence comes from Leipzig, in eastern Germany, a representative case study for urban shrinkage processes. The results show that shrinkage implies socio-environmental changes of residential livelihoods, however, does not simply increase or decrease the overall urban quality of life. The integrated assessment of all indicators identifies environmental and social opportunities, as well as the challenges a shrinking city is faced with.

  20. Spirometry variability criteria--association with respiratory morbidity and mortality in a cohort of coal miners

    SciTech Connect (OSTI)

    Kellie, S.E.; Attfield, M.D.; Hankinson, J.L.; Castellan, R.M.

    1987-03-01

    To clarify the association between spirometry variability and respiratory morbidity and mortality, the authors analyzed data for miners examined in the first round of the National Coal Study, 1969-1971, and they compared groups of miners who failed with those who met each of two spirometry variability criteria: a 5% criterion recommended by the American Thoracic Society, and a 200 ml criterion used in prior research studies. Compared with miners who met the 5% criterion (the best two forced vital capacities must be within 5% or 100 ml of one another), the group that failed had a lower mean for forced expiratory volume in one second (FEV1), and odds ratios for cough, phlegm, wheeze, shortness of breath, and death of 1.75, 1.67, 1.76, 2.71, and 1.30, respectively. The findings for the 200 ml criterion (the best two FEV1s must be within 200 ml of one another) were somewhat different. The group that failed versus the group that met this criterion had a higher mean for FEV1, and odds ratios for cough, phlegm, wheeze, shortness of breath, and death of 1.13, 1.07, 1.15, 1.43, and 0.94, respectively. Although the findings differ for the two criteria, the findings demonstrate that increased spirometry variability is associated with poorer health.

  1. An analysis of the qualification criteria for small radioactive material shipping packages

    SciTech Connect (OSTI)

    McClure, J.D.

    1983-05-01

    The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described.

  2. Technical criteria for an Area-Of-Review variance methodology. Appendix B

    SciTech Connect (OSTI)

    1994-01-01

    This guidance was developed by the Underground Injection Practices Research Foundation to assist Underground Injection Control Directors in implementing proposed changes to EPA`s Class 2 Injection Well Regulations that will apply the Area-Of-Review (AOR) requirement to previously exempt wells. EPA plans to propose amendments this year consistent with the recommendations in the March 23, 1992, Final Document developed by the Class 2 Injection Well Advisory Committee, that will require AORs to be performed on all Class 2 injection wells except those covered by previously conducted AORs and those located in areas that have been granted a variance. Variances may be granted if the Director determines that there is a sufficiently low risk of upward fluid movement from the injection zone that could endanger underground sources of drinking water. This guidance contains suggested technical criteria for identifying areas eligible for an AOR variance. The suggested criteria were developed in consultation with interested States and representatives from EPA, industry and the academic community. Directors will have six months from the promulgation of the new regulations to provide EPA with either a schedule for performing AOR`s within five years on all wells not covered by previously conducted AORs, or notice of their intent to establish a variance program. It is believed this document will provide valuable assistance to Directors who are considering whether to establish a variance program or have begun early preparations to develop such a program.

  3. Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-12-29

    The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source documents from the U.S. Nuclear RegulatoryCommission (NRC) and the New Mexico Environment Department (NMED) for acomprehensive and detailed listing of the requirements.This CH-WAC does not address the subject of waste characterization relating to adetermination of whether the waste is hazardous; rather, the sites are referred to theWaste Analysis Plan (WAP) contained in the WIPP Hazardous Waste Facility Permit fordetails of the sampling and analysis protocols to be used in determining compliance withthe required physical and chemical properties of the waste. Requirements andassociated criteria pertaining to a determination of the radiological properties of thewaste, however, are addressed in appendix A of this document. The collectiveinformation obtained from waste characterization records and acceptable knowledge(AK) serves as the basis for sites to certify that their CH-TRU waste satisfies the WIPPwaste acceptance criteria listed herein.

  4. Sanitary landfill groundwater monitoring report. First Quarter 1995

    SciTech Connect (OSTI)

    1995-06-01

    This report contains analytical data for samples taken during first quarter 1994 from wells of the LFW series located at the Sanitary Landfill Operating permit (DWP-0874A). The report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final Primary Drinking Water Standards (PDWS) or screening levels, established by the US Environmental Protection Agency, the South Carolina final Primary Drinking Water Standard for lead, or the SRS flagging criteria.

  5. SANDIA REPORT

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

    ... and Computer Engineering Georgia Institute of Technology 777 Atlantic Drive NW Atlanta, GA 30332-0250 Abstract The research presented in this report compares several real-time ...

  6. Special Report

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

    of any of the information or data contained in this Report. ... 2 1 - Introduction ...for the domestic uranium mining, conversion, and ...

  7. SPECIAL REPORT

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

    Washington, DC 20585 September 3, 2015 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Special Report: "The Department of Energy's...

  8. Financial News for Major Energy Producers, Third Quarter 2010

    Gasoline and Diesel Fuel Update (EIA)

    Forecasts and Analysis > Energy Finance > Financial News for Major Energy Producers > Company List Financial News for Major Energy Producers, Third Quarter 2010 What is FRS? | Contacts | FRS Home Corporate and Petroleum Net Income Worldwide Oil and Gas Production Operations Worldwide Refining/Marketing Operations Worldwide Petroleum Capital Expenditures Worldwide Downstream Natural Gas and Power Operations, Supplemental Figures Supplemental Tables Download this Report: pdf icon Full

  9. Compressed air energy storage technology program. Annual report for 1980

    SciTech Connect (OSTI)

    Kannberg, L.D.

    1981-06-01

    All of the major research funded under the Compressed Air Energy Storage Technology Program during the period March 1980 to March 1981 is described. This annual report is divided into two segments: Reservoir Stability Studies and Second-Generation Concepts Studies. The first represents research performed to establish stability criteria for CAES reservoirs while the second reports progress on research performed on second-generation CAES concepts. The report consists of project reports authored by research engineers and scientists from PNL and numerous subcontractors including universities, architect-engineering, and other private firms.

  10. Proposed GTA welding specification and acceptance criteria for the MC4163

    SciTech Connect (OSTI)

    Kwiatkowski, J.J.

    1991-04-12

    This specification documents the gas tungsten arc (GTA) welding process and production weld acceptance criteria requirements for the MC4163. This document is written specifically to apply to the welds on the MC4163 and is not to be used as a general gas tungsten arc welding specification. All sections of this specification must be complied with unless specifically exempted in writing. There are a total of five welds with three different joint designs required to fabricate the MC4163. In the order of fabrication they are (1) initiator closure disc, (2) nozzle to case girth welds, two and, (3) nozzle closure disc welds, two. This specification will only address the nozzle to case girth welds and the nozzle closure disc welds.

  11. DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

    SciTech Connect (OSTI)

    William E. Kastenberg; Edward Blandford; Lance Kim

    2009-03-31

    This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public.

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

    SciTech Connect (OSTI)

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

    1994-12-01

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

  13. Functional design criteria for Project W-252, Phase II Liquid Effluent Treatment and Disposal: Revision 1

    SciTech Connect (OSTI)

    Hatch, C.E.

    1994-11-10

    This document provides the functional design criteria required for the Phase 2 Liquid Effluent Treatment and Disposal Project, Project W-252. Project W-252 shall provide new facilities and existing facility modifications required to implement Best Available Technology/All Known, Available, and Reasonable Methods of Prevention, Control, and Treatment (BAT/AKART) for the 200 East Phase II Liquid Effluent Streams. The project will also provide a 200 East Area Phase II Effluent Collection System (PTECS) for connection to a disposal system for relevant effluent streams to which BAT/AKART has been applied. Liquid wastestreams generated in the 200 East Area are currently discharged to the soil column. Included in these wastestreams are cooling water, steam condensate, raw water, and sanitary wastewaters. It is the policy of the DOE that the use of soil columns to treat and retain radionuclides and nonradioactive contaminants be discontinued at the earliest practical time in favor of wastewater treatment and waste minimization. In 1989, the DOE entered into an interagency agreement with Ecology and EPA. This agreement is referred to as the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). Project W-252 is one of the projects required to achieve the milestones set forth in the Tri-Party Agreement. One of the milestones requires BAT/AKART implementation for Phase II streams by October 1997. This Functional Design Criteria (FDC) document provides the technical baseline required to initiate Project W-252 to meet the Tri-Party Agreement milestone for the application of BAT/AKART to the Phase II effluents.

  14. Annual Report

    Energy Savers [EERE]

    1 2011 Annual Report to the Oak Ridge Community Annual Report to the Oak Ridge Community DOE/ORO/2399 Progress Cleanup P Progress Cleanup P 2 This report was produced by URS | CH2M Oak Ridge LLC, DOE's Environmental Management contractor for the Oak Ridge Reservation. About the Cover After recontouring and revegetation, the P1 Pond at East Tennessee Technology Park is flourishing. The contaminated pond was drained, recontoured, and restocked with fish that would not disturb the pond sediment. 1

  15. Special Report

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

    Report 193 Chemical Weekly June 16, 2015 T he Japanese rightly called them the seeds of ... occur in the same ore deposits as the lanthanides and exhibit similar chemical properties. ...

  16. AUDIT REPORT

    Office of Environmental Management (EM)

    Treatment of Salt Waste at the Savannah River Site OAS-L-15-09 August 2015 U.S. Department ... Audit Report: "Treatment of Salt Waste at the Savannah River Site" BACKGROUND The ...

  17. Final Report

    SciTech Connect (OSTI)

    Biros, George

    2014-08-18

    This the final report for the project "Large-Scale Optimization for Bayesian Inference in Complex Systems," for the work in the group of the co-PI George Biros.

  18. Final Report

    SciTech Connect (OSTI)

    DeTar, Carleton

    2012-12-10

    This document constitutes the Final Report for award DE-FC02-06ER41446 as required by the Office of Science. It summarizes accomplishments and provides copies of scientific publications with significant contribution from this award.

  19. Report2

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

    DC, April 1983.) 8 a) R.P. Reed et al., "The Economic Effects of Fracture in the United States," (Part 1-A Synopsis of the September 30, 1982 Report to NBS by Battelle...

  20. Workshop Reports

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

    we do not know why. Complete Executive Summary (pdf) Read entire Final Report (pdf) LA-UR 10-02959 Research Needs for Material Mixing at Extremes (pdf) Image of the Cover of...

  1. FINAL REPORT

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

    FINAL REPORT AEC-ERDA Research Contract AT (11-1) 2174 Columbia University's Nevis Laboratories "Research in Neutron Velocity Spectroscopy" James RainwatGr DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or

  2. FINAL REPORT

    Office of Scientific and Technical Information (OSTI)

    FINAL REPORT Analytical and Elemental Analysis of Air and Soil Samples Facility and Public Awareness Partnership (Training/Public Awareness) Congressionally Awarded Grant No. DE-FG02-05ER64045 Submitted to: U.S. Department of Energy Attn: William Henson Submitted by: Alabama A&M University Research Institute (AAMURI) [pic] October 1, 2007 This report reflects a joint training program at the Integrated Environmental Research and Services (IERS) of the Alabama A&M University Research

  3. SANDIA REPORT

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

    REPORT SAND 2011-3958 Unlimited Release Printed June 2011 Site Environmental Report for 2010 Sandia National Laboratories, California B.L. Larsen Prepared by Sandia National Laboratories Livermore, California 94550 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. Approved for

  4. SANDIA REPORT

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

    Study of the Use of Deep Saline Formations for Combined Thermoelectric Power Plant Water Needs and Carbon Sequestration at a Regional- Scale: Phase I Report. June, 2008 Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or

  5. SANDIA REPORT

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

    5-0587 Unlimited Release January 2015 Precursor Report of Data Needs and Recommended Practices for PV Plant Availability, Operations and Maintenance Reporting Roger R Hill, Geoffrey Klise; Sandia National Laboratories John R Balfour, High Performance PV Prepared by Roger Hill Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of

  6. SPECIAL REPORT

    Energy Savers [EERE]

    SPECIAL REPORT Enforcement Activities Conducted by the Federal Energy Regulatory Commission DOE/IG-0947 September 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 September 29, 2015 MEMORANDUM FOR THE CHAIRMAN, FEDERAL ENERGY REGULATORY COMMISSION FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Special Report: "Enforcement Activities Conducted by the Federal Energy Regulatory

  7. Reporting Requirements

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

    Reporting Requirements Reporting Requirements Contacts Director Albert Migliori Deputy Franz Freibert 505 667-6879 Email Professional Staff Assistant Susan Ramsay 505 665 0858 Email The Fellow will be required to participate in the Actinide Science lecture series by both attending lectures and presenting a scientific lecture on actinide science in this series. Submission of a viewgraph and brief write-up of the project. Provide metrics information as requested. Submission of an overview article

  8. Final Report

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

    Final Report Document Number 11123-23.Final Field Demonstration of Eco-Friendly Creation of Propped Hydraulic Fractures Contract Number: 11123-23.Final February 16, 2015 Nadji Benrabah (Author) Engineer CSI Technologies 1930 W.W. Thorne Dr. Houston, TX 77073 Phil Van Trump (Principal Investigator) Chief Technology Officer DaniMer Scientific, LLC 1301 Colquitt Highway Bainbridge, GA 39817 2 LEGAL NOTICE This report was prepared by DaniMer Scientific, LLC as an account of work sponsored by the

  9. Application of multi-criteria decision-making on strategic municipal solid waste management in Dalmatia, Croatia

    SciTech Connect (OSTI)

    Vego, Goran Kucar-Dragicevic, Savka Koprivanac, Natalija

    2008-11-15

    The efficiency of providing a waste management system in the coastal part of Croatia consisting of four Dalmatian counties has been modelled. Two multi-criteria decision-making (MCDM) methods, PROMETHEE and GAIA, were applied to assist with the systematic analysis and evaluation of the alternatives. The analysis covered two levels; first, the potential number of waste management centres resulting from possible inter-county cooperation; and second, the relative merits of siting of waste management centres in the coastal or hinterland zone was evaluated. The problem was analysed according to several criteria; and ecological, economic, social and functional criteria sets were identified as relevant to the decision-making process. The PROMETHEE and GAIA methods were shown to be efficient tools for analysing the problem considered. Such an approach provided new insights to waste management planning at the strategic level, and gave a reason for rethinking some of the existing strategic waste management documents in Croatia.

  10. Brittle Failure Design Criteria for Ductile Cast Iron Spent-Fuel

    Office of Scientific and Technical Information (OSTI)

    Am. SOC. of Mech. Engineers, (1980). 3. "Pressure Vessel Codes: Their Application to Nuclear Reactor Systems," Technical Reports Series No. 56, International Atomic Energy...

  11. Comparison of Test Procedures and Energy Efficiency Criteria in Selected International Standards and Labeling Programs for Clothes Washers, Water Dispensers, Vending Machines and CFLs

    SciTech Connect (OSTI)

    Fridley, David; Zheng, Nina; Zhou, Nan

    2010-06-01

    Since the late 1970s, energy labeling programs and mandatory energy performance standards have been used in many different countries to improve the efficiency levels of major residential and commercial equipment. As more countries and regions launch programs covering a greater range of products that are traded worldwide, greater attention has been given to harmonizing the specific efficiency criteria in these programs and the test methods for measurements. For example, an international compact fluorescent light (CFL) harmonization initiative was launched in 2006 to focus on collaboration between Australia, China, Europe and North America. Given the long history of standards and labeling programs, most major energy-consuming residential appliances and commercial equipment are already covered under minimum energy performance standards (MEPS) and/or energy labels. For these products, such as clothes washers and CFLs, harmonization may still be possible when national MEPS or labeling thresholds are revised. Greater opportunity for harmonization exists in newer energy-consuming products that are not commonly regulated but are under consideration for new standards and labeling programs. This may include commercial products such as water dispensers and vending machines, which are only covered by MEPS or energy labels in a few countries or regions. As China continues to expand its appliance standards and labeling programs and revise existing standards and labels, it is important to learn from recent international experiences with efficiency criteria and test procedures for the same products. Specifically, various types of standards and labeling programs already exist in North America, Europe and throughout Asia for products in China's 2010 standards and labeling programs, namely clothes washers, water dispensers, vending machines and CFLs. This report thus examines similarities and critical differences in energy efficiency values, test procedure specifications and other technical performance requirements in existing international programs in order to shed light on where Chinese programs currently stands and considerations for their 2010 programs.

  12. Criteria and Processes for the Certification of Non-Radioactive Hazardous and Non-Hazardous Wastes

    SciTech Connect (OSTI)

    Dominick, J

    2008-12-18

    This document details Lawrence Livermore National Laboratory's (LLNL) criteria and processes for determining if potentially volumetrically contaminated or potentially surface contaminated wastes are to be managed as material containing residual radioactivity or as non-radioactive. This document updates and replaces UCRL-AR-109662, Criteria and Procedures for the Certification of Nonradioactive Hazardous Waste (Reference 1), also known as 'The Moratorium', and follows the guidance found in the U.S. Department of Energy (DOE) document, Performance Objective for Certification of Non-Radioactive Hazardous Waste (Reference 2). The 1992 Moratorium document (UCRL-AR-109662) is three volumes and 703 pages. The first volume provides an overview of the certification process and lists the key radioanalytical methods and their associated Limits of Sensitivities. Volumes Two and Three contain supporting documents and include over 30 operating procedures, QA plans, training documents and organizational charts that describe the hazardous and radioactive waste management system in place in 1992. This current document is intended to update the previous Moratorium documents and to serve as the top-tier LLNL institutional Moratorium document. The 1992 Moratorium document was restricted to certification of Resource Conservation and Recovery Act (RCRA), State and Toxic Substances Control Act (TSCA) hazardous waste from Radioactive Material Management Areas (RMMA). This still remains the primary focus of the Moratorium; however, this document increases the scope to allow use of this methodology to certify other LLNL wastes and materials destined for off-site disposal, transfer, and re-use including non-hazardous wastes and wastes generated outside of RMMAs with the potential for DOE added radioactivity. The LLNL organization that authorizes off-site transfer/disposal of a material or waste stream is responsible for implementing the requirements of this document. The LLNL Radioactive and Hazardous Waste Management (RHWM) organization is responsible for the review and maintenance of this document. It should be noted that the DOE metal recycling moratorium is still in effect and is implemented as outlined in reference 17 when metals are being dispositioned for disposal/re-use/recycling off-site. This document follows the same methodology as described in the previously approved 1992 Moratorium document. Generator knowledge and certification are the primary means of characterization. Sampling and analysis are used when there is insufficient knowledge of a waste to determine if it contains added radioactivity. Table 1 (page 12) presents a list of LLNL's analytical methods for evaluating volumetrically contaminated waste and updates the reasonably achievable analytical-method-specific Minimum Detectable Concentrations (MDCs) for various matrices. Results from sampling and analysis are compared against the maximum MDCs for the given analytical method and the sample specific MDC to determine if the sample contains DOE added volumetric radioactivity. The evaluation of an item that has a physical form, and history of use, such that accessible surfaces may be potentially contaminated, is based on DOE Order 5400.5 (Reference 3), and its associated implementation guidance document DOE G 441.1-XX, Control and Release of Property with Residual Radioactive Material (Reference 4). The guidance document was made available for use via DOE Memorandum (Reference 5). Waste and materials containing residual radioactivity transferred off-site must meet the receiving facilities Waste Acceptance Criteria (if applicable) and be in compliance with other applicable federal or state requirements.

