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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 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. Nuclear Safety Reporting Criteria

  2. Security Enforcement Reporting Criteria | Department of Energy

    Office of Environmental Management (EM)

    Mandatory Security Incident Reporting This document provides information and criteria for reporting classified information security incidents and noncompliances to the Department ...

  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 ...

  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. Fuel Retrieval System (FRS) Design Verification

    SciTech Connect (OSTI)

    YANOCHKO, R.M.

    2000-01-27

    This document was prepared as part of an independent review to explain design verification activities already completed, and to define the remaining design verification actions for the Fuel Retrieval System. The Fuel Retrieval Subproject was established as part of the Spent Nuclear Fuel Project (SNF Project) to retrieve and repackage the SNF located in the K Basins. The Fuel Retrieval System (FRS) construction work is complete in the KW Basin, and start-up testing is underway Design modifications and construction planning are also underway for the KE Basin. An independent review of the design verification process as applied to the K Basin projects was initiated in support of preparation for the SNF Project operational readiness review (ORR).

  8. 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.

  9. 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.

  10. Regulatory analysis on criteria for the release of patients administered radioactive material. Final report

    SciTech Connect (OSTI)

    Schneider, S.; McGuire, S.A.

    1997-02-01

    This regulatory analysis was developed to respond to three petitions for rulemaking to amend 10 CFR parts 20 and 35 regarding release of patients administered radioactive material. The petitions requested revision of these regulations to remove the ambiguity that existed between the 1-millisievert (0.1-rem) total effective dose equivalent (TEDE) public dose limit in Part 20, adopted in 1991, and the activity-based release limit in 10 CFR 35.75 that, in some instances, would permit release of individuals in excess of the current public dose limit. Three alternatives for resolution of the petitions were evaluated. Under Alternative 1, NRC would amend its patient release criteria in 10 CFR 35.75 to match the annual public dose limit in Part 20 of 1 millisievert (0.1 rem) TEDE. Alternative 2 would maintain the status quo of using the activity-based release criteria currently found in 10 CFR 35.75. Under Alternative 3, the NRC would revise the release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts (0.5 rem) TEDE.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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).

  17. A review of macroscopic ductile failure criteria. (Technical...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: A review of macroscopic ductile failure criteria. Citation Details In-Document Search Title: A review of macroscopic ductile failure criteria. The objective of ...

  18. Technical Qualification Program Accreditation Objectives and Criteria |

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

    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. TQP Accreditation Objectives and Criteria (40.57 KB) More Documents & Publications Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 Technical

  19. 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. Membership Criteria (126.27 KB) More Documents & Publications Better Buildings Residential Network Orientation Better Buildings Residential Network Reporting and Benefits FAQ How Can the Network Meet Your Needs?

  20. ARM - Guidelines : Review Criteria

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

    Review Criteria Guidelines Overview Annual Facility Call Proposal Deadline Guidance Small Field Campaigns Review Criteria Expectations for Principal Investigators Forms Propose a Campaign Instrument Support Request (ISR) Form (Word, 89KB) Unmanned Aerial System (UAS) Mission Request Form (Word, 72KB) Documentation Submitting Field Campaign Data and Metadata Field Campaign Guidelines (PDF, 574KB) Unmanned Aerial System Operation Safety at ARM Sites (PDF, 639KB) Guidelines : Review Criteria

  1. 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)...

  2. Plutonium storage criteria

    SciTech Connect (OSTI)

    Chung, D.; Ascanio, X.

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  3. 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.

  4. 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)

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. Assessment B - Program Criteria | Department of Energy

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

    B - Program Criteria Assessment B - Program Criteria Microsoft Word - Assessment-B-ProgramCriteria (218.66 KB) More Documents & Publications ATTACHMENT A - CHECKLIST FOR SELF ...

  12. 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.

  13. 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.

  14. EXPO Award Criteria - Hanford Site

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

    Award Criteria About Us Hanford Cultural Resources 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

  15. 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.

  16. (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)

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

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

    ... Safety Analysis Report (SAR). 7.3.2 In the design of sway bracing, the criteria of Section 4-14.4.3.5.3 (or current equivalent) of NFPA 13 (1996) should be revised as follows. ...

  18. 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.

  19. 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

  20. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards.

  1. 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 ...

  2. Membership Criteria: Better Buildings Residential Network | Department...

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

    Membership Criteria: Better Buildings Residential Network of the U.S. Department of Energy. Membership Criteria (126.27 KB) More Documents & Publications Better Buildings ...

  3. 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.

  4. Los Alamos Waste Acceptance Criteria | Department of Energy

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

    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

  5. 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 ...

  6. 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. Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE

  7. 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.

  8. 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

  9. 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...

  10. 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.

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

    SciTech Connect (OSTI)

    Osterwald, C.R.; Hammond, R.L.; Wood, B.D.; Backus, C.E.; Sears, R.L.; Zerlaut, G.A.; D`Aiello, R.V.

    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.

  12. 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...