  13. Hydrogen Energy Storage and Power-to-Gas: Establishing Criteria for Successful Business Cases

    SciTech Connect (OSTI)

    Eichman, Joshua; Melaina, Marc

    2015-10-27

    As the electric sector evolves and increasing amounts of variable generation are installed on the system, there are greater needs for system flexibility, sufficient capacity and greater concern for overgeneration. As a result there is growing interest in exploring the role of energy storage and demand response technologies to support grid needs. Hydrogen is a versatile feedstock that can be used in a variety of applications including chemical and industrial processes, as well as a transportation fuel and heating fuel. Traditionally, hydrogen technologies focus on providing services to a single sector; however, participating in multiple sectors has the potential to provide benefits to each sector and increase the revenue for hydrogen technologies. The goal of this work is to explore promising system configurations for hydrogen systems and the conditions that will make for successful business cases in a renewable, low-carbon future. Current electricity market data, electric and gas infrastructure data and credit and incentive information are used to perform a techno-economic analysis to identify promising criteria and locations for successful hydrogen energy storage and power-to-gas projects. Infrastructure data will be assessed using geographic information system applications. An operation optimization model is used to co-optimizes participation in energy and ancillary service markets as well as the sale of hydrogen. From previous work we recognize the great opportunity that energy storage and power-to-gas but there is a lack of information about the economic favorability of such systems. This work explores criteria for selecting locations and compares the system cost and potential revenue to establish competitiveness for a variety of equipment configurations. Hydrogen technologies offer unique system flexibility that can enable interactions between multiple energy sectors including electric, transport, heating fuel and industrial. Previous research established that hydrogen technologies, and in particular electrolyzers, can respond fast enough and for sufficient duration to participate in electricity markets. This work recognizes that participation in electricity markets and integration with the gas system can enhance the revenue streams available for hydrogen storage systems and quantifies the economic competitiveness and of these systems. A few of the key results include 1) the most valuable revenue stream for hydrogen systems is to sell the produced hydrogen, 2) participation in both energy and ancillary service markets yields the greatest revenue and 3) electrolyzers acting as demand response devices are particularly favorable.

  14. Hollow clay tile wall program summary report

    SciTech Connect (OSTI)

    Henderson, R.C.; Jones, W.D.

    1995-07-30

    Many of the Y-12 Plant buildings, constructed during the 1940s and 1950s, consist of steel ed concrete framing infilled with hollow clay tile (HCT). The infill was intended to provide for building enclosure and was not designed to have vertical or lateral load-carrying capacity. During the late 1970s and early 1980s, seismic and wind evaluations were performed on many of these buildings in conjunction with the preparation of a site-wide safety analysis report. This analytical work, based on the best available methodology, considered lateral load-carrying capacity of the HCT infill on the basis of building code allowable shear values. In parallel with the analysis effort, DOE initiated a program to develop natural phenomena capacity and performance criteria for existing buildings, but these criteria did not specify guidelines for determining the lateral force capacity of frames infilled with HCT. The evaluation of infills was, therefore, based on the provisions for the design of unreinforced masonry as outlined in standard masonry codes. When the results of the seismic and wind evaluations were compared with the new criteria, the projected building capacities fell short of the requirements. Apparently, if the buildings were to meet the new criteria, many millions of dollars would be required for building upgrades. Because the upgrade costs were significant, the assumptions and approaches used in the analyses were reevaluated. Four issues were identified: (1) Once the infilled walls cracked, what capacity (nonlinear response), if any, would the walls have to resist earthquake or wind loads applied in the plane of the infill (in-plane)? (2) Would the infilled walls remain within the steel or reinforced concrete framing when subjected to earthquake or high wind loads applied perpendicular to the infill (out-of-plane)? (3) What was the actual shear capacity of the HCT infill? (4) Was modeling the HCT infill as a shear wall the best approach?

  15. Usage Reports

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

    Reports Usage Reports Batch Job Statistics See queue wait times, hours used, top users and other summary statistics for jobs run at NERSC (login required). Read More » Parallel Job Statistics (Cray aprun) [rest... Read More » Historical Data Edison Job Size Charts Fraction of Hours Used per Job Size Note: Interactive charts with current and past Cori and Edison data are now available on MyNERSC This chart shows the fraction of hours used on Edison in each of 5 job-core-size bins. 2015 2014

  16. SANDIA REPORT

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

    .VUQ.SAUQ.P6.02; Apply VUQ Practices With Dakota to COBRA-TF for AMA-Relevant Problems Vincent Mousseau Brian Adams Kostadin Ivanov Maria Avramova Robert Salko Taylor Blyth Sandia National Laboratories April 2013: CASL-U-2013-0048-000 SANDIA REPORT SAND2013-3093 Unlimited Release Printed April 2013 CASL L3 Milestone Report: L3:VUQ.SAUQ.P6.02; Apply VUQ Practices with Dakota to COBRA-TF for AMA-Relevant Problems Vincent Mousseau Brian Adams Kostadin Ivanov Maria Avramova Robert Salko Taylor Blyth

  17. Annual Report

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

    09 THROUGH 09/30/2010 The following Annual Freedom of Information Act report covers the Period 10/01/2009, through 09/30/2010, as required by 5 U.S.C. 552. I. BASIC INFORMATION REGARDING REPORT 1. Kevin T. Hagerty, Director Office of Information Resources, MA-90 U.S. Department of Energy 1000 Independence Ave., SW Washington, DC 20585 202-586-5955 Alexander Morris, FOIA Officer Sheila Jeter, FOIA/Privacy Act Specialist FOIA Office, MA-90 Office of Information Resources U.S. Department of Energy

  18. Lidar Report

    SciTech Connect (OSTI)

    Wollpert.

    2009-04-01

    This report provides an overview of the LiDAR acquisition methodology employed by Woolpert on the 2009 USDA - Savannah River LiDAR Site Project. LiDAR system parameters and flight and equipment information is also included. The LiDAR data acquisition was executed in ten sessions from February 21 through final reflights on March 2, 2009; using two Leica ALS50-II 150kHz Multi-pulse enabled LiDAR Systems. Specific details about the ALS50-II systems are included in Section 4 of this report.

  19. Audit Report: OAS-L-03-10 | Department of Energy

    Energy Savers [EERE]

    0 Audit Report: OAS-L-03-10 February 19, 2003 Audit of the Research and Development Investment Criteria for Fossil Energy The purpose of this report is to inform you of the results of our review of Research and Development (R&D) Investment Criteria for Fossil Energy. This review was initiated in August 2002 and fieldwork was conducted through December 2002 at Department Headquarters and the National Energy Technology Laboratory (NETL). The review methodology is described in the attachment to

  20. Foreign Affairs Information System (FAIS) Early Operational Capability (EOC) network security criteria

    SciTech Connect (OSTI)

    Not Available

    1988-09-12

    The Joint Center for Information Security Technology (JCIST) at Oak Ridge, Tennessee, under an interagency agreement between the Department of State (DOS) and the Department of Energy (DOE), has been tasked with the security certification testing of the Foreign Affairs Information system (FAIS) Early Operational Capability (EOC) software. The basis for this certification is the FAIS (EOC) Security Requirements Allocation (SRA) document. This document defines the security requirements for the FAIS EOC software. Security certification of the FAIS system is the responsibility of the Office of Information Systems Security, Bureau of Diplomatic Security (DS/ST/ISS). The overall FAIS EOC certification will be completed in two general steps. First, a test of a stand-alone FAIS EOC system against the SRA requirements which is currently in progress. Second is a test of all FAIS network system interfaces against the SRA requirements as expanded to adequately address the network security issues. This accumulation of requirements is referred to as the FAIS EOC Network Security Criteria. 5 refs.

  1. Cost savings deliverables and criteria for the OST technology decision process

    SciTech Connect (OSTI)

    McCown, A.

    1997-04-01

    This document has been prepared to assist focus area (FA) technical and management teams in understanding the cost savings deliverables associated with a technology system during its research and development (R and D) phases. It discusses the usefulness of cost analysis in the decision-making process, and asserts that the level of confidence and data quality of a cost analysis is proportional to the maturity of the technology system`s development life cycle. Suggestions of specific investment criteria or cost savings metrics that a FA might levy on individual research projects are made but the final form of these elements should be stipulated by the FA management based on their rationale for a successful technology development project. Also, cost savings deliverables for a single FA will be more detailed than those for management of the Office of Science and Technology (OST). For example, OST management may want an analysis of the overall return on investment for each FA, while the FA program manager may want this analysis and the return on investment metrics for each technology research activity the FA supports.

  2. Unveiling Stability Criteria of DNA-Carbon Nanotubes Constructs by Scanning Tunneling Microscopy and Computational Modeling

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

    Kilina, Svetlana; Yarotski, Dzmitry A.; Talin, A. Alec; Tretiak, Sergei; Taylor, Antoinette J.; Balatsky, Alexander V.

    2011-01-01

    We present a combined approach that relies on computational simulations and scanning tunneling microscopy (STM) measurements to reveal morphological properties and stability criteria of carbon nanotube-DNA (CNT-DNA) constructs. Application of STM allows direct observation of very stable CNT-DNA hybrid structures with the well-defined DNA wrapping angle of 63.4 ° and a coiling period of 3.3 nm. Using force field simulations, we determine how the DNA-CNT binding energy depends on the sequence and binding geometry of a single strand DNA. This dependence allows us to quantitatively characterize the stability of a hybrid structure with an optimal π-stacking between DNA nucleotides andmore » the tube surface and better interpret STM data. Our simulations clearly demonstrate the existence of a very stable DNA binding geometry for (6,5) CNT as evidenced by the presence of a well-defined minimum in the binding energy as a function of an angle between DNA strand and the nanotube chiral vector. This novel approach demonstrates the feasibility of CNT-DNA geometry studies with subnanometer resolution and paves the way towards complete characterization of the structural and electronic properties of drug-delivering systems based on DNA-CNT hybrids as a function of DNA sequence and a nanotube chirality.« less

  3. 340 Facility Secondary Containment and Leak Detection Project W-302 Functional Design Criteria

    SciTech Connect (OSTI)

    Stordeur, R.T.

    1995-03-01

    This functional design criteria for the upgrade to the 340 radioactive liquid waste storage facility (Project W-302) specifically addresses the secondary containment issues at the current vault facility of the 340 Complex. This vault serves as the terminus for the Radioactive Liquid Waste System (RLWS). Project W-302 is necessary in order to bring this portion of the Complex into full regulatory compliance. The project title, ``340 Facility Secondary Containment and Leak Detection``, illustrates preliminary thoughts of taking corrective action directly upon the existing vault (such as removing the tanks, lining the vault, and replacing tanks). However, based on the conclusion of the engineering study, ``Engineering Study of the 300 Area Process Wastewater Handling System``, WHC-SD-WM-ER-277 (as well as numerous follow-up meetings with cognizant staff), this FDC prescribes a complete replacement of the current tank/vault system. This offers a greater array of tanks, and provides greater operating flexibility and ease of maintenance. This approach also minimizes disruption to RLWS services during ``tie-in``, as compared to the alternative of trying to renovate the old vault. The proposed site is within the current Complex area, and maintains the receipt of RLWS solutions through gravity flow.

  4. Use of Multiple Criteria to Map the High-Temperature Scuffing Behaviorof Co-Based Superalloys

    SciTech Connect (OSTI)

    Blau, Peter Julian; YaoPhD, Matthew; Qu, Jun; WuPhD, James

    2009-01-01

    The goal of thisworkwas to rank, as quantitatively as possible, the high-temperature scuffing characteristics of a series of Co-based materials, including coatings, for possible use inwear-critical components like those in diesel engine exhaust systems and emission-controls. A cylinder pivoting on its side against a flat tilewas used as the testing geometry. All testswere performed at 600 C in air. The time-dependent torque response was recorded for each 60 min test to investigate trends in friction as surfaces roughened and debris deposits built up. Candidate materials included Stellite 6B, Pleuco 33 (a white cast iron), nitrided stainless steel Type 310, IDM 5399 (a high-silicon, molybdenum iron), and coatings of both Tribaloy T-400 and Stellite 3 on stainless steel. Measurements of the damaged areas on the scuffed tiles were used to calculate a specific normal load and plot it versus the roughness of the worn tiles to map experimental results in a way that indicated the severity of scuffing for each material combination. Data on the map were annotated to reflect visual observations of the extent of damage as well. Using this test method and the foregoing criteria, nitrided type 310 stainless steel against T-400 gave the best overall performance.

  5. American National Standard: design criteria for an independent spent-fuel-storage installation (water pool type)

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

    This standard provides design criteria for systems and equipment of a facility for the receipt and storage of spent fuel from light water reactors. It contains requirements for the design of major buildings and structures including the shipping cask unloading and spent fuel storage pools, cask decontamination, unloading and loading areas, and the surrounding buildings which contain radwaste treatment, heating, ventilation and air conditioning, and other auxiliary systems. It contains requirements and recommendations for spent fuel storage racks, special equipment and area layout configurations, the pool structure and its integrity, pool water cleanup, ventilation, residual heat removal, radiation monitoring, fuel handling equipment, cask handling equipment, prevention of criticality, radwaste control and monitoring systems, quality assurance requirements, materials accountability, and physical security. Such an installation may be independent of both a nuclear power station and a reprocessing facility or located adjacent to any of these facilities in order to share selected support systems. Support systems shall not include a direct means of transferring fuel assemblies from the nuclear facility to the installation.

  6. Development of flaw acceptance criteria for aging management of spent nuclear fuel multiple-purpose canisters

    SciTech Connect (OSTI)

    Lam, P.; Sindelar, R.

    2015-03-09

    A typical multipurpose canister (MPC) is made of austenitic stainless steel and is loaded with spent nuclear fuel assemblies. The canister may be subject to service-induced degradation when it is exposed to aggressive atmospheric environments during a possibly long-term storage period if the permanent repository is yet to be identified and readied. Because heat treatment for stress relief is not required for the construction of an MPC, stress corrosion cracking may be initiated on the canister surface in the welds or in the heat affected zone. An acceptance criteria methodology is being developed for flaw disposition should the crack-like defects be detected by periodic In-service Inspection. The first-order instability flaw sizes has been determined with bounding flaw configurations, that is, through-wall axial or circumferential cracks, and part-through-wall long axial flaw or 360° circumferential crack. The procedure recommended by the American Petroleum Institute (API) 579 Fitness-for-Service code (Second Edition) is used to estimate the instability crack length or depth by implementing the failure assessment diagram (FAD) methodology. The welding residual stresses are mostly unknown and are therefore estimated with the API 579 procedure. It is demonstrated in this paper that the residual stress has significant impact on the instability length or depth of the crack. The findings will limit the applicability of the flaw tolerance obtained from limit load approach where residual stress is ignored and only ligament yielding is considered.

  7. Development of flaw acceptance criteria for aging management of spent nuclear fuel multi-purpose canisters

    SciTech Connect (OSTI)

    Lam, Poh -Sang; Sindelar, Robert L.

    2015-03-09

    A typical multipurpose canister (MPC) is made of austenitic stainless steel and is loaded with spent nuclear fuel assemblies. The canister may be subject to service-induced degradation when it is exposed to aggressive atmospheric environments during a possibly long-term storage period if the permanent repository is yet to be identified and readied. Because heat treatment for stress relief is not required for the construction of an MPC, stress corrosion cracking may be initiated on the canister surface in the welds or in the heat affected zone. An acceptance criteria methodology is being developed for flaw disposition should the crack-like defects be detected by periodic in-service Inspection. The first-order instability flaw sizes has been determined with bounding flaw configurations, that is, through-wall axial or circumferential cracks, and part-through-wall long axial flaw or 360° circumferential crack. The procedure recommended by the American Petroleum Institute (API) 579 Fitness-for-Service code (Second Edition) is used to estimate the instability crack length or depth by implementing the failure assessment diagram (FAD) methodology. The welding residual stresses are mostly unknown and are therefore estimated with the API 579 procedure. It is demonstrated in this paper that the residual stress has significant impact on the instability length or depth of the crack. The findings will limit the applicability of the flaw tolerance obtained from limit load approach where residual stress is ignored and only ligament yielding is considered.

  8. Global Failure Criteria for Positive/Electrolyte/Negative Structure of Planar Solid Oxide Fuel Cell

    SciTech Connect (OSTI)

    Liu, Wenning N.; Sun, Xin; Khaleel, Mohammad A.; Qu, Jianmin

    2009-07-15

    Due to mismatch of the coefficients of thermal expansion of various layers in the positive/electrolyte/negative (PEN) structures of solid oxide fuel cells (SOFC), thermal stresses and warpage on the PEN are unavoidable due to the temperature changes from the stress-free sintering temperature to room temperature during the PEN manufacturing process. In the meantime, additional mechanical stresses will also be created by mechanical flattening during the stack assembly process. In order to ensure the structural integrity of the cell and stack of SOFC, it is necessary to develop failure criteria for SOFC PEN structures based on the initial flaws occurred during cell sintering and stack assembly. In this paper, the global relationship between the critical energy release rate and critical curvature and maximum displacement of the warped cells caused by the temperature changes as well as mechanical flattening process is established so that possible failure of SOFC PEN structures may be predicted deterministically by the measurement of the curvature and displacement of the warped cells.

  9. Hot Cell Facility (HCF) Safety Analysis Report

    SciTech Connect (OSTI)

    MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.; MAHN,JEFFREY A.; BERRY,DONALD T.; SCHWERS,NORMAN F.; VANDERBEEK,THOMAS E.; NAEGELI,ROBERT E.

    2000-11-01

    This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR.