  13. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect (OSTI)

    Not Available

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC (Nuclear Regulatory Commission) licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor.

  14. 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...

  15. 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...

  16. 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...

  17. 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

  18. WPN 99-7- WAP Eligibility Criteria

    Broader source: Energy.gov [DOE]

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

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

    Energy Savers [EERE]

    Electronic Records Management Software Applications Design Criteria Standard This Standard is reissued under the authority of DoD Directive 5015.2, "Department of DefenseRecords ...

  20. 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

  1. 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.

  2. 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.

  3. Program Evaluation: Criteria, Logistics, Cost, and Analysis | Department of

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

    Energy Criteria, Logistics, Cost, and Analysis Program Evaluation: Criteria, Logistics, Cost, and Analysis There are a few criteria that are often recommended and used by the DOE, OMB, NAS, and others. Although programs may choose to define additional criteria, at a minimum all EERE programs are expected to use the following three criteria (referred to as "core criteria"). The three core criteria are the following: Quality, Productivity, and Accomplishments. Quality, as used here,

  4. 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.

  5. Facility Representative Program, Criteria & Review Approach Documents

    Office of Energy Efficiency and Renewable Energy (EERE)

    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.

  6. 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.

  7. 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. Electronic Records Management

  8. Criteria for SES Positions | Department of Energy

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

    Services » Executive Resources » Senior Executive Service (SES) » Criteria for SES Positions Criteria for SES Positions 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 least all Federal civil service employees. Vacancies are published on the USAJOBS Veteran's preference does not apply to SES selections. An Executive Resources Board (ERB) is

  9. NITRATE DESTRUCTION LITERATURE SURVEY AND EVALUATION CRITERIA

    SciTech Connect (OSTI)

    Steimke, J.

    2011-02-01

    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

  10. Reports

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

    ... Submittal Letter (pdf) Appendix A (xls) AnchoChaquehui Watershed PCB Report Polychlorinated Biphenyls in Precipitation and Stormwater within the Upper Rio Grande Watershed (pdf) ...

  11. 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.

  12. 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.

  13. 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 ...

  14. Energy Department Announces More Stringent Criteria for ENERGY...

    Office of Environmental Management (EM)

    More Stringent Criteria for ENERGY STAR Refrigerators Energy Department Announces More Stringent Criteria for ENERGY STAR Refrigerators August 3, 2007 - 2:55pm Addthis ...

  15. Understanding seismic design criteria for Japanese nuclear power...

    Office of Scientific and Technical Information (OSTI)

    Understanding seismic design criteria for Japanese nuclear power plants Citation Details In-Document Search Title: Understanding seismic design criteria for Japanese nuclear power ...

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. Solid waste disposal facility criteria. Technical manual

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

    The technical manual has been developed to assist municipal solid waste landfill (MSWLF) owners and operators in achieving compliance with the revised MSWLF Criteria, promulgated on October 9, 1991 in Title 40, Part 258, of the Code of Federal Regulations (CFR). The manual is not a regulatory document, and does not provide mandatory technical guidance, but does provide assistance for coming into compliance with the technical aspects of the revised landfill Criteria. The document is intended for use by landfill owners/operators and their consultants and contractors who provide advice on demonstrating compliance with the Part 258 standards.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. Microsoft Word - Assessment-B-ProgramCriteria

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

    ATTACHMENT B PROGRAM ASSESSMENT CRITERIA Identify the following for all sites: Program Management * Number FTE's devoted to Records Management o Full-time Federal and Contractor o Part-time Federal and Contractor Percent of time spent on Records Management duties * Percentage of time each Records Management employee is assigned to: o Program Management o Operations Training/Assistance Schedule Application Records Holding/Storage Area Activities EEOICPA Claims * Monthly Claim Volume Other,

  11. 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.

  12. Application Content and Evaluation Criteria/Process

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

    Evaluation Criteria/Process Jill Gruber Golden Field Office Department of Energy May 18, 2007 The information presented here is an outline of how the Funding Opportunity Announcement (FOA) may be structured. The final application requirements will be shown in the FOA when it is posted on Grants.gov. The schedule and awards are dependent on future appropriations and may change if future appropriations are lower than expected or in the event of a continuing resolution. DOE Points of Contact DOE

  13. Application Content and Evaluation Criteria/Process

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

    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

  14. 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,

  15. 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.

  16. Reports

    Office of Legacy Management (LM)

    Reports . . . . , Book -1. Service Open File Information for Project Rulison, Production Testing Phase, . , August 28,1970 : . "; DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. DESCRIPTION O F PU1:T41C I-l!lkI,T;-1 SE1:VICh: 0P:SN F I L E INPOPt4ATION i[ ' 7 S&u-~%uestcrn E a d i o l o g i c a l H e a l t h 1,aboratol-p r? U. S. Depaieraent o f I l e a l t h ,. E d u c a t i o n aud

  17. 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.

  18. 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...

  19. 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.