  10. Activity report

    SciTech Connect (OSTI)

    Yu, S W

    2008-08-11

    This report is aimed to show the author's activities to support the LDRD. The title is 'Investigation of the Double-C Behavior in the Pu-Ga Time-Temperature-Transformation Diagram' The sections are: (1) Sample Holder Test; (2) Calculation of x-ray diffraction patterns; (3) Literature search and preparing publications; (4) Tasks Required for APS Experiments; and (5) Communications.

  11. Occurrence Reporting

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

    1995-09-25

    To establish and maintain a system for reporting operations information related to DOE-owned or -operated facilities and processing that information to identify the root causes of Unusual, Off-Normal, and Emergency Occurrences and provide for appropriate corrective action. Cancels DOE 5000.3B.

  12. Assessment of health-care waste disposal methods using a VIKOR-based fuzzy multi-criteria decision making method

    SciTech Connect (OSTI)

    Liu, Hu-Chen [School of Management, Hefei University of Technology, Hefei 230009 (China); Department of Industrial Engineering and Management, Tokyo Institute of Technology, Tokyo 152-8552 (Japan); Wu, Jing [Department of Public Management, Tongji University, Shanghai 200092 (China); Li, Ping, E-mail: yiwuchulp@126.com [Shanghai Pudong New Area Zhoupu Hospital, No. 135 Guanyue Road, Shanghai 201318 (China); East Hospital Affiliated to Tongji University, No. 150 Jimo Road, Shanghai 200120 (China)

    2013-12-15

    Highlights: Propose a VIKOR-based fuzzy MCDM technique for evaluating HCW disposal methods. Linguistic variables are used to assess the ratings and weights for the criteria. The OWA operator is utilized to aggregate individual opinions of decision makers. A case study is given to illustrate the procedure of the proposed framework. - Abstract: Nowadays selection of the appropriate treatment method in health-care waste (HCW) management has become a challenge task for the municipal authorities especially in developing countries. Assessment of HCW disposal alternatives can be regarded as a complicated multi-criteria decision making (MCDM) problem which requires consideration of multiple alternative solutions and conflicting tangible and intangible criteria. The objective of this paper is to present a new MCDM technique based on fuzzy set theory and VIKOR method for evaluating HCW disposal methods. Linguistic variables are used by decision makers to assess the ratings and weights for the established criteria. The ordered weighted averaging (OWA) operator is utilized to aggregate individual opinions of decision makers into a group assessment. The computational procedure of the proposed framework is illustrated through a case study in Shanghai, one of the largest cities of China. The HCW treatment alternatives considered in this study include incineration, steam sterilization, microwave and landfill. The results obtained using the proposed approach are analyzed in a comparative way.

  13. CRAD, Criteria and Guidelines For the Assessment of Safety System Software and Firmware at Defense Nuclear Facilities

    Broader source: Energy.gov [DOE]

    The purpose and scope of this CRAD is to provide a set of consistent assessment criteria and guidelines for the assessment of safety system software and firmware that performs an SC or SS function, as described in the Background section. The scope of the assessment, henceforth, is called "I&C software."

  14. Compliance with Waste Acceptance Criteria of WIPP and NTS for Vitrified Low-Level and TRU Waste Forms

    SciTech Connect (OSTI)

    Harbour, J.R.; Andrews, M.K.

    1998-07-01

    A joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) has been established to evaluate vitrification as an option for the immobilization of waste within ORNL tank farms. This paper presents details of calculations based on current best available analyses of the Oak Ridge Tanks on the limits for waste loadings imposed by the waste acceptance criteria.

  15. STRUCTURAL DESIGN CRITERIA FOR TARGET/BLANKET SYSTEM COMPONENT MATERIALS FOR THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT

    SciTech Connect (OSTI)

    W. JOHNSON; R. RYDER; P. RITTENHOUSE

    2001-01-01

    The design of target/blanket system components for the Accelerator Production of Tritium (APT) plant is dependent on the development of materials properties data specified by the designer. These data are needed to verify that component designs are adequate. The adequacy of the data will be related to safety, performance, and economic considerations, and to other requirements that may be deemed necessary by customers and regulatory bodies. The data required may already be in existence, as in the open technical literature, or may need to be generated, as is often the case for the design of new systems operating under relatively unique conditions. The designers' starting point for design data needs is generally some form of design criteria used in conjunction with a specified set of loading conditions and associated performance requirements. Most criteria are aimed at verifying the structural adequacy of the component, and often take the form of national or international standards such as the ASME Boiler and Pressure Vessel Code (ASME B and PV Code) or the French Nuclear Structural Requirements (RCC-MR). Whether or not there are specific design data needs associated with the use of these design criteria will largely depend on the uniqueness of the conditions of operation of the component. A component designed in accordance with the ASME B and PV Code, where no unusual environmental conditions exist, will utilize well-documented, statistically-evaluated developed in conjunction with the Code, and will not be likely to have any design data needs. On the other hand, a component to be designed to operate under unique APT conditions, is likely to have significant design data needs. Such a component is also likely to require special design criteria for verification of its structural adequacy, specifically accounting for changes in materials properties which may occur during exposure in the service environment. In such a situation it is common for the design criteria and design data needs to evolve as the design progresses, operating conditions are refined, and materials characteristics in the unique environment are established. This paper develops the relationship between the designers' data needs and the structural design criteria recently adopted for the Target Blanket System of the APT. The latter, the newly-developed APT Supplemental Structural Design Requirements (APT SSDR), was patterned after the design criteria developed for the International Thermonuclear Experimental (Fusion) Reactor (ITER). A summary description of the design rules based on the APT SSDR is presented, and the impact of these rules of changes in materials properties resulting from exposure in the APT proton/neutron irradiation environment are discussed.

  16. ASSESSMENT REPORT

    Energy Savers [EERE]

    & Wilcox Technical Services Pantex LLC During Fiscal Year 2013 Through June 30, 2014, Under Department of Energy Contract No. DE-AC54-00AL66620 OAI-V-16-04 February 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 February 12, 2016 MEMORANDUM FOR THE MANAGER, NNSA PRODUCTION OFFICE FROM: David Sedillo, Director Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Assessment Report on

  17. AUDIT REPORT

    Energy Savers [EERE]

    AU Organization Chart AU Organization Chart AU Organization Chart: December 22, 2015 PDF icon AU Organization Chart: December 22, 2015 More Documents & Publications FTCP Senior Technical Safety Manager (STSM) Status Report USW Health Safety and Environment Conference - HSS Workshop Organizational Chart

    Management of the Startup of the Sodium-Bearing Waste Treatment Facility DOE-OIG-16-09 March 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections

  18. AUDIT REPORT

    Energy Savers [EERE]

    and Oversight of Information Technology Contracts at the Department of Energy's Hanford Site DOE-OIG-16-10 April 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 April 1, 2016 MEMORANDUM FOR THE SECRETARY FROM: Rickey R. Hass Acting Inspector General SUBJECT: INFORMATION: Audit Report on the "Management and Oversight of Information Technology Contracts at the Department of Energy's Hanford Site"

  19. Final Report

    Office of Scientific and Technical Information (OSTI)

    Internal magnetic field, temperature, and density measurements on magnetized HED plasmas using Pulsed Polarimetry DOE Grant ER55034, UW grant # 61-9515 - High Energy Density, Office of Fusion Science Roger J Smith (PI) Dept. Aeronautics and Astronautics, University of Washington, Seattle, Wa 98195 smith@aa.washington.edu, 206 543 6323 (AA grants administrator) June 11, 2014 Report submitted to: Formerly Dr. Francis Thio Program Manager, DOE Office of Fusion Energy Sciences Nominal Grant Period:

  20. SANDIA REPORT

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

    3-3735 Unlimited Release Printed June 2013 Site Environmental Report for 2012 Sandia National Laboratories, California Barbara L. Larsen Prepared by Sandia National Laboratories Livermore, California 94550 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. Approved for public

  1. SANDIA REPORT

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

    4-4161 Unlimited Release Printed June 2014 Site Environmental Report for 2013 Sandia National Laboratories, California Barbara L. Larsen Prepared by Sandia National Laboratories Livermore, California 94550 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. Approved for public

  2. SANDIA REPORT

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

    2-4417 Unlimited Release Printed June 2012 Site Environmental Report for 2011 Sandia National Laboratories, California B.L. Larsen Prepared by Sandia National Laboratories Livermore, California 94550 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. Approved for public release,

  3. SANDIA REPORT

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

    5-4277 Unlimited Release Printed June 2015 Site Environmental Report for 2014 Sandia National Laboratories, California Barbara L. Larsen Prepared by Sandia National Laboratories Livermore, California 94550 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. Approved for public

  4. SANDIA REPORT

    Energy Savers [EERE]

    Russel Edge About Us Russel Edge Team Leader, Uranium Mine Team Russel Edge became an LM staff member on November 2, 2014, as a Business Management Specialist in the Westminster, Colorado, office. He reports directly to the DOE Office of Site Operations Director. Prior to joining LM, Russel was employed by the National Nuclear Security Administration Sandia field office in Albuquerque, New Mexico, as a program manager for the Laboratory Directed Research and Development (LDRD) program and point

  5. AUDIT REPORT

    Energy Savers [EERE]

    Management of Information Technology Hardware DOE/IG-0926 October 2014 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 October 30, 2014 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "Follow-up on the Department of Energy's Management of Information Technology Hardware" BACKGROUND The Department of Energy and its facility contractors rely on

  6. AUDIT REPORT

    Energy Savers [EERE]

    Management of High-Risk Excess Facilities DOE/IG-0931 January 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 January 23, 2015 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "The Department of Energy's Management of High-Risk Excess Facilities" BACKGROUND Fifty years of nuclear weapons production and energy research during the Manhattan

  7. AUDIT REPORT

    Energy Savers [EERE]

    Procurement of Parts and Materials for the Waste Treatment and Immobilization Plant at the Hanford Site DOE-OIG-16-03 November 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 November 17, 2015 MEMORANDUM FOR THE SECRETARY FROM: Rickey R. Hass Acting Inspector General SUBJECT: INFORMATION: Audit Report: "Procurement of Parts and Materials for the Waste Treatment and Immobilization Plant at the Hanford

  8. AUDIT REPORT

    Energy Savers [EERE]

    5 Consolidated Financial Statements OAI-FS-16-01 November 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 November 16, 2015 MEMORANDUM FOR THE SECRETARY FROM: Rickey R. Hass Acting Inspector General SUBJECT: INFORMATION: Audit Report: "Department of Energy's Fiscal Year 2015 Consolidated Financial Statements" Pursuant to requirements established by the Government Management Reform Act of 1994, the

  9. AUDIT REPORT

    Energy Savers [EERE]

    Issues Management at the Los Alamos Field Office OAI-M-16-02 December 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 December 7, 2015 MEMORANDUM FOR THE MANAGER, LOS ALAMOS FIELD OFFICE FROM: Daniel M. Weeber Assistant Inspector General for Audits and Administration Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Issues Management at the Los Alamos Field Office" BACKGROUND The

  10. AUDIT REPORT

    Energy Savers [EERE]

    Audit of the Department of Energy's Management of Contractor Fines, Penalties, and Legal Costs DOE-OIG-16-06 February 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 February 5, 2016 MEMORANDUM FOR THE SECRETARY FROM: Rickey R. Hass Acting Inspector General SUBJECT: INFORMATION: Audit Report on the "Followup Audit of the Department of Energy's Management of Contractor Fines, Penalties, and Legal

  11. AUDIT REPORT

    Energy Savers [EERE]

    Corrective Action Program at the Waste Treatment and Immobilization Plant OAI-M-16-06 February 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 February 1, 2016 MEMORANDUM FOR THE ASSISTANT SECRETARY FOR ENVIRONMENTAL MANAGEMENT FROM: George Collard Deputy Inspector General for Audits and Inspections Office of Inspector General SUBJECT: INFORMATION: Audit Report on the "Corrective Action Program at the

  12. AUDIT REPORT

    Energy Savers [EERE]

    National Laboratory DOE-OIG-16-07 February 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 February 25, 2016 MEMORANDUM FOR THE SECRETARY FROM: Rickey R. Hass Acting Inspector General SUBJECT: INFORMATION: Audit Report on "Issues Management at the Los Alamos National Laboratory" BACKGROUND The Department of Energy's Los Alamos National Laboratory (LANL) is part of the National Nuclear Security

  13. Annual Report

    Energy Savers [EERE]

    Report Fiscal Year 2011 Office of Environment, Security, Safety and Health The Office of Fossil Energy: Striving for Environmental, Security, Safety and Health (ESS&H) and Sustainability Excellence I The Department of Energy's Office of Fossil Energy (FE) is dedicated to ensuring that the nation can continue to rely on traditional resources for clean, affordable energy while enhancing sustainability across its three sites: the Strategic Petroleum Reserve (SPR), the National Energy Technology

  14. SANDIA REPORT

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

    12 Unlimited Release Printed December 2014 PV Reliability Operations and Maintenance (PVROM) Database Initiative: 2014 Progress Report Geoffrey T. Klise, Roger R. Hill, Colin J. Hamman, Peter H. Kobos, Vipin Gupta, Benjamin B. Yang, Sandia National Laboratories Nadav Enbar, Electric Power Research Institute Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 Sandia National Laboratories is a multi-program laboratory managed and operated by

  15. SANDIA REPORT

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

    4778 Unlimited Release July 2011 Utility-Scale Grid-Tied PV Inverter Reliability Workshop Summary Report Stanley Atcitty, Jennifer E. Granata, Michael A. Quintana, Coryne A. Tasca Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 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

  16. SANDIA REPORT

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

    09 Unlimited Release SAND2010-7245P Printed October 2010 Annual Groundwater Monitoring Report Prepared by Sandia National Laboratories, Albuquerque, New Mexico 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. Approved for public release; further dissemination unlimited Issued

  17. AUDIT REPORT

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

    5 Consolidated Financial Statements OAI-FS-16-01 November 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 November 16, 2015 MEMORANDUM FOR THE SECRETARY FROM: Rickey R. Hass Acting Inspector General SUBJECT: INFORMATION: Audit Report: "Department of Energy's Fiscal Year 2015 Consolidated Financial Statements" Pursuant to requirements established by the Government Management Reform Act of 1994, the

  18. SPECIAL REPORT

    Energy Savers [EERE]

    The Department of Energy's Freedom of Information Act Process DOE/IG-0946 September 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 September 18, 2015 MEMORANDUM FOR THE DIRECTOR, OFFICE OF MANAGEMENT FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Special Report: "The Department of Energy's Freedom of Information Act Process" BACKGROUND The Freedom of Information Act (FOIA or the

  19. SPECIAL REPORT

    Energy Savers [EERE]

    Management Challenges at the Department of Energy - Fiscal Year 2016 OIG-SR-16-01 November 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 November 16, 2015 MEMORANDUM FOR THE SECRETARY FROM: Rickey R. Hass Acting Inspector General SUBJECT: INFORMATION: Special Report: "Management Challenges at the Department of Energy - Fiscal Year 2016" INTRODUCTION The Department of Energy is responsible for some

  20. CRD Report

    SciTech Connect (OSTI)

    Wang, Ucilia

    2007-12-18

    This report has the following articles: (1) Deconstructing Microbes--metagenomic research on bugs in termites relies on new data analysis tools; (2) Popular Science--a nanomaterial research paper in Nano Letters drew strong interest from the scientific community; (3) Direct Approach--researchers employ an algorithm to solve an energy-reduction issue essential in describing complex physical system; and (4) SciDAC Special--A science journal features research on petascale enabling technologies.

  1. Final Report

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

    Cyber Security for Utility Operations NETL Project M63SNL34 Sponsored by the U.S. DOE Office of Energy Assurance Managed by NETL Final Report Period of Performance October, 2003 - April, 2005 Dennis Holstein and John Tengdin, OPUS Publishing Jay Wack and Roger Butler, TecSec, Inc. Timothy Draelos, Sandia National Laboratories 1 Paul Blomgren, SafeNet/Mykotronx April 18, 2005 1 Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States

  2. Compressed air energy storage technology program. Annual report for 1979

    SciTech Connect (OSTI)

    Loscutoff, W.V.

    1980-06-01

    The objectives of the Compressed Air Energy Storage (CAES) program are to establish stability criteria for large underground reservoirs in salt domes, hard rock, and porous rock used for air storage in utility applications, and to develop second-generation CAES technologies that have minimal or no dependence on petroleum fuels. During the year reported reports have been issued on field studies on CAES on aquifers and in salt, stability, and design criteria for CAES and for pumped hydro-storage caverns, laboratory studies of CAES in porous rock reservoris have continued. Research has continued on combined CAES/Thermal Energy Storage, CAES/Solar systems, coal-fired fluidized bed combustors for CAES, and two-reservoir advanced CAES concepts. (LCL)

  3. Determining site-specific drum loading criteria for storing combustible {sup 238}Pu waste

    SciTech Connect (OSTI)

    Marshall, R.S.; Callis, E.L.; Cappis, J.H.; Espinoza, J.M.; Foltyn, E.M.; Reich, B.T.; Smith, M.C.

    1994-02-01

    Waste containing hydrogenous-combustible material contaminated with {sup 238}Pu can generate hydrogen gas at appreciable rates through alpha radiolysis. To ensure safe transportation of WIPP drums, the limit for {sup 238}Pu-combustible waste published in the WIPP TRUPACT-11 CONTENT (TRUCON) CODES is 21 milliwafts per 55 gallon drum. This corresponds to about 45 milligrams of {sup 238}PuO{sub 2} used for satellite heat source-electrical generators. The Los Alamos waste storage site adopted a {sup 238}Pu waste storage criteria based on these TRCUCON codes. However, reviews of the content in drums of combustible waste generated during heat source assembly at Los Alamos showed the amount of {sup 238}Pu is typically much greater than 45 milligrams. It is not feasible to appreciably reduce Los Alamos {sup 238}Pu waste drum loadings without significantly increasing waste volumes or introducing unsafe practices. To address this concern, a series of studies were implemented to evaluate the applicability of the TRUCON limits for storage of this specific waste. Addressed in these evaluations were determination of the hydrogen generation rate, hydrogen diffusion rates through confinement layers and vent filters, and packaging requirements specific to Los Alamos generated {sup 238}Pu contaminated combustible waste. These studies also showed that the multiple-layer packaging practices in use at Los Alamos could be relaxed without significantly increasing the risk of contamination. Based on a model developed to predict H{sub 2} concentrations in packages and drum headspace, the site specific effective hydrogen generation rate, and hydrogen-diffusion values, and revising the waste packaging practices, we were able to raise the safe loading limit for {sup 238}Pu waste drums for on site storage to the gram levels typical of currently generated {sup 238}Pu waste.