  20. DOE Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria

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

    for DOE Facilities | Department of Energy Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria for DOE Facilities DOE Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria for DOE Facilities 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

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. Independent review of Oak Ridge HCTW test program and development of seismic evaluation criteria

    SciTech Connect (OSTI)

    1995-05-01

    Many of the existing buildings at the Oak Ridge Y-12 Plant are steel frame construction with unreinforced hollow clay tile infill walls (HCTW). The HCTW infill provides some lateral seismic resistance to the design/evaluation basis earthquake; however acceptance criteria for this construction must be developed. The basis for the development of seismic criteria is the Oak Ridge HCTW testing and analysis program and the target performance goals of DOE 5480.28 and DOE-STD-1020-94. This report documents and independent review of the testing and analysis program and development of recommended acceptance criteria for Oak Ridge HCTW construction. The HCTW test program included ``macro`` wall in-plane and out-of-plane tests, full-scale wall in-plane and out-of-plane tests, in-situ out-of-plane test, shake table tests, and masonry component tests.

  9. 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

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

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

    Refrigerators | Department of Energy 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

  11. 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

  12. 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.

  13. 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...

  14. 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...

  15. 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 (42 U.S.C. 8253 Subsection (f), Use of Energy and Water Efficiency ...

  16. 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...

  17. 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,...

  18. 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...

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

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

    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 ...

  20. 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...

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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)

  6. 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

  7. 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.

  8. Application Content and Evaluation Criteria/Process | Department...

    Office of Environmental Management (EM)

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

  9. 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.

  10. Department of Energy Announces Tougher Criteria for ENERGY STAR®...

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

    The Department of Energy projects that this new criteria could result in savings of over ... each year, equivalent to the amount of water that flows over Niagara Falls in four hours. ...

  11. Understanding seismic design criteria for Japanese Nuclear Power Plants

    SciTech Connect (OSTI)

    Park, Y.J.; Hofmayer, C.H.; Costello, J.F.

    1995-04-01

    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. Some key documents for understanding Japanese seismic design criteria are also listed with brief descriptions. The paper highlights the design criteria to determine the seismic demand and component capacity in comparison with U.S. criteria, the background studies which have led to the current Japanese design criteria, and a survey of current research activities. More detailed technical descriptions are presented on the development of Japanese shear wall equations, design requirements for containment structures, and ductility requirements.

  12. 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.

  13. Criteria for Evaluation of Nuclear Facility Training Programs

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

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

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. Fisk-based criteria to support validation of detection methods for drinking water and air.

    SciTech Connect (OSTI)

    MacDonell, M.; Bhattacharyya, M.; Finster, M.; Williams, M.; Picel, K.; Chang, Y.-S.; Peterson, J.; Adeshina, F.; Sonich-Mullin, C.; Environmental Science Division; EPA

    2009-02-18

    This report was prepared to support the validation of analytical methods for threat contaminants under the U.S. Environmental Protection Agency (EPA) National Homeland Security Research Center (NHSRC) program. It is designed to serve as a resource for certain applications of benchmark and fate information for homeland security threat contaminants. The report identifies risk-based criteria from existing health benchmarks for drinking water and air for potential use as validation targets. The focus is on benchmarks for chronic public exposures. The priority sources are standard EPA concentration limits for drinking water and air, along with oral and inhalation toxicity values. Many contaminants identified as homeland security threats to drinking water or air would convert to other chemicals within minutes to hours of being released. For this reason, a fate analysis has been performed to identify potential transformation products and removal half-lives in air and water so appropriate forms can be targeted for detection over time. The risk-based criteria presented in this report to frame method validation are expected to be lower than actual operational targets based on realistic exposures following a release. Note that many target criteria provided in this report are taken from available benchmarks without assessing the underlying toxicological details. That is, although the relevance of the chemical form and analogues are evaluated, the toxicological interpretations and extrapolations conducted by the authoring organizations are not. It is also important to emphasize that such targets in the current analysis are not health-based advisory levels to guide homeland security responses. This integrated evaluation of chronic public benchmarks and contaminant fate has identified more than 200 risk-based criteria as method validation targets across numerous contaminants and fate products in drinking water and air combined. The gap in directly applicable values is

  19. 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.

  20. 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.

  1. DOE-STD-1023-95; Natural Phenomena Hazards Assessment Criteria

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

    ... Criteria for the atmospheric pressure change and recommended windborne missiles are ... pressure change (APC) and tornado missiles) need to be considered based on criteria ...

  2. 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...

  3. 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.

  4. Accuracy-based time step criteria for solving parabolic equations

    SciTech Connect (OSTI)

    Mohtar, R.; Segerlind, L.