  4. SU-E-T-478: Sliding Window Multi-Criteria IMRT Optimization

    SciTech Connect (OSTI)

    Craft, D; Papp, D; Unkelbach, J; Bokrantz, R

    2014-06-01

    Purpose: To demonstrate a method for what-you-see-is-what-you-get multi-criteria Pareto surface navigation for step and shoot IMRT treatment planning. Methods: We show mathematically how multiple sliding window treatment plans can be averaged to yield a single plan whose dose distribution is the dosimetric average of the averaged plans. This is incorporated into the Pareto surface navigation based approach to treatment planning in such a way that as the user navigates the surface, the plans he/she is viewing are ready to be delivered (i.e. there is no extra ‘segment the plans’ step that often leads to unacceptable plan degradation in step and shoot Pareto surface navigation). We also describe how the technique can be applied to VMAT. Briefly, sliding window VMAT plans are created such that MLC leaves paint out fluence maps every 15 degrees or so. These fluence map leaf trajectories are averaged in the same way the static beam IMRT ones are. Results: We show mathematically that fluence maps are exactly averaged using our leaf sweep averaging algorithm. Leaf transmission and output factor corrections effects, which are ignored in this work, can lead to small errors in terms of the dose distributions not being exactly averaged even though the fluence maps are. However, our demonstrations show that the dose distributions are almost exactly averaged as well. We demonstrate the technique both for IMRT and VMAT. Conclusions: By turning to sliding window delivery, we show that the problem of losing plan fidelity during the conversion of an idealized fluence map plan into a deliverable plan is remedied. This will allow for multicriteria optimization that avoids the pitfall that the planning has to be redone after the conversion into MLC segments due to plan quality decline. David Craft partially funded by RaySearch Laboratories.

  5. Columbia County Habitat for Humanity Passive Townhomes (Technical Report) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Technical Report: Columbia County Habitat for Humanity Passive Townhomes Citation Details In-Document Search Title: Columbia County Habitat for Humanity Passive Townhomes Columbia County Habitat for Humanity (CCHH) (New York, Climate Zone 5A) built a pair of townhomes to Passive House Institute U.S. (PHIUS+ 2015) criteria to explore approaches for achieving Passive House performance (specifically with respect to exterior wall, space-conditioning, and ventilation strategies)

  6. Nuclear waste management. Quarterly progress report, January-March 1980

    SciTech Connect (OSTI)

    Platt, A.M.; Powell, J.A.

    1980-06-01

    Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

  7. Geotechnical analysis report, July 1992--June 1993

    SciTech Connect (OSTI)

    Not Available

    1993-12-31

    This report provides an assessment of the geotechnical status of the Waste Isolation Pilot Plant (WIPP). During the construction of the principal underground access and experimental areas, reporting was on a quarterly basis. Since 1987, reporting has been carried out annually because additional excavations will take place gradually over an extended period. This report presents and analyzes data collected up to June 30, 1993. The format of the Geotechnical Analysis Report was selected to meet the needs of several audiences. This report focuses on the geotechnical performance of the various underground facilities including the shafts, shaft stations, access drifts, test rooms, and waste storage areas. The results of excavation effects investigations, stratigraphic mapping, and other geologic studies are also included. The report provides an evaluation of the geotechnical aspects of performance in the context of the relevant design criteria and also describes the techniques used to acquire the data and the performance history of the instruments. The depth and breadth of the evaluation for the different underground facilities varies according to the types and quantities of data that are available, and the complexity of the recorded geotechnical responses.

  8. Progress Report on Alloy 617 Time Dependent Allowables

    SciTech Connect (OSTI)

    Wright, Julie Knibloe

    2015-06-01

    Time dependent allowable stresses are required in the ASME Boiler and Pressure Vessel Code for design of components in the temperature range where time dependent deformation (i.e., creep) is expected to become significant. There are time dependent allowable stresses in Section IID of the Code for use in the non-nuclear construction codes, however, there are additional criteria that must be considered in developing time dependent allowables for nuclear components. These criteria are specified in Section III NH. St is defined as the lesser of three quantities: 100% of the average stress required to obtain a total (elastic, plastic, primary and secondary creep) strain of 1%; 67% of the minimum stress to cause rupture; and 80% of the minimum stress to cause the initiation of tertiary creep. The values are reported for a range of temperatures and for time increments up to 100,000 hours. These values are determined from uniaxial creep tests, which involve the elevated temperature application of a constant load which is relatively small, resulting in deformation over a long time period prior to rupture. The stress which is the minimum resulting from these criteria is the time dependent allowable stress St. In this report data from a large number of creep and creep-rupture tests on Alloy 617 are analyzed using the ASME Section III NH criteria. Data which are used in the analysis are from the ongoing DOE sponsored high temperature materials program, form Korea Atomic Energy Institute through the Generation IV VHTR Materials Program and historical data from previous HTR research and vendor data generated in developing the alloy. It is found that the tertiary creep criterion determines St at highest temperatures, while the stress to cause 1% total strain controls at low temperatures. The ASME Section III Working Group on Allowable Stress Criteria has recommended that the uncertainties associated with determining the onset of tertiary creep and the lack of significant cavitation associated with early tertiary creep strain suggest that the tertiary creep criteria is not appropriate for this material. If the tertiary creep criterion is dropped from consideration, the stress to rupture criteria determines St at all but the lowest temperatures.

  9. ASSESSMENT REPORT

    Energy Savers [EERE]

    Alliance for Sustainable Energy LLC During Fiscal Years 2012 and 2013 Under Department of Energy Contract No. DE-AC36-08GO28308 OAI-V-16-06 March 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 March 11, 2016 MEMORANDUM FOR THE DIRECTOR, GOLDEN FIELD OFFICE FROM: Jack Rouch Deputy Assistant Inspector General for Audits Office of Inspector General SUBJECT: INFORMATION: Assessment Report on "Audit Coverage

  10. ASSESSMENT REPORT

    Energy Savers [EERE]

    Stanford University During Fiscal Years 2012 and 2013 Under Department of Energy Contract No. DE-AC02-76SF00515 OAS-V-15-04 September 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 September 21, 2015 MEMORANDUM FOR THE MANAGER, SLAC SITE OFFICE FROM: David Sedillo, Director Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Assessment Report: "Audit Coverage of Cost Allowability for

  11. ASSESSMENT REPORT

    Energy Savers [EERE]

    Brookhaven Science Associates LLC During Fiscal Years 2012 and 2013 Under Department of Energy Contract No. DE-AC02-98CH10886 OAI-V-16-03 January 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 January 19, 2016 MEMORANDUM FOR THE MANAGER, BROOKHAVEN SITE OFFICE FROM: Jack Rouch, Director Central Audits Division Office of Inspector General SUBJECT: INFORMATION: Assessment Report: "Audit Coverage of Cost

  12. TECHNICAL REPORT

    Office of Scientific and Technical Information (OSTI)

    TECHNICAL REPORT September 1 through November 30, 1994 Project Title: MANUFACTURE OF AMMONIUM SULFATE FERTILIZER FROM FGD-GYPSUM ICCI Project Number: Principal Investigator: Other Investigators: Project Manager; DOE Cooperative Agreement Number: DE-FC22-92PC9252 1 (Year 3) 94-1/3.1B-3M M.4.M. Chou, Illinois State Geological Survey (ISGS) M. Rostam-Abadi and J.M. Lytle, ISGS R. Hoeft, University of Illinois; EZ. Blevins, Allied Signal-Chemicals; F. Achron, Southeast Marketing Chemical Process

  13. ASSESSMENT REPORT

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

    ASSESSMENT REPORT Audit Coverage of Cost Allowability for National Security Technologies LLC During Fiscal Years 2012 Through 2014 Under Department of Energy Contract No. DE-AC52-06NA25946 OAI-V-16-07 April 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 April 12, 2016 MEMORANDUM FOR THE MANAGER, NEVADA FIELD OFFICE FROM: David Sedillo Deputy Assistant Inspector General for Audits and Inspections Office of

  14. ONTRACTOR REPORT

    Office of Scientific and Technical Information (OSTI)

    ONTRACTOR REPORT S A N D 8 2 -7 0 5 6 Unlimited Release Peer-Review Study of the Draft Handbook for Human-Reliability Analysis With Emphasis on Nuclear-Power- Plant Applications, NUREG/CR-1278 R. L. Brune, M. Weinstein, M. E. Fitzwater Human Performance Technologies, Inc. P.O. Box 3816 Thousand Oaks, CA 91359 Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 for the United States D epartment of Energy under Contract DE-AC04-76DR00789 Printed

  15. Trip Report

    Office of Legacy Management (LM)

    Site A/Plot M, Cook County, Illinois May 2013 Page 1 2013 Inspection and Annual Site Status Report for the Site A/Plot M, Cook County, Illinois Decontamination and Decommissioning Program Site Summary Site A/Plot M was inspected on April 10, 2013. The site, located within a county forest preserve with significant tree and grass cover, was in good condition. No cause for a follow-up inspection was identified. Erosion on top of the grass covered mound at Plot M continues to be a concern. Bike

  16. Final Report

    SciTech Connect (OSTI)

    R Paul Drake

    2004-01-12

    OAK-B135 This is the final report from the project Hydrodynamics by High-Energy-Density Plasma Flow and Hydrodynamics and Radiation Hydrodynamics with Astrophysical Applications. This project supported a group at the University of Michigan in the invention, design, performance, and analysis of experiments using high-energy-density research facilities. The experiments explored compressible nonlinear hydrodynamics, in particular at decelerating interfaces, and the radiation hydrodynamics of strong shock waves. It has application to supernovae, astrophysical jets, shock-cloud interactions, and radiative shock waves.

  17. DURING THIS REPORTING PERIOD, WE ISSUED 45 REPORTS; IDENTIFIED...

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

    ... in its performance criteria, could not store oil at ... fully cognizant of the Reserve's long-term sustainability. ... of steps to fully implement ISM into site work processes. ...

  18. Final Report

    SciTech Connect (OSTI)

    Webb, Robert C.; Kamon, Teruki; Toback, David; Safonov, Alexei; Dutta, Bhaskar; Dimitri, Nanopoulos; Pope, Christopher; White, James

    2013-11-18

    Overview The High Energy Physics Group at Texas A&M University is submitting this final report for our grant number DE-FG02-95ER40917. This grant has supported our wide range of research activities for over a decade. The reports contained here summarize the latest work done by our research team. Task A (Collider Physics Program): CMS & CDF Profs. T. Kamon, A. Safonov, and D. Toback co-lead the Texas A&M (TAMU) collider program focusing on CDF and CMS experiments. Task D: Particle Physics Theory Our particle physics theory task is the combined effort of Profs. B. Dutta, D. Nanopoulos, and C. Pope. Task E (Underground Physics): LUX & NEXT Profs. R. Webb and J. White(deceased) lead the Xenon-based underground research program consisting of two main thrusts: the first, participation in the LUX two-phase xenon dark matter search experiment and the second, detector R&D primarily aimed at developing future detectors for underground physics (e.g. NEXT and LZ).

  19. Performance profiles of major energy producers 1989

    SciTech Connect (OSTI)

    Not Available

    1991-01-23

    Performance Profiles of Major Energy Producers 1989 is the thirteenth annual report of the Energy Information Administration's (EIA) Financial Reporting System (FRS). The report examines financial and operating developments, with particular reference to the 23 major energy companies (the FRS companies'') required to report annually on Form EIA-28. Financial information is reported by major lines of business including oil and gas production, petroleum refining and marketing, and other energy operations. Domestic and international operations are examined separately in this report. It also traces key developments affecting the financial performance of major energy companies in 1989, as well as review of important trends.

  20. Natural Phenomena Hazards Design Criteria and Other Characterization Information for the MFFF at SRS

    SciTech Connect (OSTI)

    Wyatt, D.E.

    2000-12-01

    This report is a comprehensive complication applicable to the general Savannah River Site area, developed by both the original contractor, the DuPont Company, and by the current plant operator, Westinghouse Savannah River Company, over the full plant lifetime period (1950 - 2000).

  1. ECONOMIC REPORT OF THE PRESIDENT

    Energy Savers [EERE]

    service mark of the Federal National Mortgage Association, a U.S. Government-sponsored enter- prise. Fannie Mae buys mortgage loans that meet certain criteria from primary...

  2. Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities

    Office of Environmental Management (EM)

    Department of Energy 4, 2015 - September 18, 2015 Summary of Decisions - September 14, 2015 - September 18, 2015 September 18, 2015 - 2:37pm Addthis Personnel Security (10 CFR Part 710) On September 14, 2015, an Administrative Judge issued a decision in which he determined that an individual's access authorization should not be restored. In reaching this determination, the Administrative Judge found that the individual had not resolved security concerns under Criteria H regarding a diagnosis

  3. Final Report

    SciTech Connect (OSTI)

    Gurney, Kevin R

    2015-01-12

    This document constitutes the final report under DOE grant DE-FG-08ER64649. The organization of this document is as follows: first, I will review the original scope of the proposed research. Second, I will present the current draft of a paper nearing submission to Nature Climate Change on the initial results of this funded effort. Finally, I will present the last phase of the research under this grant which has supported a Ph.D. student. To that end, I will present the graduate student’s proposed research, a portion of which is completed and reflected in the paper nearing submission. This final work phase will be completed in the next 12 months. This final workphase will likely result in 1-2 additional publications and we consider the results (as exemplified by the current paper) high quality. The continuing results will acknowledge the funding provided by DOE grant DE-FG-08ER64649.

  4. Final Report

    SciTech Connect (OSTI)

    Yelton, John Martin; Mitselmakher, Guenakh; Korytov, Andrey; Avery, Paul; Furic, Ivan; Acosta, Darin; Konigsberg, Jacobo; Field, Richard; Matchev, Konstantin; Ramond, Pierre; Thorn, Richard; Sikivie, Pierre; Ray, Heather; Tanner, David

    2013-10-10

    We report on progress in a series of different directions within high energy physics research. 1. Neutrino research in hardware and software on the Minerva and MiniBooNE experiments 2. Experimental particle physics at the hadron colliders, with emphasis on research and development and data analysis on the CMS experiment operating at the CERN LHC. This includes research on the discovery and properties on the Higgs Boson. 3. Educational outreach through the Quarknet program, taking physics research into High School classrooms. 4. Theoretical and Phenomenological High Energy research, covering a broad range of activities ranging from fundamental theoretical issues to areas of immediate phenomenological importance. 5. Experiment searches for the Axion, as part of the ADMX experiment.

  5. NRC TLD Direct Radiation Monitoring Network progress report, October--December 1994. Volume 14, No. 4

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1995-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1994. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program.

  6. NRC TLD Direct Radiation Monitoring Network. Progress report, October--December 1996

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1997-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1996. It provides the ambient radiation levels measured in the vicinity of 74 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs.

  7. Washington Closure Hanford Report of Settlement Monitoring of the ERDF Landfill

    SciTech Connect (OSTI)

    J. T. Cameron

    2008-07-30

    This report summarizes the results of the ERDF Settlement Monitoring Program conducted between August 9, 2007, and April 29, 2008, on the 35-foot and 70-foot levels of the ERDF landfill. The purpose of this monitoring program was to verify that the materials already placed under the 35-foot and 70-foot levels satisfy the settlement criteria of the conceptual cap design.

  8. PROJECT W-551 INTERIM PRETREATMENT SYSTEM TECHNOLOGY SELECTION SUMMARY DECISION REPORT AND RECOMMENDATION

    SciTech Connect (OSTI)

    CONRAD EA

    2008-08-12

    This report provides the conclusions of the tank farm interim pretreatment technology decision process. It documents the methodology, data, and results of the selection of cross-flow filtration and ion exchange technologies for implementation in project W-551, Interim Pretreatment System. This selection resulted from the evaluation of specific scope criteria using quantitative and qualitative analyses, group workshops, and technical expert personnel.

  9. Cognos Reporting & Self Service

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

    Reporting & Self Service

  10. Sanitary landfill groundwater monitoring report. Third quarter 1995

    SciTech Connect (OSTI)

    1995-11-01

    This report contains analytical data for samples taken during third quarter 1995 from wells of the LFW series located at the Sanitary Landfill at the Savannah River Site (SRS). The data are submitted in reference to the Sanitary Landfill Operating Permit (DWP-087A). The report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final Primary Drinking Water Standards (PDWS) or screening levels, established by the U.S. Environmental Protection Agency, the South Carolina final Primary Drinking Water Standard for lead, or the SRS flagging criteria.

  11. Sanitary Landfill Groundwater Monitoring Report. Second Quarter 1995

    SciTech Connect (OSTI)

    Chase, J.A.

    1995-08-01

    This report contains analytical data for samples taken during second quarter 1995 from wells of the LFW series located at the Sanitary Landfill at the Savannah River Site (SRS). The data are submitted in reference to the Sanitary landfill Operating Permit (DWP-087A). The report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final Primary Water Standards (PDWS) or screening levels, established by the US Environmental Protection Agency (Appendix A), the South Carolina final Primary Drinking Water Standard for lead (Appendix A), or the SRS flagging criteria (Appendix B).

  12. PRECLOSURE CRITICALITY ANALYSIS PROCESS REPORT

    SciTech Connect (OSTI)

    A.E. Danise

    2004-10-25

    This report describes a process for performing preclosure criticality analyses for a repository at Yucca Mountain, Nevada. These analyses will be performed from the time of receipt of fissile material until permanent closure of the repository (preclosure period). The process describes how criticality safety analyses will be performed for various configurations of waste in or out of waste packages that could occur during preclosure as a result of normal operations or event sequences. The criticality safety analysis considers those event sequences resulting in unanticipated moderation, loss of neutron absorber, geometric changes, or administrative errors in waste form placement (loading) of the waste package. The report proposes a criticality analyses process for preclosure to allow a consistent transition from preclosure to postclosure, thereby possibly reducing potential cost increases and delays in licensing of Yucca Mountain. The proposed approach provides the advantage of using a parallel regulatory framework for evaluation of preclosure and postclosure performance and is consistent with the U.S. Nuclear Regulatory Commission's approach of supporting risk-informed, performance-based regulation for fuel cycle facilities, ''Yucca Mountain Review Plan, Final Report'', and 10 CFR Part 63. The criticality-related criteria for ensuring subcriticality are also described as well as which guidance documents will be utilized. Preclosure operations and facilities have significant similarities to existing facilities and operations currently regulated by the U.S. Nuclear Regulatory Commission; therefore, the design approach for preclosure criticality safety will be dictated by existing regulatory requirements while using a risk-informed approach with burnup credit for in-package operations.

  13. Final report

    SciTech Connect (OSTI)

    Joseph H. Simmons; Tracie J. Bukowski

    2002-08-07

    This grant was a continuation of research conducted at the University of Florida under Grant No. DE-FG05-91ER45462 in which we investigated the energy bandgap shifts produced in semiconductor quantum dots of sizes between 1.5 and 40 nm. The investigated semiconductors consisted of a series of Column 2-6 compounds (CdS, CdSe, CdTe) and pure Column IV elements (Si and Ge). It is well-known of course that the 2-6 semiconductors possess a direct-gap electronic structure, while the Column IV elements possess an indirect-gap structure. The investigation showed a major difference in quantum confinement behavior between the two sets of semiconductors. This difference is essentially associated with the change in bandgap energy resulting from size confinement. In the direct-gap semiconductors, the change in energy (blue shift) saturates when the crystals approach 2-3 nm in diameter. This limits the observed shift in energy to less than 1 eV above the bulk value. In the indirect-gap semiconductors, the energy shift does not show any sign of saturation and in fact, we produced Si and Ge nanocrystals with absorption edges in the UV. The reason for this difference has not been determined and will require additional experimental and theoretical studies. In our work, we suggest, but do not prove that mixing of conduction band side valleys with the central valley under conditions of size confinement may be responsible for the saturation in the blue-shift of direct-gap semiconductors. The discovery of large bandgap energy shifts with crystal size prompted us to suggest that these materials may be used to form photovoltaic cells with multi-gap layers for high efficiency in a U.S. Patent issued in 1998. However, this possibility depends strongly on the ability to collect photoexcited carriers from energy-confined crystals. The research conducted at the University of Arizona under the subject grant had a major goal of testing an indirect gap semiconductor in size-confined structures to determine if photocarriers could be collected. Thus, we tested a variety of semiconductor-glass nano-composite structures for photoconductivity. Tests were conducted in collaboration with the Laser Physics Division at Sandia National Laboratories. Nano-composite samples were formed consisting of Ge nanocrystals embedded in an indium-tin-oxide matrix. Photoconductivity measurements were conducted with exposure of the films to sub-bandgap and super-bandgap light. The results showed a clear photoconductivity effect arising from exposure to super-bandgap light only. These results suggest that the high-efficiency photovoltaic cell structure proposed in DOE sponsored U.S. Patent 5,720,827 is viable. The results of fabrication studies, structural characterization studies and photovoltaic measurements are presented in the report. This report is taken from a PhD dissertation of Tracie J. Bukowski submitted to the University of Florida in May 2002. ''The optical and photoconductive response in germanium quantum dots and indium tin oxide composite thin film structures,'' Dr. Bukowski conducted her PhD study under this grant at the University of Arizona and under Grant No DE-FG05-91ER45462 at the University of Florida, as well as during a two-year fellowship at Sandia National Laboratories.

  14. NEXT GENERATION MELTER OPTIONEERING STUDY - INTERIM REPORT

    SciTech Connect (OSTI)

    GRAY MF; CALMUS RB; RAMSEY G; LOMAX J; ALLEN H

    2010-10-19

    The next generation melter (NOM) development program includes a down selection process to aid in determining the recommended vitrification technology to implement into the WTP at the first melter change-out which is scheduled for 2025. This optioneering study presents a structured value engineering process to establish and assess evaluation criteria that will be incorporated into the down selection process. This process establishes an evaluation framework that will be used progressively throughout the NGM program, and as such this interim report will be updated on a regular basis. The workshop objectives were achieved. In particular: (1) Consensus was reached with stakeholders and technology providers represented at the workshop regarding the need for a decision making process and the application of the D{sub 2}0 process to NGM option evaluation. (2) A framework was established for applying the decision making process to technology development and evaluation between 2010 and 2013. (3) The criteria for the initial evaluation in 2011 were refined and agreed with stakeholders and technology providers. (4) The technology providers have the guidance required to produce data/information to support the next phase of the evaluation process. In some cases it may be necessary to reflect the data/information requirements and overall approach to the evaluation of technology options against specific criteria within updated Statements of Work for 2010-2011. Access to the WTP engineering data has been identified as being very important for option development and evaluation due to the interface issues for the NGM and surrounding plant. WRPS efforts are ongoing to establish precisely data that is required and how to resolve this Issue. It is intended to apply a similarly structured decision making process to the development and evaluation of LAW NGM options.

  15. Waste Isolation Pilot Plant Safety Analysis Report

    SciTech Connect (OSTI)

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  16. Canister storage building (CSB) safety analysis report phase 3: Safety analysis documentation supporting CSB construction

    SciTech Connect (OSTI)

    Garvin, L.J.

    1997-04-28

    The Canister Storage Building (CSB) will be constructed in the 200 East Area of the U.S. Department of Energy (DOE) Hanford Site. The CSB will be used to stage and store spent nuclear fuel (SNF) removed from the Hanford Site K Basins. The objective of this chapter is to describe the characteristics of the site on which the CSB will be located. This description will support the hazard analysis and accident analyses in Chapter 3.0. The purpose of this report is to provide an evaluation of the CSB design criteria, the design's compliance with the applicable criteria, and the basis for authorization to proceed with construction of the CSB.

  17. Report to Congress on abnormal occurrences: (Quarterly report), January-March 1987

    SciTech Connect (OSTI)

    Not Available

    1987-10-01

    The Energy Reorganization Act of 1974 identifies an abnormal occurrence as an unscheduled incident or event which the Nuclear Regulatory Commission determines to be significant from the standpoint of public health or safety and requires a quarterly report of such events to be made to Congress. This report covers the period from January 1 to March 31, 1987. The report states that for this reporting period, there was one abnormal occurrence at the nuclear power plants licensed to operate. The item involved the NRC suspension of power operations of the Peach Bottom Facility due to inattentiveness of the control room staff. There were seven abnormal occurrences at the other NRC licensees. Four involved diagnostic medical misadministrations; the other three involved breakdowns in management controls at three separate industrial radiography licensees. There were two abnormal occurrences reported by the Agreement States. Both involved breakdowns in management controls at industrial radiography licensees. The report also contains information updating some previously reported abnormal occurrences. Appendix A contains the criteria used to define an abnormal occurrence. 13 refs.

  18. Savannah River Site environmental report for 1993

    SciTech Connect (OSTI)

    Arnett, M.W.; Karapatakis, L.K.; Mamatey, A.R.

    1994-08-01

    Savannah River Site (SRS) conducts effluent monitoring and environmental surveillance to ensure the safety of the public and the well-being of the environment. DOE Order 5400,1, ``General Environmental Protection Program,`` requires the submission of an environmental report that documents the impact of facility operations on the environment and on public health. SRS has had an extensive environmental surveillance program in place since 1951 (before site startup). At that time, data generated by the on-site surveillance program were reported in site documents. Beginning in 1959, data from off-site environmental monitoring activities were presented in reports issued for public dissemination. Separate reporting of SRS`s on- and off-site environmental monitoring activities continued until 1985, when data from both surveillance programs were merged into a single public document. The Savannah River Site Environmental Report for 1993 is an overview of effluent monitoring and environmental surveillance activities conducted on and in the vicinity of SRS from January 1 through December 31, 1993. For complete program descriptions, consult the ``SRS Environmental Monitoring Plan`` (WSRC-3Ql-2-1000). It documents the rationale and design criteria for the monitoring program, the frequency of monitoring and analysis, the specific analytical and sampling procedures, and the quality assurance requirements.

  19. Technical Qualification Program Self-Assessment Report- Oak Ridge Office- 2014

    Broader source: Energy.gov [DOE]

    This assessment, using criteria referred to in DOE O 426.1, Federal Technical Capability, is designed to evaluate the effectiveness of the implementation of the FTCP and the TQP at ORO. The purpose of this report is to document the results of ORO's self-assessment. The remaining sections of this report include the assessment scope and methodology, the results of the assessment, and supporting information.

  20. Final Report

    SciTech Connect (OSTI)

    Michael C. Weinberg; Lori L. Burgner; Joseph H. Simmons

    2003-05-23

    OAK B135 The formation of metastable crystalline phases in lithium disilicate glass has been a subject of controversy for decades. Here, one aspect of this problem relating to the stability of these non-equilibrium phases when glasses are heated for extended time periods in the nucleation regime is addressed. The results of a systematic experimental investigation on the persistence of metastable phases and the factors that may influence the appearance of such phases, e.g., water content, impurities, glass composition, and glass preparation procedure are presented. Growth rates of lithium disilicate crystals in lithium disilicate glass are measured as a function water concentration in the glass and of temperature in the deeply undercooled regime. The growth rate data obtained in this work are combined with data reported in the literature and used to assess the applicability of standard models of crystal growth for the description of experimental results over a very broad temperature range. The reduced growth rate versus undercooling graph is found to consist of three regimes. For undercoolings less than 140C, the reduced growth rate curve is suggestive of either 2-D surface nucleation or screw dislocation growth. For undercoolings greater than 400C, the reduced growth rate plot suggests the operative crystal growth mechanism is 2-D surface nucleation, but detailed calculations cast doubt upon this conclusion. In the intermediate undercooling range, there appears to be some sort of transitional behavior for which none of the standard models appear to be applicable. Further, it is observed that small differences in the viscosity data employed can produce enormous differences in the predicted growth rates at larger undercoolings. Results of the kinetic analyses conducted herein seem to indicate that the nature of the kinetic rate coefficient used in the standard growth models may be incorrect. Nucleation rates of sodium metasilicate crystals in a sodium silicate glass of composition 43Na2O-57SiO2 (mol%) are investigated using the development technique. The results of this study are compared with the nucleation rate results recently obtained for this composition using a novel DTA method. The two techniques are found to agree within experimental error.

  1. WIPP AIB Report

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

    WIPP AIB Report WIPP Accident Investigation Board Report Department of Energy (DOE) Issues Accident Investigation Board (AIB) Report on February 14 Incident at the Waste Isolation ...

  2. Annual Coal Distribution Report

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

    Annual Coal Distribution Report Release Date: April 16, 2015 | Next Release Date: March 2016 | full report | RevisionCorrection Revision to the Annual Coal Distribution Report ...

  3. Essential Systems Functionality Inspection Criteria, Approach, and Lines of Inquiry, October 16, 2008 (HSS CRAD 64-11 Rev. 2)

    Broader source: Energy.gov [DOE]

    The Essential Systems Functionality (ESF) inspection will evaluate the effectiveness of programs and processes for engineering design and safety basis, construction and installation, configuration management, surveillance testing, maintenance, operations, cognizant system engineer (CSE) and safety system oversight (SSO), and feedback and improvement of selected safety systems. This review will evaluate the effectiveness in maintaining the functionality of these safety systems. The ESF review will be performed in the context of integrated safety management (ISM), although the inspection criteria, activities and lines of inquiry are organized by ESF functional areas rather than ISM principles and core functions.

  4. AFIP-6 Breach Assessment Report

    SciTech Connect (OSTI)

    Dan Wachs; Adam Robinson; Pavel Medvedev

    2011-02-01

    Analysis of the AFIP-6 experiment is summarized in this report in order to determine the cause of gaseous fission product release observed during irradiation. During the irradiation, a series of small fission product releases were observed. In order to limit the potential for primary coolant contamination, the operating cycle was terminated and the AFIP-6 experiment was removed for examination. Both in-canal and post-irradiation examination revealed the presence of an unusually thick oxide layer and discrete surface blisters on the fuel plates. These blisters were the likely cause of fission product release. Subsequent detailed thermal hydraulic analysis of the experiment indicated that the combination of the high operating power and test vehicle configuration led to high nominal operating temperatures for the fuel plates. This elevated temperature led to accelerated surface corrosion and eventually spallation of the fuel plate cladding. The thermal insulating nature of this corrosion layer led to significantly elevated fuel meat temperatures that induced blistering. Analysis was performed to validate a corrosion rate model and criteria for onset of spallation type surface corrosion were determined. The corrosion rate model will be used to estimate the oxide thickness anticipated for experiments in the future. The margin to the spallation threshold will then be used to project the experiment performance.

  5. Electricity market players subgroup report

    SciTech Connect (OSTI)

    Borison, A.

    1990-03-01

    The purpose of this study is to examine competition in the electric power industry from an ``industrial organization`` point of view. The remainder of this report is organized as follows. Chapter 2 describes the ``industrial organization`` approach used to analyze the electric power market. Industrial organization emphasizes specific market performance criteria, and the impact of market structure and behavior on performance. Chapter 3 identifies the participants in the electric power market, grouped primarily into regulated producers, unregulated producers, and consumers. Chapter 4 describes the varieties of electric power competition, organized along two dimensions: producer competition and consumer competition. Chapters 5 and 6 identify the issues raised by competition along the two dimensions. These issues include efficiency, equity, quality, and stability. Chapters 7 through 9 describe market structure, behavior and performance in three competitive scenarios: minimum competition, maximum competition, and moderate competition. Market structure, behavior and performance are discussed, and the issues raised in Chapters 5 and 6 are discussed in detail. Chapter 10 provides conclusions about ``winners and losers`` and identifies issues that require further study.

  6. Electricity market players subgroup report

    SciTech Connect (OSTI)

    Borison, A.

    1990-03-01

    The purpose of this study is to examine competition in the electric power industry from an industrial organization'' point of view. The remainder of this report is organized as follows. Chapter 2 describes the industrial organization'' approach used to analyze the electric power market. Industrial organization emphasizes specific market performance criteria, and the impact of market structure and behavior on performance. Chapter 3 identifies the participants in the electric power market, grouped primarily into regulated producers, unregulated producers, and consumers. Chapter 4 describes the varieties of electric power competition, organized along two dimensions: producer competition and consumer competition. Chapters 5 and 6 identify the issues raised by competition along the two dimensions. These issues include efficiency, equity, quality, and stability. Chapters 7 through 9 describe market structure, behavior and performance in three competitive scenarios: minimum competition, maximum competition, and moderate competition. Market structure, behavior and performance are discussed, and the issues raised in Chapters 5 and 6 are discussed in detail. Chapter 10 provides conclusions about winners and losers'' and identifies issues that require further study.

  7. Status Update on Action 2c: Criteria Review and Approach Document (CRAD) for Performing Assessments of Activity-level Work Planning and Control

    Broader source: Energy.gov [DOE]

    Slide Presentation by Bradley K. Davy, Director, Office of Worker Safety and Health Assistance, HS. Criteria Review and Approach Document (CRAD) for Performing Assessments of Activity- Level Work Planning and Control. DOE CRAD Development Approach.

  8. Building Energy Simulation Test for Existing Homes (BESTEST-EX): Instructions for Implementing the Test Procedure, Calibration Test Reference Results, and Example Acceptance-Range Criteria

    SciTech Connect (OSTI)

    Judkoff, R.; Polly, B.; Bianchi, M.; Neymark, J.; Kennedy, M.

    2011-08-01

    This publication summarizes building energy simulation test for existing homes (BESTEST-EX): instructions for implementing the test procedure, calibration tests reference results, and example acceptance-range criteria.

  9. Well-to-Wheels Analysis of Advanced Fuel/Vehicle Systems - A North American Study of Energy Use, Greenhouse Gas Emissions, and Criteria Pollutant Emissions

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

    Well-to-Wheels Analysis of Advanced Fuel/Vehicle Systems - A North American Study of Energy Use, Greenhouse Gas Emissions, and Criteria Pollutant Emissions May 2005 Well-to-Wheels Analysis of Advanced Fuel/Vehicle Systems - A North American Study of Energy Use, Greenhouse Gas Emissions, and Criteria Pollutant Emissions Norman Brinkman, General Motors Corporation Michael Wang, Argonne National Laboratory Trudy Weber, General Motors Corporation Thomas Darlington, Air Improvement Resource, Inc. May

  10. Weekly Petroleum Status Report

    Gasoline and Diesel Fuel Update (EIA)

    Please go to the redesigned Weekly Petroleum Status Report.

  11. 105 K East isolation barrier acceptance analysis report

    SciTech Connect (OSTI)

    McCracken, K.J.; Irwin, J.J.

    1995-05-31

    The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KE/100K. The tests were performed in accordance with the test plan (McCracken 1995c) and acceptance test procedure (McCracken 1995a). The test report (McCracken 1995b) contains the test data. This document compares the test data (McCracken 1995b) against the criteria (McCracken 1995a, c). A discussion of the leak rate analytical characterization (Irwin 1995) describes how the flow characteristics and the flow rate will be determined using the test data from the test report (McCracken 1995b). The barriers must adequately control the leakage from the main basin to the discharge chute to less than the 1,500 gph (5,680 lph) Safety Analysis Report (SAR 1994) limit.

  12. Papers and Reports

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

    Papers, Reports Papers and Reports Bringing together top space science students with internationally recognized researchers at Los Alamos in an educational and collaborative atmosphere. Contacts Director Misa Cowee Email Administrative Assistant Mary Wubbena Email Request more information Email Annual research reports Report 2015 (pdf - 9.35 MB) Report 2014 (pdf - 12.16 MB) Report 2013 (pdf - 29.06 MB) Report 2012 (pdf - 25.42 MB) Report 2011 (pdf - 10.46 MB) Papers, posters, presentations

  13. Module 8- Reporting

    Broader source: Energy.gov [DOE]

    This module illustrates and defines the different cost performance reports (CPR) available for reporting earned value information.

  14. ARM - Annual Reports

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

    MaterialsAnnual Reports Publications Journal Articles Conference Documents Program Documents Technical Reports Publications Database Public Information Materials Image Library...

  15. Comparison of Stack Measurement Data from R&D Facilities to Regulatory Criteria. A Case Study from PNNL

    SciTech Connect (OSTI)

    Ballinger, Marcel Y.; Duchsherer, Cheryl J.; Woodruff, Rodger K.; Larson, Timothy V.

    2013-10-30

    Chemical emissions from research and development (R&D) activities are difficult to estimate because of the large number of chemicals used and the potential for continual changes in processes. In this case study, stack measurements taken from R&D facilities at Pacific Northwest National Laboratory (PNNL) were examined, including extreme worst-case emissions estimates and alternate analyses using a Monte Carlo method that takes into account the full distribution of sampling results. The results from these analyses were then compared to emissions estimated from chemical inventories. Results showed that downwind ambient air concentrations calculated from the stack measurement data were below acceptable source impact levels (ASILs) for almost all compounds, even under extreme worst-case analyses. However, for compounds with averaging periods of a year, the unrealistic but simplifying extreme worst-case analysis often resulted in exceedances of lower level regulatory criteria used to determine modeling requirements or to define trivial releases. Compounds with 24-hour averaging periods were nearly all several orders of magnitude below all, including the trivial release, criteria. The alternate analysis supplied a more realistic basis of comparison and an ability to explore effects under different operational modes.