    1995-12-31

    Parabolic equations govern many transient engineering problems. Space integration using finite element or finite difference methods changes the parabolic partial differential equation into an ordinary differential equation. Time integration schemes are needed to solve the later equation. In order to accurately perform the later integration a proper time step must be provided. Time step estimates based on a stability criteria have been prescribed in the literature. The following paper presents time step estimates that satisfy stability as well as accuracy criteria. These estimates were correlated to the Froude and Courant Numbers. The later criteria were found to be overly conservative for some integration schemes. Suggestions as to which time integration scheme is the best to use are also presented.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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)

  11. Manual for the certification of laboratories analyzing drinking water. Criteria and procedures quality assurance (third edition)

    SciTech Connect (OSTI)

    Not Available

    1992-09-01

    Contents: introduction; responsibilities; implementation--(regional laboratories and programs; principal state laboratories; local laboratories; other considerations for certification; requirements for maintaining certification status; criteria and procedures for downgrading/revoking certification status; reciprocity; training; technical services; and alternate analytical techniques); chemistry--(personnel; laboratory facilities; laboratory equipment and instrumentation; general laboratory practices; analytical methodology; sample collection, handling, and preservation; quality assurance; records and data reporting; and action response to laboratory); microbiology--(personnel; laboratory facilities; laboratory equipment and instrumentation; general laboratory practices; analytical methodology; sample collection, handling, and preservation; quality assurance; records and data reporting; and action response to laboratory); radiochemistry--(personnel; laboratory facilities; laboratory equipment and instrumentation; general laboratory practices; analytical methodology; sample collection, handling, and preservation; quality assurance; records and data reporting; and action response to laboratory); appendices.

  12. 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

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. Functional design criteria 241-AP-102 Flexible Receiver System

    SciTech Connect (OSTI)

    Roblyer, S.P.

    1995-02-16

    A mixer pump was installed in the 1.07 m (42-in.) riser of the central pump pit of tank 241-AP-102 to mitigate potential fluid separation particle sedimentation by mixing the tank`s contents. The mixer pump performed this function until failure. Its removal is now necessary to meet possible tank content removal commitments or other corrective actions. The proposed removal procedure requires a flexible receiver that will provide a barrier to contamination during removal and transfer of the pump to the mixer pump storage container. This document describes the functional design criteria of the flexible receiver. These criteria include the functional and performance requirements of the flexible receiver as a barrier to contamination during normal conditions and contingencies and the instrumentation requirements.

  5. MCO combustible gas management leak test acceptance criteria

    SciTech Connect (OSTI)

    SHERRELL, D.L.

    1999-05-11

    Existing leak test acceptance criteria for mechanically sealed and weld sealed multi-canister overpacks (MCO) were evaluated to ensure that MCOs can be handled and stored in stagnant air without compromising the Spent Nuclear Fuel Project's overall strategy to prevent accumulation of combustible gas mixtures within MCO's or within their surroundings. The document concludes that the integrated leak test acceptance criteria for mechanically sealed and weld sealed MCOs (1 x 10{sup -5} std cc/sec and 1 x 10{sup -7} std cc/sec, respectively) are adequate to meet all current and foreseeable needs of the project, including capability to demonstrate compliance with the NFPA 60 Paragraph 3-3 requirement to maintain hydrogen concentrations [within the air atmosphere CSB tubes] t or below 1 vol% (i.e., at or below 25% of the LFL).

  6. 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.

  7. 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.

  8. Criteria for Evaluation of Nuclear Facility Training Programs

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

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

  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. 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.

  11. DOE Standard Natural Phenomena Hazards Site Characterization Criteria

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

    2-94 March 1994 Change Notice No. 1 January 1996 Reaffirmed with Errata April 2002 DOE STANDARD NATURAL PHENOMENA HAZARDS SITE CHARACTERIZATION CRITERIA U.S. Department of Energy AREA FACR Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Environment Safety and Health Technical Information Services, U.S. Department of

  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. 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.

  17. Criteria for Packaging and Storing Uranium-233-Bearing Materials

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

    3028-2000 July 2000 DOE STANDARD CRITERIA FOR PACKAGING AND STORING URANIUM-233-BEARING MATERIALS U.S. Department of Energy AREA SAFT 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, fax: (301) 903-9823. Available to the public from the U.S.

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

    Office of Environmental Management (EM)

    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) ...

  19. 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.

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

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

    | Department of Energy 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 criteria and guidelines for the Federal Energy and Water Management Awards. Download the 2016 Criteria and Guidelines document. (555.76 KB) More Documents & Publications Federal Energy and Water Management Awards: Frequently Asked Questions Federal Energy and Water Management Awards:

  1. Preliminary siting criteria for the proposed mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    SciTech Connect (OSTI)

    Jorgenson-Waters, M.

    1992-09-01

    The Mixed and Low-Level Waste Treatment Facility project was established in 1991 by the US Department of Energy Idaho Field Office. This facility will provide treatment capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This report identifies the siting requirements imposed on facilities that treat and store these waste types by Federal and State regulatory agencies and the US Department of Energy. Site selection criteria based on cost, environmental, health and safety, archeological, geological and service, and support requirements are presented. These criteria will be used to recommend alternative sites for the new facility. The National Environmental Policy Act process will then be invoked to evaluate the alternatives and the alternative sites and make a final site determination.