  16. Evaluation of the Validity of 3 Criteria for Sampling and Analyzing DST Wastes in Support of Waste Feed Delivery

    SciTech Connect (OSTI)

    BOGER, R.M.

    2000-10-16

    This document summarizes the analysis of 3 basic criteria for the sampling systems that will provide waste validation samples of tank waste feeds prior to delivery to the waste treatment and immobilization plant where the wastes will be converted to glass forms. The assessed criteria includes sampling through a 4-inch riser, sampling while a mixer pump is operating, and the deployment of an at-tank analysis system. The assessment, based on the Phase I, 3S6 waste feed scenario, indicated that for high level waste, sampling through a 4-inch riser is not required but sampling while mixer pumps are operating will be required. For low activity waste, sampling through a 4-inch riser will be required but sampling while mixer pumps are operating is not required. The assessment indicated that an at-tank analysis system to provide tank mixing/settling (homogeneity) status is not needed since the number of tanks providing LAW feed was expanded and the payment basis in the original privatization contract has been modified.

  17. Cost and schedule control systems criteria for contract performance measurement: work breakdown structure guide

    SciTech Connect (OSTI)

    Not Available

    1981-10-01

    This document provides guidance on development and use of the Work Breakdown Structure (WBS) technique. It describes the types of work breakdown structures, their preparation, and their effective use for organizing, planning, and controlling projects and contracts managed by the Department of Energy (DOE). The WBS technique is the preferred management tool for identifying and defining work. It provides an ordered framework for planning and controlling the work efforts to be performed in achieving technical objectives and for summarizing data, and the quantitative and narrative reports used for monitoring cost, schedule and technical performance. A WBS is developed for first identifying the major end items or systems to be produced, followed by their successive subdivision into increasingly detailed and manageable subsidiary products. Most of these subsidiary products are the direct result of work, while others are simply the aggregation of selected products into a logical set for management control purposes. In either case, detailed tasks are eventually identified for each product on the WBS at the level where work will be performed. As a minimum, these detailed tasks or work packages identify the product, describe the effort to be performed, identify the resources to be applied, specify the budget and schedule constraints, and the technical requirements, and identify the organizational element responsible for work accomplishment.

  18. 2012 Hanford Climate Survey Report - ATL Report

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

    ATL Report Prepared by EurekaFacts LLC 1 Table of Contents Introduction.................................................................................................................................................... 2 Safety Culture and Climate Focus Areas and Factors .................................................................................. 3 Interpreting the Survey Results Presented in this Report ............................................................................. 4 Key

  19. 2012 Hanford Climate Survey Report - CHPRC Report

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

    CHPRC Report Prepared by EurekaFacts LLC 1 Table of Contents Introduction.................................................................................................................................................... 2 Safety Culture and Climate Focus Areas and Factors .................................................................................. 3 Interpreting the Survey Results Presented in this Report ............................................................................. 4 Key

  20. 2012 Hanford Climate Survey Report - MSA Report

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

    MSA Report Prepared by EurekaFacts LLC 1 Table of Contents Introduction.................................................................................................................................................... 2 Safety Culture and Climate Focus Areas and Factors .................................................................................. 3 Interpreting the Survey Results Presented in this Report ............................................................................. 4 Key

  1. 2012 Hanford Climate Survey Report - WCH Report

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

    WCH Report Prepared by EurekaFacts LLC 1 Table of Contents Introduction.................................................................................................................................................... 2 Safety Culture and Climate Focus Areas and Factors .................................................................................. 3 Interpreting the Survey Results Presented in this Report ............................................................................. 4 Key

  2. 2012 Hanford Climate Survey Report - WRPS Report

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

    WRPS Report Prepared by EurekaFacts LLC 1 Table of Contents Introduction.................................................................................................................................................... 2 Safety Culture and Climate Focus Areas and Factors .................................................................................. 3 Interpreting the Survey Results Presented in this Report ............................................................................. 4 Key

  3. Reporting | Department of Energy

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

    Reporting Reporting Electric Disturbance Events Incident Reporting - OE417 The Electric Emergency Incident and Disturbance Report (Form OE-417) collects information on electric incidents and emergencies. Emergency Situation Reports Reports on energy related activities resulting from natural and man-made disasters. Energy Assurance Daily Energy Assurance Daily provides a summary of public information concerning current energy issues. Transmission Project Reporting - FPA 216h Information on 216(h)

  4. Environmental impact of APC residues from municipal solid waste incineration: Reuse assessment based on soil and surface water protection criteria

    SciTech Connect (OSTI)

    Quina, Margarida J.; Bordado, Joao C.M.; Quinta-Ferreira, Rosa M.

    2011-09-15

    Highlights: > The Dutch Building Material Decree (BMD) was used to APC residues from MSWI. > BMD is a straightforward tool to calculate expectable loads to the environment of common pollutants. > Chloride load to the environment lead to classification of building material not allowed. > At least a pre-treatment (e.g. washing) is required in order to remove soluble salts. > The stabilization with phosphates or silicates eliminate the problem of heavy metals. - Abstract: Waste management and environmental protection are mandatory requirements of modern society. In our study, air pollution control (APC) residues from municipal solid waste incinerators (MSWI) were considered as a mixture of fly ash and fine particulate solids collected in scrubbers and fabric filters. These are hazardous wastes and require treatment before landfill. Although there are a number of treatment options, it is highly recommended to find practical applications rather than just dump them in landfill sites. In general, for using a construction material, beyond technical specifications also soil and surface water criteria may be used to ensure environmental protection. The Dutch Building Materials Decree (BMD) is a valuable tool in this respect and it was used to investigate which properties do not meet the threshold criteria so that APC residues can be further used as secondary building material. To this end, some scenarios were evaluated by considering release of inorganic species from unmoulded and moulded applications. The main conclusion is that the high amount of soluble salts makes the APC residues a building material prohibited in any of the conditions tested. In case of moulding materials, the limits of heavy metals are complied, and their use in Category 1 would be allowed. However, also in this case, the soluble salts lead to the classification of 'building material not allowed'. The treatments with phosphates or silicates are able to solve the problem of heavy metals, but difficulties with the soluble salts are still observed. This analysis suggests that for APC residues to comply with soil and surface water protection criteria to be further used as building material at least a pre-treating for removing soluble salts is absolutely required.

  5. Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums

    SciTech Connect (OSTI)

    Lunsford, G.F.

    1999-06-14

    This report is fully responsive to the requirements of Section 4.0 Acceptable Knowledge from the WIPP Transuranic Waste Characterization Quality Assurance Plan, CAO-94-1010, and provides a sound, (and auditable) characterization that satisfies the WIPP criteria for Acceptable Knowledge.

  6. NRC TLD Direct Radiation Monitoring Network. Volume 15, No. 4: Quarterly progress report, October--December 1995

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1996-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1995. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program.

  7. Remarks on the regularity criteria of three-dimensional magnetohydrodynamics system in terms of two velocity field components

    SciTech Connect (OSTI)

    Yamazaki, Kazuo

    2014-03-15

    We study the three-dimensional magnetohydrodynamics system and obtain its regularity criteria in terms of only two velocity vector field components eliminating the condition on the third component completely. The proof consists of a new decomposition of the four nonlinear terms of the system and estimating a component of the magnetic vector field in terms of the same component of the velocity vector field. This result may be seen as a component reduction result of many previous works [C. He and Z. Xin, “On the regularity of weak solutions to the magnetohydrodynamic equations,” J. Differ. Equ. 213(2), 234–254 (2005); Y. Zhou, “Remarks on regularities for the 3D MHD equations,” Discrete Contin. Dyn. Syst. 12(5), 881–886 (2005)].

  8. HOW TO DEAL WITH WASTE ACCEPTANCE UNCERTAINTY USING THE WASTE ACCEPTANCE CRITERIA FORECASTING AND ANALYSIS CAPABILITY SYSTEM (WACFACS)

    SciTech Connect (OSTI)

    Redus, K. S.; Hampshire, G. J.; Patterson, J. E.; Perkins, A. B.

    2002-02-25

    The Waste Acceptance Criteria Forecasting and Analysis Capability System (WACFACS) is used to plan for, evaluate, and control the supply of approximately 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous wastes from over 60 environmental restoration projects between FY02 through FY10 to the Oak Ridge Environmental Management Waste Management Facility (EMWMF). WACFACS is a validated decision support tool that propagates uncertainties inherent in site-related contaminant characterization data, disposition volumes during EMWMF operations, and project schedules to quantitatively determine the confidence that risk-based performance standards are met. Trade-offs in schedule, volumes of waste lots, and allowable concentrations of contaminants are performed to optimize project waste disposition, regulatory compliance, and disposal cell management.

  9. Feasibility Assessment of the Water Energy Resources of the United States for New Low Power and Small Hydro Classes of Hydroelectric Plants: Main Report and Appendix A

    Broader source: Energy.gov [DOE]

    Main Report and Appendix A: Evaluates water energy resource sites identified in the resource assessment study reported in Water Energy Resources of the United States with Emphasis on Low Head/Low Power Resources, DOE/ID-11111, April 2004 to identify which could feasibly be developed using a set of feasibility criteria. The gross power potential of the sites estimated in the previous study was refined to determine the realistic hydropower potential of the sites using a set of development criteria assuming they are developed as low power (less than 1 MWa) or small hydro (between 1 and 30 MWa) projects.

  10. Monthly Report 2015

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

    Report 2015 Monthly Report for the Reporting Period ending November 30, 2015, as required by NMED Administrative Orders dated February 27, 2014 and May 12, 2014, as Amended by NMED ...

  11. Report: RFP0001

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

    1 of 5 Report: RFP0001 Fiscal Year: 2010 Fiscal Month: 05 Financial Plan Number: 5 Rpt ... RL14383 - AdvanceMed Hanford Financial Plan Report - Detail Report Generated on: February ...

  12. DOE Hydropower Program Annual Report for FY 2003

    SciTech Connect (OSTI)

    ?ada, Glenn F.; Carlson, Thomas J.; Dauble, Dennis D.; Hunt, Richard T.; Sale, Michael J.; Sommers, Garold L.

    2004-02-01

    This report describes the progress of the R&D conducted in FY 2003 the under four program areas at the time: (1) Advanced Hydropower Technology (Large Turbine Field Testing, Testing of the Alden/NREC pilot scale runner, and Improved Mitigation Practices); (2) Supporting Research and Testing (Biological Design Criteria, Computer and Physical Modeling, Instrumentation and Controls, and Environmental Analysis); (3) Systems Integration and Technology Acceptance (Wind/Hydro Integration Studies and Technical Support and Outreach); and (4) Engineering and Analysis (Innovative Technology Characterization).

  13. Geotechnical Seismic Assessment Report for Defense Waste Processing Facility

    SciTech Connect (OSTI)

    McHood, M.

    2000-10-04

    High level waste facilities at the Savannah River Site include several major structures that must meet seismic requirements, including the Defense Waste Processing Facility. Numerous geotechnical and geological investigations have been performed to characterize the in-situ static and dynamic properties of the soil sediments. These investigations have led to conclusions concerning the stability of foundation soils in terms of liquefaction potential and structure settlement. This report reviews past work that addresses seismic soil stability and presents the results of more recent analyses incorporating updated seismic criteria.

  14. Basic Energy Sciences Reports

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

    Basic Energy Sciences Reports Basic Energy Sciences Reports The list below of Basic Energy Sciences workshop reports addresses the status of some important research areas that can help identify research directions for a decades-to-century energy strategy. Basic Energy Sciences (BES) Workshop Reports The Energy Challenges Report: New Science for a Secure and Sustainable Energy Future This Basic Energy Sciences Advisory Committee (BESAC) report summarizes a 2008 study by the Subcommittee on Facing

  15. Annual Reports - Hanford Site

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

    Annual Reports Soil & Groundwater Home Annual Reports Environmental Data Access Administrative Record Annual Reports Email Email Page | Print Print Page |Text Increase Font Size Decrease Font Size NEW The Groundwater Remediation Project issues an annual report describing its accomplishments and plans. The projects associated with the Groundwater Remediation Project also issue periodic status reports. Those reports can be found in this section. Title Issue Date Rev. Document Information 2014

  16. Economic assessment of advanced flue gas desulfurization processes. Final report

    SciTech Connect (OSTI)

    Bierman, G. R.; May, E. H.; Mirabelli, R. E.; Pow, C. N.; Scardino, C.; Wan, E. I.

    1981-09-01

    This report presents the results of a project sponsored by the Morgantown Energy Technology Center (METC). The purpose of the study was to perform an economic and market assessment of advanced flue gas desulfurization (FGD) processes for application to coal-fired electric utility plants. The time period considered in the study is 1981 through 1990, and costs are reported in 1980 dollars. The task was divided into the following four subtasks: (1) determine the factors affecting FGD cost evaluations; (2) select FGD processes to be cost-analyzed; (3) define the future electric utility FGD system market; and (4) perform cost analyses for the selected FGD processes. The study was initiated in September 1979, and separate reports were prepared for the first two subtasks. The results of the latter two subtasks appear only in this final reprot, since the end-date of those subtasks coincided with the end-date of the overall task. The Subtask 1 report, Criteria and Methods for Performing FGD Cost Evaluations, was completed in October 1980. A slightly modified and condensed version of that report appears as appendix B to this report. The Subtask 2 report, FGD Candidate Process Selection, was completed in January 1981, and the principal outputs of that subtask appear in Appendices C and D to this report.

  17. NERSC Annual Reports

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

    Annual Reports NERSC Annual Reports Sort by: Default | Name 2014cover.jpg NERSC Annual Report 2014 Download Image: 2014cover.jpg | jpg | 202 KB Download File: 2014NERSCAnnualReport.pdf | pdf | 6.1 MB 2013-Annual-Report-cover.png NERSC Annual Report 2013 Download Image: 2013-Annual-Report-cover.png | png | 645 KB Download File: annrep2013.pdf | pdf | 6.7 MB 2012-Cover.png NERSC Annual Report 2012 Download Image: 2012-Cover.png | png | 420 KB Download File: annrep12.pdf | pdf | 38 MB

  18. Federal Financial Report

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

    REPORT (Follow form instructions) 1. Federal Agency and Organizational Element 2. Federal Grant or Other Identifying Number Assigned by Federal Agency Page of to Which Report is ...

  19. PGI Bug Reports

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

    PGI PGI Bug Reports PGI Bug Reports Internal compiler error for function pointer with identically named arguments June 9, 2015 by Scott French, NERSC USG Status: Bug 21435...

  20. Capital Reporting Company Quadrennial ...

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

    TAKER NATALIE KEMPKEY-NOTE TAKER Capital Reporting Company Quadrennial Energy ... MANAGER-DEVELOPMENT, ACCESS MIDSTREAM Capital Reporting Company Quadrennial Energy ...

  1. Capital Reporting Company Quadrennial ...

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

    CA 94102 REPORTED BY: FREDDIE REPPOND Capital Reporting Company Quadrennial Energy ... Director, Center for Water-Energy 25 Efficiency, University of California at Davis Capital ...

  2. Quarterly Progress Reports

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

    Quarterly Progress Reports Quarterly Progress Reports Investigating the field of high energy physics through experiments that strengthen our fundamental understanding of matter,...

  3. Uranium Purchases Report

    Reports and Publications (EIA)

    1996-01-01

    Final issue. This report details natural and enriched uranium purchases as reported by owners and operators of commercial nuclear power plants. 1996 represents the most recent publication year.

  4. Papers and Reports

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

    Papers, Reports Papers and Reports Bringing together top space science students with ... or papers related to your Los Alamos Space Weather Summer School project listed here, ...

  5. Audit Report: OAS-FS-14-08 | Department of Energy

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

    8 Audit Report: OAS-FS-14-08 April 15, 2014 Performance Audit of the Department of Energy's Improper Payment Reporting in the Fiscal Year 2013 Agency Financial Report We contracted with the independent public accounting firm of KPMG LLP, to express an opinion on whether the Department of Energy (Department) met the U.S. Office of Management and Budget's criteria for compliance with the Improper Payments Elimination and Recovery Act of 2010 (IPERA). The objective of this audit was to complete an

  6. A criticism of applications with multi-criteria decision analysis that are used for the site selection for the disposal of municipal solid wastes

    SciTech Connect (OSTI)

    Kemal Korucu, M.; Erdagi, Bora

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer The existing structure of the multi-criteria decision analysis for site selection is criticized. Black-Right-Pointing-Pointer Fundamental problematic points based on the critics are defined. Black-Right-Pointing-Pointer Some modifications are suggested in order to provide solutions to these problematical points. Black-Right-Pointing-Pointer A new structure for the decision making mechanism is proposed. Black-Right-Pointing-Pointer The feasibility of the new method is subjected to an evaluation process. - Abstract: The main aim of this study is to criticize the process of selecting the most appropriate site for the disposal of municipal solid wastes which is one of the problematic issues of waste management operations. These kinds of problems are pathological symptoms of existing problematical human-nature relationship which is related to the syndrome called ecological crisis. In this regard, solving the site selection problem, which is just a small part of a larger entity, for the good of ecological rationality and social justice is only possible by founding a new and extensive type of human-nature relationship. In this study, as a problematic point regarding the discussions on ecological problems, the existing structure of the applications using multi-criteria decision analysis in the process of site selection with three main criteria is criticized. Based on this critique, fundamental problematic points (to which applications are insufficient to find solutions) will be defined. Later, some modifications will be suggested in order to provide solutions to these problematical points. Finally, the criticism addressed to the structure of the method with three main criteria and the feasibility of the new method with four main criteria is subjected to an evaluation process. As a result, it is emphasized that the new structure with four main criteria may be effective in solution of the fundamental problematic points.

  7. Microsoft Word - Blue Report Cover Report

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

    Report on Critical Asset Vulnerability and Risk Assessments at the Power Marketing ... and Risk Assessment at the Power Marketing Administrations--Follow-up Audit" ...

  8. Groups of homeomorphisms of the line. Criteria for the existence of invariant and projectively invariant measures in terms of the commutator subgroup

    SciTech Connect (OSTI)

    Beklaryan, L A

    2014-12-31

    Existence criteria for invariant and projectively invariant measures are obtained for a group G of homeomorphisms of the line. These criteria are formulated in terms of the commutator subgroup [G,G]. For the special (but very important) case of groups of homeomorphisms of the line containing a freely acting element we obtain a criterion for the existence of a projectively invariant measure in the form of the absence of a special subgroup with two generators in which one of the generating elements is a freely acting element. Bibliography: 20 titles.

  9. Hanford Lifecycle Reports - Hanford Site

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

    Hanford Lifecycle Reports Hanford Lifecycle Reports Hanford Lifecycle Reports Hanford Lifecycle Reports Email Email Page | Print Print Page |Text Increase Font Size Decrease Font Size 2016 Hanford Lifecycle Report 2015 Hanford Lifecycle Report 2014 Hanford Lifecycle Report 2013 Hanford Lifecycle Report 2012 Hanford Lifecycle Report 2011 Hanford Lifecycle Report Share on Last Updated 02/22/2016 2:54

  10. Title V Semi-Annual Emissions Report for Permit P100R1 July 1, 2011 - December 31, 2011

    SciTech Connect (OSTI)

    Whetham, Walter

    2012-03-15

    Reports of actual emissions from permitted sources in Section 2.0 shall be submitted on a 6 month basis. Reports shall not include emissions from insignificant activities. Emission estimates of criteria pollutants NOx, CO, SO2, PM and VOCs shall not include fugitive emissions. Emission estimates of HAPs shall include fugitive emissions. The reports shall include a comparison of actual emissions that occurred during the reporting period with the facility-wide allowable emission limits specified in Section 2.11 of this permit. The report required by Condition 4.1 shall be submitted within 90 days from the end of the reporting period. The semiannual report required by Condition 4.2 shall be submitted within 45 days from the end of the reporting period. The reporting periods are January 1st to June 30th and July 1st to December 31st. This condition is pursuant to 20.2.70.302.E.1 NMAC.

  11. SOLERAS - Solar Controlled Environment Agriculture Project. Final report, Volume 5. Science Applications, Incorporated system requirements definition

    SciTech Connect (OSTI)

    Not Available

    1985-01-01

    This report sets forth the system requirements for a Solar Controlled-Environment Agriculture System (SCEAS) Project. In the report a conceptual baseline system description for an engineering test facility is given. This baseline system employs a fluid roof/roof filter in combination with a large storage tank and a ground water heat exchanger in order to provide cooling and heating as needed. Desalination is accomplished by pretreatment followed by reverse osmosis. Energy is provided by means of photovoltaics and wind machines in conjunction with storage batteries. Site and climatic data needed in the design process are given. System performance specifications and integrated system design criteria are set forth. Detailed subsystem design criteria are presented and appropriate references documented.

  12. Quarterly Progress Report

    Broader source: Energy.gov [DOE]

    Quarterly Progress Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  13. Technical Consultant Report Template

    Office of Energy Efficiency and Renewable Energy (EERE)

    Technical Consultant Report Template, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  14. Daily Occurrence Reports

    Broader source: Energy.gov [DOE]

    DOE posting of occurrence reports will contain reports that were transmitted since the morning of the previous workday. The summary will provide a brief description of each occurrence along with the facility's organizational information and the title of the report. For those that desire additional information, the listing will contain the full occurrence reports.

  15. STEP Program Benchmark Report

    Broader source: Energy.gov [DOE]

    STEP Program Benchmark Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  16. STEP Participant Survey Report

    Broader source: Energy.gov [DOE]

    STEP Participant Survey Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  17. 2008 Annual Report

    SciTech Connect (OSTI)

    2008-01-01

    This annual report includes: a brief overview of Western; FY 2008 operational highlights; and financial data.

  18. CAF Bug Reports

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

    Reports CAF Bug Reports Viewing entries posted in November 2013 There are currently no significant reported user bugs with CAF. November 18, 2013 No reported CAF bugs. Read the full post Subscribe via RSS Subscribe Browse by Date November 2013 Last edited: 2016-04-29 11:34:54

  19. CAF Bug Reports

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

    » CAF Bug Reports CAF Bug Reports There are currently no significant reported user bugs with CAF. November 18, 2013 No reported CAF bugs. Read the full post Subscribe via RSS Subscribe Browse by Date November 2013 Last edited: 2016-04-29 11:34:54

  20. Audit Report: IG-0651

    Office of Energy Efficiency and Renewable Energy (EERE)

    Audit Report on Management of the Department's Personnel Security and Access Control Information Systems

  1. The NOvA Technical Design Report

    SciTech Connect (OSTI)

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

    2007-10-08

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

  2. Towards sustainable settlement growth: A new multi-criteria assessment for implementing environmental targets into strategic urban planning

    SciTech Connect (OSTI)

    Schetke, Sophie; Haase, Dagmar; Koetter, Theo

    2012-01-15

    For nearly one decade, the German political and research-agenda has been to a large extent determined by the ongoing question of how to limit the expansion of settlement areas around cities in order to preserve natural resources, make settlement growth more sustainable and to strengthen the re-use of existing inner-urban areas (see a.o. Koetter et al. 2009a, 2010; Schetke et al. 2009, 2010b). What is already under discussion within the international literature are the recommendations of the German Council for Sustainability to quantitatively reduce the daily greenfield consumption from the current rate of over 100 ha per day to a rate of 30 ha per day in 2020 and to bring urban infill development up to a ratio of 3:1 with greenfield development (German Council for Sustainability, 2004).). This paper addresses the added value beyond those abstract political targets and presents an innovative, multi-criteria assessment (MCA) of greenfield and infill sites to evaluate their sustainability and resource efficiency. MCA development and its incorporation into a Decision Support System (DSS) were accomplished by utilising a stakeholder-driven approach. The resulting tool can be applied in preparing and revising land-use plans. The paper presents the concept and the development process of the MCA-DSS. Test runs with planners prove that the evaluation of potential housing sites using individually weighted environmental indicators helps to identify those strategies of housing development that accord most closely with sustainability goals. The tests further show that the development of greenfield sites generally exhibits less sustainability than that of infill sites. - Highlights: Black-Right-Pointing-Pointer This paper presents an innovative, multi-criteria assessment (MCA) of greenfield and infill sites. Black-Right-Pointing-Pointer The MCA evaluates sustainability and resource efficiency of potential housing sites in a stakeholder-driven approach. Black-Right-Pointing-Pointer Test runs with planners identified prominent environmental indicators and assigned individual weights. Black-Right-Pointing-Pointer The resulting tool can be applied in preparing and revising land-use plans according to sustainable housing development. Black-Right-Pointing-Pointer Test runs also show that greenfield development generally exhibits less sustainability than infill development.

  3. NERSC Annual Reports

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

    NERSC Annual Reports NERSC Annual Reports Sort by: Default | Name anrep2000.png NERSC Annual Report 2000 Download Image: anrep2000.png | png | 203 KB Download File: NERSCAnnualReport2000.pdf | pdf | 4.9 MB anrep2001.png NERSC Annual Report 2001 Download Image: anrep2001.png | png | 175 KB Download File: annrep01.pdf | pdf | 7.1 MB anrep2002.png NERSC Annual Report 2002 Download Image: anrep2002.png | png | 55 KB Download File: annrep02.pdf | pdf | 3.4 MB anrep2003.png NERSC Annual Report 2003

  4. Publications & Reports

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

    User Surveys HPC Requirements for Science HPC Workshop Reports NERSC Staff Publications & Presentations Journal Cover Stories Galleries facebook icon Facebook google plus icon Google+ twitter icon Twitter Home » News & Publications » Publications & Reports Publications & Reports » Download the NERSC Strategic Plan (PDF | 3.2 MB) NERSC Annual Reports NERSC's annual reports highlight the scientific accomplishments of its users and innovations of its staff. Read More » Science

  5. Drilling Productivity Report

    U.S. Energy Information Administration (EIA) Indexed Site

    Drilling Productivity Report Report Background and Methodological Overview August 2014 Updated March 2016 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | Drilling Productivity Report: Report Background and Methodological Overview i This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data,

  6. ALS Activity Reports

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

    ALS Activity Reports Print These hard-copy annual reports were produced from 1993-2006. They illustrated the depth and breadth of the ALS scientific program with a selection of research results. They also summarized operations and ongoing R&D, highlighted educational outreach efforts and special events, and provided yearly documentation of the beamlines and publications. The Activity Report was replaced in 2007 by ALS Spectrum. The reports for 1996-2006 are available here. Activity Report

  7. ALS Activity Reports

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

    Activity Reports Print These hard-copy annual reports were produced from 1993-2006. They illustrated the depth and breadth of the ALS scientific program with a selection of research results. They also summarized operations and ongoing R&D, highlighted educational outreach efforts and special events, and provided yearly documentation of the beamlines and publications. The Activity Report was replaced in 2007 by ALS Spectrum. The reports for 1996-2006 are available here. Activity Report 2006

  8. ALS Activity Reports

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

    Activity Reports Print These hard-copy annual reports were produced from 1993-2006. They illustrated the depth and breadth of the ALS scientific program with a selection of research results. They also summarized operations and ongoing R&D, highlighted educational outreach efforts and special events, and provided yearly documentation of the beamlines and publications. The Activity Report was replaced in 2007 by ALS Spectrum. The reports for 1996-2006 are available here. Activity Report 2006

  9. ALS Activity Reports

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

    Activity Reports Print These hard-copy annual reports were produced from 1993-2006. They illustrated the depth and breadth of the ALS scientific program with a selection of research results. They also summarized operations and ongoing R&D, highlighted educational outreach efforts and special events, and provided yearly documentation of the beamlines and publications. The Activity Report was replaced in 2007 by ALS Spectrum. The reports for 1996-2006 are available here. Activity Report 2006

  10. Annual Site Environmental Report

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

    2014 Annual Site Environmental Report Updated July 24, 2015 NETL's Annual Site Environmental Report for 2014 -ii- 2014 Annual Site Environmental Report September 9, 2015 U.S. Department of Energy National Energy Technology Laboratory Albany, Oregon Anchorage, Alaska Morgantown, West Virginia Pittsburgh, Pennsylvania Sugar Land, Texas NETL's Annual Site Environmental Report for 2014 -iii- Disclaimer This report was prepared as an account of work sponsored by an agency of the U.S. Government.

  11. F-Area Acid/Caustic Basin groundwater monitoring report: Second quarter 1992

    SciTech Connect (OSTI)

    Thompson, C.Y.

    1992-09-01

    During second quarter 1992, samples from the six FAC monitoring wells at the F-Area Acid/Caustic Basin were analyzed for herbicides, indicator parameters, major ions, pesticides, radionuclides, turbidity, volatile organic compounds, and other constituents. Monitoring results that exceeded the US Environmental Protection Agency's Primary Drinking Water Standards (PDWS) or the Savannah River Site flagging criteria or turbidity standards during the quarter are the focus of this report.

  12. F-Area Acid/Caustic Basin groundwater monitoring report: Second quarter 1992

    SciTech Connect (OSTI)

    Thompson, C.Y.

    1992-09-01

    During second quarter 1992, samples from the six FAC monitoring wells at the F-Area Acid/Caustic Basin were analyzed for herbicides, indicator parameters, major ions, pesticides, radionuclides, turbidity, volatile organic compounds, and other constituents. Monitoring results that exceeded the US Environmental Protection Agency`s Primary Drinking Water Standards (PDWS) or the Savannah River Site flagging criteria or turbidity standards during the quarter are the focus of this report.

  13. Third Party Financing Criteria

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

    a loan or score against BPA's Treasury Borrowing Authority. The proposal must address any tax (local, state, property, etc.) issues that would arise under the proposal. At this...

  14. Criteria for quantum chaos

    SciTech Connect (OSTI)

    Heller, E.J. (Los Alamos National Lab., Albuquerque, NM); Davis, M.J.

    1982-06-10

    This paper reviews some of the opinions on quantum chaos put forth at the 1981 American Conference on Theoretical Chemistry and presents evidence to support the author's point of view. The degree of correspondence between classical and quantum onset and extent of chaos differs markedly according to the definition adopted for quantum chaos. At one extreme, a quantum generalization of the classical Kolmolgorov entropy which give zero entrophy for quantum systems with a discrete spectrum regardless of the classical properties, was a suitable foundation for the definition of quantum chaos. At the other, the quantum phase space definition shows generally excellent correspondence to the classical phase space measures. The authors preferred this approach. Another point of controversy is the question of whether the spectrum of energy levels (or its variation with some parameter of the Hamiltonian) is enough to characterize the quantum chaos (or lack of it), or whether more information is needed (i.e., eigenfunctions). The authors conclude that one does not want to rely upon eigenvalues alone to characterize the degree of chaos in the quantum dynamics.

  15. Criteria for SES Positions

    Broader source: Energy.gov [DOE]

    Initial career appointments to the SES must be made following competitive merit staffing requirements. Agencies must announce SES vacancies that will be filled by initial career appointment to at...

  16. Regulatory Analysis on Criteria

    Office of Scientific and Technical Information (OSTI)

    ... For other implants involving NUREG-1492 the lungs, brain, pancreas, etc., tissue shielding values of similar magnitude can be assumed for an adult male and female. However, for ...

  17. ARM - Guidelines : Review Criteria

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

    for Principal Investigators Forms Propose a Campaign Instrument Support Request (ISR) Form (Word, 89KB) Documentation Steps for Submitting Field Campaign Data and Metadata...

  18. SU-E-T-617: A Feasibility Study of Navigation Based Multi Criteria Optimization for Advanced Cervical Cancer IMRT Planning

    SciTech Connect (OSTI)

    Ma, C

    2014-06-01

    Purpose: This study aims to validate multi-criteria optimization (MCO) against standard intensity modulated radiation therapy (IMRT) optimization for advanced cervical cancer in RayStation (v2.4, RaySearch Laboratories, Sweden). Methods: 10 advanced cervical cancer patients IMRT plans were randomly selected, these plans were designed with step and shoot optimization, new plans were then designed with MCO based on these plans,while keeping optimization conditions unchanged,comparison was made between both kinds of plans including the dose volume histogram parameters of PTV and OAR,and were analysed by pairing-t test. Results: We normalize the plan so that 95% volume of PTV achieved the prescribed dose(50Gy). The volume of radiation 10, 20, 30, and 40 Gy of the rectum were reduced by 14.7%,26.8%,21.1%,10.5% respectively(P?0.05). The mean dose of rectum were reduced by 7.2Gy(P?0.05). There were no significant differences for the dosimetric parameters for the bladder. Conclusion: In comparision with standard IMRT optimization, MCO reduces the dose of organs at risk with the same PTV coverage,but the result needs further clinical evalution.

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

    SciTech Connect (OSTI)

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

    1995-02-01

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

  20. Annual Reports | Department of Energy

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

    Annual Reports Annual Reports Note: Some of the following documents are in PDF and will require Adobe Reader for viewing. Freedom of Information Act Annual Reports Annual Report for 2015 Annual Report for 2014 Annual Report for 2013 Annual Report for 2012 Annual Report for 2011 Annual Report for 2010 Annual Report for 2009 Annual Report for 2008 (pdf) Annual Report for 2007 (pdf) Annual Report for 2006 (pdf) Annual Report for 2005 (pdf) Annual Report for 2004 (pdf) Annual Report for 2003 (pdf)

  1. Pulsed Power Peer Review Committee Report

    SciTech Connect (OSTI)

    BLOOMQUIST,DOUGLAS D.

    2000-12-01

    In 1993, the Government Performance and Results Act (GPRA, PL 103-62) was enacted. GPRA, which applies to all federal programs, has three components: strategic plans, annual performance plans, and metrics to show how well annual plans are being followed. As part of meeting the GRPA requirement in FY2000, a 14-member external peer review panel (the Garwin Committee) was convened on May 17-19, 2000 to review Sandia National Laboratories' Pulsed Power Programs as a component of the Performance Appraisal Process negotiated with the Department of Energy (DOE). The scope of the review included activities in inertial confinement fission (ICF), weapon physics, development of radiation sources for weapons effects simulation, x-ray radiography, basic research in high energy density physics (HEDP), and pulsed power technology research and development. In his charge to the committee, Jeffrey Quintenz, Director of Pulsed Power Sciences (1600) asked that the review be based on four criteria (1) quality of science, technology, and engineering, (2) programmatic performance, management, and planning, (3) relevance to national needs and agency missions, and (4) performance in the operation and construction of major research facilities. In addition, specific programmatic questions were posed by the director and by the DOE-Defense Programs (DP). The accompanying report, produced as a SAND document, is the report of the committee's findings.

  2. Data Network Weather Service Reporting - Final Report

    SciTech Connect (OSTI)

    Michael Frey

    2012-08-30

    A final report is made of a three-year effort to develop a new forecasting paradigm for computer network performance. This effort was made in co-ordination with Fermi Lab's construction of e-Weather Center.

  3. Enclosures Standing Technical Committee Strategic Plan report

    Energy Savers [EERE]

    ... to several comparison criteria. http:... Field reviews of installed low-density and high-density ... Heating Home Energy Management Advanced Heating & ...

  4. 2008 Annual Site Environmental Report Summary Pamphlet

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

    ... ER sites addressed included solid waste management units ... waste, radioactive low-level waste (LLW), mixed hazardous... when they meet NMED criteria, either before or after ...

  5. Report - Considering Cumulative Effects Under NEPA

    Energy Savers [EERE]

    ... with natural water level regimes in the context of ... assessment and management planning: Lessons learned to date. ... WQC water quality criteria Q upstream flow s Q ...

  6. "Annual Coal Report

    U.S. Energy Information Administration (EIA) Indexed Site

    Annual Coal Report Data Released: January 20, 2015 Data for: 2013 Re-Release Date: April 23, 2015 (CORRECTION) Annual Coal Report 2013 CorrectionUpdate April 23, 2015 The Annual ...

  7. MSC Monthly Performance Report

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

    Report January 2010 F.A. Figueroa President and General Manager U.S. Department of Energy Contract DE-AC06-09RL14728 MSC Monthly Performance Report January 2010 DOE...

  8. MSC Monthly Performance Report

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

    Report December 2009 F.A. Figueroa President and General Manager U.S. Department of Energy Contract DE-AC06-09RL14728 MSC Monthly Performance Report December 2009 DOE...

  9. Quarterly Progress Report

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

    Effective Recovery of Low-TDS Frac Flowback Water for Re-use Department of Energy: DE-FE0000784 Final Report Reporting Period: October 1, 2009 - March 31, 2011 Harish R. Acharya...