  2. Electrical and mechanical design criteria for EHV and UHV: overhead...

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

    Report Number(s): DOERA2133-01 DOE Contract Number: AC01-77ET29236 Resource Type: Technical Report Research Org: Main (Charles T.), Inc., Boston, MA (USA) Country of Publication: ...

  3. Rationale for wind-borne missile criteria for DOE facilities

    SciTech Connect (OSTI)

    McDonald, J R; Murray, R

    1999-09-01

    High winds tend to pick up and transport various objects and debris, which are referred to as wind-borne missiles or tornado missiles, depending on the type of storm. Missiles cause damage by perforating the building envelope or by collapsing structural elements such as walls, columns or frames. The primary objectives of this study are as follows: (1) to provide a basis for wind-borne or tornado missile criteria for the design and evaluation of DOE facilities, and (2) to provide guidelines for the design and evaluation of impact-resistant missile barriers for DOE facilities The first objective is accomplished through a synthesis of information from windstorm damage documentation experience and computer simulation of missile trajectories. The second objective is accomplished by reviewing the literature, which describes various missile impact tests, and by conducting a series of impact tests at a Texas Tech University facility to fill in missing information.

  4. 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.

  5. 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.

  6. 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.

  7. Design criteria Drain Rerouting Project 93-OR-EW-2

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This document contains the design criteria to be used by the architect-engineer (A--E) in the performance of Title I and II design for the Drain Rerouting Project. The Drain Rerouting project at the US Department of Energy`s (DOE) Oak Ridge Reservation in Oak Ridge, Tennessee will provide the Y-12 Plant with the capability to reroute particular drains within buildings 9202, 9203 and 9995. Process drains that are presently connected to the storm sewer shall be routed to the sanitary sewer to ensure that any objectionable material inadvertently discharged into process drains will not discharge to East Fork Popular Creek (EFPC) without treatment. The project will also facilitate compliance with the Y-12 Plant`s National Pollutant Discharge Elimination System (NPDES) discharge permit and allow for future pretreatment of once-through coolant.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. Performance objectives and criteria for conducting DOE environmental audits

    SciTech Connect (OSTI)

    1994-01-01

    This document contains the Performance Objectives and Criteria (POC) that have been developed for environmental audits and assessments conducted by the Office of the Assistant Secretary for Environment, Safety and Health. The Environmental POC can serve multiple purposes. Primarily, they are to serve as guidelines for the technical specialists conducted the audits and assessments, and for the team management. The POC can also serve as supporting documents for training of technical discipline specialists and Team Leaders and as bases for DOE programs and field offices and contractors conducting audit or assessment activities or improving environmental protection programs. It must be recognized that not all of the POC will necessarily apply to all DOE facilities. The users of this document must rely upon their knowledge of the facility and their professional judgment, or the judgment of qualified environmental professionals to determine the applicability of each POC. The POC cover eleven technical disciplines: air; surface water and drinking water quality; groundwater; waste management; toxic and chemical materials; radiation; quality assurance; inactive waste sites and releases; ecological and cultural resources; the National Environmental Policy Act (NEPA); and environmental management systems.

  14. 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

  15. Criteria for Selection of Seed Motions to Envelop Design Response Spectra

    Broader source: Energy.gov [DOE]

    Criteria for Selection of Seed Motions to Envelop Design Response Spectra DOE Natural Phenomena Hazards Workshop October 25, 2011 Michael Costantino, Thomas Houston, Greg Mertz, Andrew Maham

  16. DOE Publishes GATEWAY Report on Pedestrian Friendly Outdoor Lighting

    Broader source: Energy.gov [DOE]

    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 t

  17. DOE Publishes GATEWAY Report on Pedestrian Friendly Outdoor Lighting

    Broader source: Energy.gov [DOE]

    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...

  18. 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-

  19. TRU waste acceptance criteria for the Waste Isolation Pilot Plant: Revision 3

    SciTech Connect (OSTI)

    Not Available

    1989-01-01

    This document is intended to delineate the criteria by which unclassified waste will be accepted for emplacement at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico and describe the bases upon which these criteria were established. These criteria are not intended to be specifications but rather limits that will allow waste generating and shipping sites to develop their own procedures and specifications for preparation of TRU waste for shipment to the WIPP. These criteria will also allow waste generating sites to plan future facilities for waste preparation that will produce TRU waste forms compatible with WIPP waste emplacement and isolation requirements. These criteria only apply to contract-handled (CH) and remote-handled (RH) transuranic (TRU) waste forms and are not intended to apply to beta-gamma wastes, spent fuel, high-level waste (HLW), low-level waste (LLW), low specific activity (LSA) waste, or forms of radioactive waste for experimental purposes. Specifications for receipt of experimental waste forms will be prepared by the responsible projects in conjunction with the staff of the WIPP project at a later date. In addition, these criteria only apply to waste emplaced in bedded rock salt. Technical bases for these criteria may differ significantly from those for other host rocks. 25 refs. 4 figs., 1 tab.

  20. 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.

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

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

    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

  2. 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.

  3. 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...