  10. Prediction of External Corrosion for Steel Cylinders--2002 Report

    SciTech Connect (OSTI)

    Schmoyer, RLS

    2002-07-31

    The United States Department of Energy (DOE) manages the UF{sub 6} Cylinder Project. The project was formed to maintain and safely manage the depleted uranium hexafluoride (UF{sub 6}) stored in approximately 50,000 carbon steel cylinders. The cylinders are located at three DOE sites: the East Tennessee Technology Park (ETTP) site in Oak Ridge, Tennessee; the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky, and the Portsmouth Gaseous Diffusion Plant (PORTS) in Portsmouth, Ohio. The System Requirements Document (SRD) (LMES 1997a) delineates the requirements of the project, and the actions needed to fulfill these requirements are specified in the System Engineering Management Plan (SEMP) (LMES 1997b). This report documents activities that in whole or part satisfy specific requirements and actions stated in the UF{sub 6} Cylinder Project SRD and SEMP with respect to forecasting cylinder conditions. The results presented here supercede those presented by Lyon (1995, 1996, 1997, 1998, 2000), and Schmoyer and Lyon (2001). Many of the wall thickness projections made in this report are conservative, because they are based on the assumption that corrosion trends will continue, despite activities such as improved monitoring, relocations to better storage, painting, and other improvements in storage conditions relative to the conditions at the times most of the wall thickness measurements were made. For thin-wall cylinders (design nominal wall thickness 312.5 mils), the critical minimum wall thicknesses criteria used in this report are 0 (breach), 62.5 mils, and 250 mils (1 mil = 0.001 in.). For thick-wall cylinders (design nominal wall thickness 625 mils), the thickness criteria used in this report are 0, 62.5 mils, and 500 mils. The criteria triples are preliminary boundaries identified within the project that indicate (1) loss of material (UF{sub 6}), (2) safe handling and stacking operations, and (3) standards for off-site transport and contents transfer criteria, respectively. In general, these criteria are based on an area of wall thinning. However, the minimum thickness predicted in this report is essentially for a point--an area of about 0.01 square inches--because the thickness measurements on which the predictions are based are essentially for points. For thicknesses criteria greater than zero, conclusions based on minimum point thicknesses are conservative. Because of the interaction of UF{sub 6}, with atmospheric moisture and steel, a point breach would deteriorate in a year to one-inch diameter hole (DNFSB 1995), however, and so small area approximations should be close for the breach criteria. The most recently collected data, entered into the corrosion model database and not available for the previous report (Schmoyer and Lyon 2001), consists of evaluations of wall loss of 48 inch thin-wall cylinders: 301 cylinders at Paducah, 101 at ETTP, and 139 at Portsmouth; 14 thick-wall cylinders at Portsmouth; and 99 model 30A cylinders at Paducah. However, because of missing values, repeated measures on the same cylinders, outliers, and other data problems, however, not all of these measurements are necessarily used in the corrosion analysis. In several cases, difficulty with the data is also due to a mathematical approach to cylinder corrosion modeling that is used in this report, in Schmoyer and Lyon (2001), and in earlier reports by Lyon. Therefore, an alternative approach is also considered in this report. In previous reports, minimum wall thicknesses have been modeled indirectly through separate models of initial thickness and maximum pit depth. In order to estimate minimum wall thicknesses, the initial thickness and maximum pit depth models are combined using mathematics that assumes independence of the statistical distributions of the initial thicknesses and maximum pit depths. Initial thicknesses are modeled from wall thickness maxima measured at relatively uncorroded wall areas of each cylinder. Maximum pit depths for each cylinder are estimated as differences between the initial thickness estimates and measured minimum wall thicknesses. The pit depth maxima estimates are modeled as a function of age and a cylinder grouping based on location.

  11. FY 2007 Reports

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

    Environmental Management Monthly Reports - FY 2007 The Department of Energy Nevada Field Office Environmental Management Program creates monthly reports for the NSSAB. These reports cover the completed activities for the current month and the expectations for the following month. Should you have questions about the EM Monthly Reports please contact envmgt@nv.doe.gov or call (702) 295-3521. October 2006 November 2006 December 2006 January 2007 February 2007 March 2007 April 2007 May 2007 June

  12. FY 2008 Reports

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

    Environmental Management Monthly Reports - FY 2008 The Department of Energy Nevada Field Office Environmental Management Program creates monthly reports for the NSSAB. These reports cover the completed activities for the current month and the expectations for the following month. Should you have questions about the EM Monthly Reports please contact envmgt@nv.doe.gov or call (702) 295-3521. October 2007 November 2007 December 2007 January 2008 February 2008 March 2008 April 2008 May 2008 June

  13. FY 2009 Reports

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

    Environmental Management Monthly Reports - FY 2009 The Department of Energy Nevada Field Office Environmental Management Program creates monthly reports for the NSSAB. These reports cover the completed activities for the current month and the expectations for the following month. Should you have questions about the EM Monthly Reports please contact envmgt@nv.doe.gov or call (702) 295-3521. October 2008 November 2008 December 2008 January 2009 February 2009 March 2009 April 2009 May 2009 June

  14. FY 2010 Reports

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

    Environmental Management Monthly Reports - FY 2010 The Department of Energy Nevada Field Office Environmental Management Program creates monthly reports for the NSSAB. These reports cover the completed activities for the current month and the expectations for the following month. Should you have questions about the EM Monthly Reports please contact envmgt@nv.doe.gov or call (702) 295-3521. October 2009 November 2009 December 2009 January 2010 February 2010 March 2010 April 2010 May 2010 June

  15. FY 2011 Reports

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

    Environmental Management Monthly Reports - FY 2011 The Department of Energy Nevada Field Office Environmental Management Program creates monthly reports for the NSSAB. These reports cover the completed activities for the current month and the expectations for the following month. Should you have questions about the EM Monthly Reports please contact envmgt@nv.doe.gov or call (702) 295-3521. October 2010 November 2010 December 2010 January 2011 February 2011 March 2011 April 2011 May 2011 June

  16. Guidance, Reports, and Documents

    Broader source: Energy.gov [DOE]

    The following are annual reports, guidance documents, and regulatory drivers for long-term surveillance and maintenance activities.

  17. Annual Site Environmental Report

    Energy Savers [EERE]

    Department of Energy Annual Reports to Congress on Federal Government Energy Management Annual Reports to Congress on Federal Government Energy Management Annual reports on federal energy management respond to section 548 of the National Energy Conservation Policy Act (NECPA, Pub. L. No. 95-619), as amended, and provide information on energy consumption in federal buildings, operations, and vehicles. Compiled by the Federal Energy Management Program, these reports document activities

  18. CM modeling report

    SciTech Connect (OSTI)

    Vann, J.M., Fluor Daniel Hanford

    1997-02-07

    This report compiles TWRS configuration management pre- implementation assessments, categorizes findings, and highlights programs identified for improvement.

  19. Regional Efficiency Progress Report

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

    Expand Utility Resources News & Events Expand News & Events Skip navigation links Marketing Resources Reports, Publications, and Research Agricultural Commercial Consumer...

  20. Assorted Situation Reports

    Broader source: Energy.gov [DOE]

    The Office of Electricity Delivery and Energy Reliability issues public Situation Reports during large scale energy emergencies.

  1. MMCR Calibration Report

    SciTech Connect (OSTI)

    Mead, D

    2010-03-23

    Calibration report for the Millimeter Wavelength Cloud Radar performed for the ARM Climate Research Facility by ProSensing Inc.

  2. Federal Financial Report

    Broader source: Energy.gov [DOE]

    Federal Financial Report, as posted on the U.S. Department of Energy's Better Buildings Neighborhood Program website.

  3. Updated greenhouse gas and criteria air pollutant emission factors and their probability distribution functions for electricity generating units

    SciTech Connect (OSTI)

    Cai, H.; Wang, M.; Elgowainy, A.; Han, J.

    2012-07-06

    Greenhouse gas (CO{sub 2}, CH{sub 4} and N{sub 2}O, hereinafter GHG) and criteria air pollutant (CO, NO{sub x}, VOC, PM{sub 10}, PM{sub 2.5} and SO{sub x}, hereinafter CAP) emission factors for various types of power plants burning various fuels with different technologies are important upstream parameters for estimating life-cycle emissions associated with alternative vehicle/fuel systems in the transportation sector, especially electric vehicles. The emission factors are typically expressed in grams of GHG or CAP per kWh of electricity generated by a specific power generation technology. This document describes our approach for updating and expanding GHG and CAP emission factors in the GREET (Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation) model developed at Argonne National Laboratory (see Wang 1999 and the GREET website at http://greet.es.anl.gov/main) for various power generation technologies. These GHG and CAP emissions are used to estimate the impact of electricity use by stationary and transportation applications on their fuel-cycle emissions. The electricity generation mixes and the fuel shares attributable to various combustion technologies at the national, regional and state levels are also updated in this document. The energy conversion efficiencies of electric generating units (EGUs) by fuel type and combustion technology are calculated on the basis of the lower heating values of each fuel, to be consistent with the basis used in GREET for transportation fuels. On the basis of the updated GHG and CAP emission factors and energy efficiencies of EGUs, the probability distribution functions (PDFs), which are functions that describe the relative likelihood for the emission factors and energy efficiencies as random variables to take on a given value by the integral of their own probability distributions, are updated using best-fit statistical curves to characterize the uncertainties associated with GHG and CAP emissions in life-cycle modeling with GREET.

  4. An Approach to Industrial Stormwater Benchmarks: Establishing and Using Site-Specific Threshold Criteria at Lawrence Livermore National Laboratory

    SciTech Connect (OSTI)

    Campbell, C G; Mathews, S

    2006-09-07

    Current regulatory schemes use generic or industrial sector specific benchmarks to evaluate the quality of industrial stormwater discharges. While benchmarks can be a useful tool for facility stormwater managers in evaluating the quality stormwater runoff, benchmarks typically do not take into account site-specific conditions, such as: soil chemistry, atmospheric deposition, seasonal changes in water source, and upstream land use. Failing to account for these factors may lead to unnecessary costs to trace a source of natural variation, or potentially missing a significant local water quality problem. Site-specific water quality thresholds, established upon the statistical evaluation of historic data take into account these factors, are a better tool for the direct evaluation of runoff quality, and a more cost-effective trigger to investigate anomalous results. Lawrence Livermore National Laboratory (LLNL), a federal facility, established stormwater monitoring programs to comply with the requirements of the industrial stormwater permit and Department of Energy orders, which require the evaluation of the impact of effluent discharges on the environment. LLNL recognized the need to create a tool to evaluate and manage stormwater quality that would allow analysts to identify trends in stormwater quality and recognize anomalous results so that trace-back and corrective actions could be initiated. LLNL created the site-specific water quality threshold tool to better understand the nature of the stormwater influent and effluent, to establish a technical basis for determining when facility operations might be impacting the quality of stormwater discharges, and to provide ''action levels'' to initiate follow-up to analytical results. The threshold criteria were based on a statistical analysis of the historic stormwater monitoring data and a review of relevant water quality objectives.

  5. Technical Review Panel Report

    Energy Savers [EERE]

    TRP Report v7, 12 Aug 2012 TRP Report Final December 2012 Advanced Reactor Concepts Technical Review Panel Report Evaluation and Identification of future R&D on eight Advanced Reactor Concepts, conducted April - September 2012 December 2012 Public release version 2 Public release version 3 Table of Contents Summary ................................................................................................................................... 4 1. Overview of the Technical Review Panel

  6. Organic solvent topical report

    SciTech Connect (OSTI)

    Cowley, W.L.

    1998-04-30

    This report is the technical basis for the accident and consequence analyses used in the Hanford Tank Farms Basis for Interim Operation. The report also contains the scientific and engineering information and reference material needed to understand the organic solvent safety issue. This report includes comments received from the Chemical Reactions Subcommittee of the Tank Advisory Panel.

  7. 2014 Site Environmental Report

    SciTech Connect (OSTI)

    Paquette, Douglas; Remien, Jason; Foley, Brian; Burke, John; Dorsch, William; Ratel, Karen; Howe, Robert; Welty, Tim; Williams, Jeffrey; Pohlpt, Peter; Lagattolla, Richard; Metz, Robert; Milligan, James; Lettieri, Lawrence

    2015-10-01

    BNL prepares an annual Site Environmental Report (SER) in accordance with DOE Order 231.1B, Environment, Safety and Health Reporting. The report is written to inform the public, regulators, employees, and other stakeholders of the Laboratory’s environmental performance during the calendar year in review.

  8. Cray Bug Reports

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

    Cray » Cray Bug Reports Cray Bug Reports Cray C/C++ predefined _RELEASE macro returns wrong value [updated] November 18, 2013 by Mike Stewart, NERSC USG Status: Reported to Cray as bug 797442, became documentation bug 805340. Read the full post Subscribe via RSS Subscribe Browse by Date November 2013 Last edited: 2016-04-29 11:34:26

  9. Proposals and Design Reports

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

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

  10. Report number codes

    SciTech Connect (OSTI)

    Nelson, R.N.

    1985-05-01

    This publication lists all report number codes processed by the Office of Scientific and Technical Information. The report codes are substantially based on the American National Standards Institute, Standard Technical Report Number (STRN)-Format and Creation Z39.23-1983. The Standard Technical Report Number (STRN) provides one of the primary methods of identifying a specific technical report. The STRN consists of two parts: The report code and the sequential number. The report code identifies the issuing organization, a specific program, or a type of document. The sequential number, which is assigned in sequence by each report issuing entity, is not included in this publication. Part I of this compilation is alphabetized by report codes followed by issuing installations. Part II lists the issuing organization followed by the assigned report code(s). In both Parts I and II, the names of issuing organizations appear for the most part in the form used at the time the reports were issued. However, for some of the more prolific installations which have had name changes, all entries have been merged under the current name.

  11. Near field and altered zone environmental report Volume I: technical bases for EBS design

    SciTech Connect (OSTI)

    Wilder, D. G., LLNL

    1997-08-01

    This report presents an updated summary of results for the waste package (WP) and engineered barrier system (EBS) evaluations, including materials testing, waste-form characterization, EBS performance assessments, and near-field environment (NFE) characterization. Materials testing, design criteria and concept development, and waste-form characterization all require an understanding of the environmental conditions that will interact with the WP and EBS. The Near-Field Environment Report (NFER) was identified in the Waste Package Plan (WPP) (Harrison- Giesler, 1991) as the formal means for transmitting and documenting this information.

  12. 2014 Better Buildings Neighborhood Program Reporting Calendar

    Broader source: Energy.gov [DOE]

    Better Buildings Neighborhood Program, reporting, grants, quarterly report, recovery act report, davis-bacon report, historic preservation report, pmc

  13. Tank 241-BY-112, cores 174 and 177 analytical results for the final report

    SciTech Connect (OSTI)

    Nuzum, J.L.

    1997-05-06

    Results from bulk density tests ranged from 1.03 g/mL to 1.86 g/mL. The highest bulk density result of 1.86 g/mL was used to calculate the solid total alpha activity notification limit for this tank (33.1 uCi/g), Total Alpha (AT) Analysis. Attachment 2 contains the Data Verification and Deliverable (DVD) Summary Report for AT analyses. This report summarizes results from AT analyses and provides data qualifiers and total propagated uncertainty (TPU) values for results. The TPU values are based on the uncertainties inherent in each step of the analysis process. They may be used as an additional reference to determine reasonable RPD values which may be used to accept valid data that do not meet the TSAP acceptance criteria. A report guide is provided with the report to assist in understanding this summary report.

  14. MINIMARS conceptual design: Final report

    SciTech Connect (OSTI)

    Lee, J.D.

    1986-09-01

    This volume contains the following sections: (1) fueling systems; (2) blanket; (3) alternative blanket concepts; (4) halo scraper/direct converter system study and final conceptual design; (5) heat-transport and power-conversion systems; (6) tritium systems; (7) minimars air detritiation system; (8) appropriate radiological safety design criteria; and (9) cost estimate. (MOW)

  15. CRAD, Assessment Criteria and Guidelines for Determining the Adequacy of Software Used in the Safety Analysis and Design of Defense Nuclear Facilities

    Broader source: Energy.gov [DOE]

    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.

  16. Damaged Surface Hydrodynamics (DSH) Flash Report (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Damaged Surface Hydrodynamics (DSH) Flash Report Citation Details In-Document Search Title: Damaged Surface Hydrodynamics (DSH) Flash Report You are accessing ...

  17. FY09 Engineering Research & Technology Report (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: FY09 Engineering Research & Technology Report Citation Details In-Document Search Title: FY09 Engineering Research & Technology Report Authors: Sharpe, R ; Pannu, ...

  18. Majors' Shift to Natural Gas, The

    Reports and Publications (EIA)

    2001-01-01

    The Majors' Shift to Natural Gas investigates the factors that have guided the United States' major energy producers' growth in U.S. natural gas production relative to oil production. The analysis draws heavily on financial and operating data from the Energy Information Administration's Financial Reporting System (FRS)

  19. Geotechnical field data and analysis report, July 1990--June 1991

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    The Geotechnical Field Data and Analysis Report documents the geotechnical data from the underground excavations at the Waste Isolation Pilot Plant (WIPP) located near Carlsbad, New Mexico. The data are used to characterize conditions, confirm design assumption, and understand and predict the performance of the underground excavations during operations. During the construction of the principal underground access and experimental areas, reporting was on a quarterly basis. Since 1987, reporting has been carried out annually because additional excavations such as the waste storage panels, will take place gradually over an extended period. This report presents and analyzes data collected up to June 30, 1991. The two-volume format of the Geotechnical Field Data and Analysis Report was selected to meet the needs of several audiences. Volume I focuses on the geotechnical performance of the various underground facilities including the shafts, shaft stations, access drifts, test rooms, and waste storage areas. The results of excavation effects investigations, stratigraphic mapping, and the occurrence of brine are also documented. It provides an evaluation of the geotechnical aspects of performance in the context of the relevant design criteria. The depth and breadth of the evaluation for the different underground facilities varies according to the types and quantities of data that are available, and the complexity of the recorded geotechnical responses.

  20. 2006 SITE ENVIRONMENTAL REPORT

    SciTech Connect (OSTI)

    BROOKHAVEN NATIONAL LABORATORY; RATEL,K.

    2007-10-01

    Each year, Brookhaven National Laboratory (BNL) prepares an annual Site Environmental Report (SER) in accordance with DOE Order 231.1A, Environment, Safety and Health Reporting of the U.S. Department of Energy. The report is written to inform the public, regulators, employees, and other stakeholders of BNL's environmental performance during the calendar year in review. The SER summarizes environmental data; environmental management performance; compliance with applicable DOE, federal, state, and local regulations; and compliance, restoration, and surveillance monitoring program performance. BNL has prepared annual SERs since 1971 and has documented nearly all of its environmental history since the Laboratory's inception in 1947. The report is available in print and as a downloadable file on the BNL web page at http://www.bnl.gov/ewms/ser/. A summary of the SER is also prepared each year to provide a general overview of the report, and is distributed with a CD of the full report.