  4. February 23, 2016 Webinar- Multi-Criteria Decisional Analyses: Methodology and Case Studies

    Broader source: Energy.gov [DOE]

    Performance & RIsk Assessment (P&RA) Community of 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).

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

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

    ... and vertical seismic loads. 7.3.3 In the design of sway bracing, the criteria of Section 4-6.4.3.5.2 (or current equivalent) of NFPA 13 (1994) should be revised as follows. ...

  6. 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.

  7. Fee Waiver and Reduction Criteria | U.S. DOE Office of Science (SC)

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

    Fee Waiver and Reduction Criteria Integrated Support Center (ISC) ISC Home About Services Freedom of Information Act (FOIA) Privacy Act Advisory Exemptions How to Submit a FOIA Request Fee Waiver and Reduction Criteria Electronic Reading Room ISC Conventional Reading Rooms Reference Links Privacy Act NEPA Documents Contact Information Integrated Support Center Roxanne Purucker U.S. Department of Energy 9800 S. Cass Avenue Argonne, IL 60439 P: (630) 252-2110 Kenneth Tarcza U.S. Department of

  8. 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.

  9. Preliminary/Sample Residential EE Loan Term Sheet and Underwriting Criteria

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

    (Appendix A of the Clean Energy Finance Guide, 3rd Edition) | Department of Energy Preliminary/Sample Residential EE Loan Term Sheet and Underwriting Criteria (Appendix A of the Clean Energy Finance Guide, 3rd Edition) Preliminary/Sample Residential EE Loan Term Sheet and Underwriting Criteria (Appendix A of the Clean Energy Finance Guide, 3rd Edition) Provides a sample or preliminary term sheet for single family residential energy efficiency loans. Author: Energy Efficiency Finance Corp.

  10. 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).

  11. Criteria for Selection of Seed Motions to Envelop Design Response Spectra

    Office of Environmental Management (EM)

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

  12. 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.

  13. 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.

  14. Alternative methods for dispoal of low-level radioactive wastes. Task 1. Description of methods and assessment of criteria. [Alternative methods are belowground vaults, aboveground vaults; earth mounded concrete bunkers, mined cavities, augered holes

    SciTech Connect (OSTI)

    Bennett, R.D.; Miller, W.O.; Warriner, J.B.; Malone, P.G.; McAneny, C.C.

    1984-04-01

    The study reported herein contains the results of Task 1 of a four-task study entitled Criteria for Evaluating Engineered Facilities. The overall objective of this study is to ensure that the criteria needed to evaluate five alternative low-level radioactive waste (LLW) disposal methods are available to the Nuclear Regulatory Commission (NRC) and the Agreement States. The alternative methods considered are belowground vaults, aboveground vaults, earth mounded concrete bunkers, mined cavities, and augered holes. Each of these alternatives is either being used by other countries for low-level radioactive waste (LLW) disposal or is being considered by other countries or US agencies. In this report the performance requirements are listed, each alternative is described, the experience gained with its use is discussed, and the performance capabilities of each method are addressed. Next, the existing 10 CFR Part 61 Subpart D criteria with respect to paragraphs 61.50 through 61.53, pertaining to site suitability, design, operations and closure, and monitoring are assessed for applicability to evaluation of each alternative. Preliminary conclusions and recommendations are offered on each method's suitability as an LLW disposal alternative, the applicability of the criteria, and the need for supplemental or modified criteria.

  15. 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.

  16. 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.

  17. 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

  18. 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.

  19. 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.

  20. 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.

  1. 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.

  2. Fuel Retrieval System Design Verification Report

    SciTech Connect (OSTI)

    GROTH, B.D.

    2000-04-11

    The Fuel Retrieval Subproject was established as part of the Spent Nuclear Fuel Project (SNF Project) to retrieve and repackage the SNF located in the K Basins. The Fuel Retrieval System (FRS) construction work is complete in the KW Basin, and start-up testing is underway. Design modifications and construction planning are also underway for the KE Basin. An independent review of the design verification process as applied to the K Basin projects was initiated in support of preparation for the SNF Project operational readiness review (ORR). A Design Verification Status Questionnaire, Table 1, is included which addresses Corrective Action SNF-EG-MA-EG-20000060, Item No.9 (Miller 2000).

  3. Impact of structural design criteria on first wall surface heat flux limit

    SciTech Connect (OSTI)

    Majumdar, S.

    1998-09-01

    The irradiation environment experienced by the in-vessel components of fusion reactors presents structural design challenges not envisioned in the development of existing structural design criteria such as the ASME Code or RCC-MR. From the standpoint of design criteria, the most significant issues stem from the irradiation-induced changes in material properties, specifically the reduction of ductility, strain hardening capability, and fracture toughness with neutron irradiation. Recently, Draft 7 of the ITER structural design criteria (ISDC), which provide new rules for guarding against such problems, was released for trial use by the ITER designers. The new rules, which were derived from a simple model based on the concept of elastic follow up factor, provide primary and secondary stress limits as functions of uniform elongation and ductility. The implication of these rules on the allowable surface heat flux on typical first walls made of type 316 stainless steel and vanadium alloys are discussed.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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...

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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

  19. 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

  20. 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 ...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. Financial News for Major Energy Companies

    Gasoline and Diesel Fuel Update (EIA)

    First Quarter 2006 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 (excluding

  7. 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

  8. Financial News for Major Energy Companies

    Gasoline and Diesel Fuel Update (EIA)

    Third 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-one 1 major energy companies reported overall net income (excluding

  9. 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

  10. Financial News for Major Energy Companies, Fourth Quarter 2006

    Gasoline and Diesel Fuel Update (EIA)

    6 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 do not provide separate information for the company's U.S. operations. Nineteen major energy companies 1 reported overall net income (excluding unusual

  11. Financial News for Major Energy Companies, July - September 2004

    Gasoline and Diesel Fuel Update (EIA)

    NEWS FOR MAJOR ENERGY COMPANIES The "Financial News for Major Energy Companies" is issued quarterly to report recent trends in the financial performance of the major energy companies, which 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-four major energy companies reported overall net income

  12. 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

  13. Financial News for Major Energy Companies, Second Quarter 2006

    Gasoline and Diesel Fuel Update (EIA)

    Second Quarter 2006 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 do not provide separate information for the company's U.S. operations. Twenty-one major energy companies 1 reported overall net income

  14. Financial News for Major Energy Companies, Third Quarter 2006

    Gasoline and Diesel Fuel Update (EIA)

    Third Quarter 2006 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 do not provide separate information for the company's U.S. operations. Twenty major energy companies 1 reported overall net income

  15. Wind turbine performance: Methods and criteria for reliability of measured power curves

    SciTech Connect (OSTI)

    Griffin, D.A.

    1996-12-31

    In order to evaluate the performance of prototype turbines, and to quantify incremental changes in performance through field testing, Advanced Wind Turbines (AWT) has been developing methods and requirements for power curve measurement. In this paper, field test data is used to illustrate several issues and trends which have resulted from this work. Averaging and binning processes, data hours per wind-speed bin, wind turbulence levels, and anemometry methods are all shown to have significant impacts on the resulting power curves. Criteria are given by which the AWT power curves show a high degree of repeatability, and these criteria are compared and contrasted with current published standards for power curve measurement. 6 refs., 5 figs., 5 tabs.

  16. 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.

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

    SciTech Connect (OSTI)

    Yu, K. Y.; Zhang, X.; Bufford, D.; Chen, Y.; Liu, Y.; Wang, H.

    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.

  18. 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.

  19. Regulatory analysis on criteria for the release of patients administered radioactive material

    SciTech Connect (OSTI)

    Schneider, S.; McGuire, S.A.; Behling, U.H.; Behling, K.; Goldin, D.

    1994-05-01

    The Nuclear Regulatory Commission (NRC) has received two petitions to amend its regulations in 10 CFR Parts 20 and 35 as they apply to doses received by members of the public exposed to patients released from a hospital after they have been administered radioactive material. While the two petitions are not identical they both request that the NRC establish a dose limit of 5 millisieverts (0.5 rem) per year for individuals exposed to patients who have been administered radioactive materials. This Regulatory Analysis evaluates three alternatives. Alternative 1 is for the NRC to amend its patient release criteria in 10 CFR 35.75 to use the more stringent dose limit of 1 millisievert per year in 10 CFR 20.1301(a) for its patient release criteria. Alternative 2 is for the NRC to continue using the existing patient release criteria in 10 CFR 35.75 of 1,110 megabecquerels of activity or a dose rate at one meter from the patient of 0.05 millisievert per hour. Alternative 3 is for the NRC to amend the patient release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts for patient release. The evaluation indicates that Alternative 1 would cause a prohibitively large increase in the national health care cost from retaining patients in a hospital longer and would cause significant personal and psychological costs to patients and their families. The choice of Alternatives 2 or 3 would affect only thyroid cancer patients treated with iodine-131. For those patients, Alternative 3 would result in less hospitalization than Alternative 2. Alternative 3 has a potential decrease in national health care cost of $30,000,000 per year but would increase the potential collective dose from released therapy patients by about 2,700 person-rem per year, mainly to family members.

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

    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.

  1. Design criteria for Waste Coolant Processing Facility and preliminary proposal 722 for Waste Coolant Processing Facility

    SciTech Connect (OSTI)

    Not Available

    1991-09-27

    This document contains the design criteria to be used by the architect-engineer (A-E) in the performance of Titles 1 and 2 design for the construction of a facility to treat the biodegradable, water soluble, waste machine coolant generated at the Y-12 plant. The purpose of this facility is to reduce the organic loading of coolants prior to final treatment at the proposed West Tank Farm Treatment Facility.

  2. Functional design criteria for project W-252, phase II liquid effluent treatment and disposal. Revision 2

    SciTech Connect (OSTI)

    Hatch, C.E.

    1995-05-01

    This document is the Functional Design Criteria for Project W-252. Project W-252 provides the scope to provide BAT/AKART (best available technology...) to 200 Liquid Effluent Phase II streams (B-Plant). This revision (Rev. 2) incorporates a major descoping of the project. The descoping was done to reflect a combination of budget cutting measures allowed by a less stringent regulatory posture toward the Phase II streams

  3. USE OF LEAD SHIELDING Nevada National Security Site Waste Acceptance Criteria (NNSSWAC)

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

    USE OF LEAD SHIELDING Nevada National Security Site Waste Acceptance Criteria (NNSSWAC) Container ID: Waste profile: NOTE: If dose rate is < 5 mrem/hr at 30 cm from the standard waste package, lead shielding is unacceptable. Dose rate of loaded waste package without lead shielding: mrem/hr @ 30 cm (attach calculations) Describe lead shielding: Basis for demonstrating lead is not excessive (attached calculations, e.g. Microshield analysis, or attach dose rate survey): Maximum lead shielded

  4. 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.

  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. 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.

  7. IDENTIFYING LUMINOUS ACTIVE GALACTIC NUCLEI IN DEEP SURVEYS: REVISED IRAC SELECTION CRITERIA

    SciTech Connect (OSTI)

    Donley, J. L.; Koekemoer, A. M.; Brusa, M.; Salvato, M.; Capak, P.; Cardamone, C. N.; Civano, F.; Ilbert, O.; Impey, C. D.; Kartaltepe, J. S.; Miyaji, T.; Sanders, D. B.; Trump, J. R.

    2012-04-01

    Spitzer/IRAC selection is a powerful tool for identifying luminous active galactic nuclei (AGNs). For deep IRAC data, however, the AGN selection wedges currently in use are heavily contaminated by star-forming galaxies, especially at high redshift. Using the large samples of luminous AGNs and high-redshift star-forming galaxies in COSMOS, we redefine the AGN selection criteria for use in deep IRAC surveys. The new IRAC criteria are designed to be both highly complete and reliable, and incorporate the best aspects of the current AGN selection wedges and of infrared power-law selection while excluding high-redshift star-forming galaxies selected via the BzK, distant red galaxy, Lyman-break galaxy, and submillimeter galaxy criteria. At QSO luminosities of log L{sub 2-10keV}(erg s{sup -1}) {>=}44, the new IRAC criteria recover 75% of the hard X-ray and IRAC-detected XMM-COSMOS sample, yet only 38% of the IRAC AGN candidates have X-ray counterparts, a fraction that rises to 52% in regions with Chandra exposures of 50-160 ks. X-ray stacking of the individually X-ray non-detected AGN candidates leads to a hard X-ray signal indicative of heavily obscured to mildly Compton-thick obscuration (log N{sub H} (cm{sup -2}) = 23.5 {+-} 0.4). While IRAC selection recovers a substantial fraction of luminous unobscured and obscured AGNs, it is incomplete to low-luminosity and host-dominated AGNs.

  8. 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.

  9. 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.

  10. 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.

  11. 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

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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).

  17. 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.

  18. Charges/Reports | U.S. DOE Office of Science (SC)

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

    Charges/Reports Biological and Environmental Research Advisory Committee (BERAC) BERAC Home Meetings Members Charges/Reports Current BERAC Charges Archive of BERAC Reports Charter .pdf file (135KB) BER Committees of Visitors Federal Advisory Committees BER Home Charges/Reports Print Text Size: A A A FeedbackShare Page A BERAC report .pdf file (1019KB) describing criteria and priorities for field-based BER research that capture a multi-disciplinary approach and build on observations and

  19. 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.

  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. 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.

  2. 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.

  3. 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.

  4. 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

  5. Multi-criteria analysis on how to select solar radiation hydrogen production system

    SciTech Connect (OSTI)

    Badea, G.; Naghiu, G. S. Felseghi, R.-A.; Giurca, I.; Răboacă, S.; Aşchilean, I.

    2015-12-23

    The purpose of this article is to present a method of selecting hydrogen-production systems using the electric power obtained in photovoltaic systems, and as a selecting method, we suggest the use of the Advanced Multi-Criteria Analysis based on the FRISCO formula. According to the case study on how to select the solar radiation hydrogen production system, the most convenient alternative is the alternative A4, namely the technical solution involving a hydrogen production system based on the electrolysis of water vapor obtained with concentrated solar thermal systems and electrical power obtained using concentrating photovoltaic systems.

  6. 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)

  7. 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...

  8. DNFSB 2002-1 Software Quality Assurance Improvement Plan Commitment 4.2.1.2: Safety Quality Assurance Plan and Criteria for the Safety Analysis Toolbox Codes

    Office of Environmental Management (EM)

    EH-4.2.1.2-Criteria Defense Nuclear Facilities Safety Board Recommendation 2002-1 Software Quality Assurance Improvement Plan Commitment 4.2.1.2: Software Quality Assurance Plan and Criteria for the Safety Analysis Toolbox Codes U.S. Department of Energy Office of Environment, Safety and Health 1000 Independence Ave., S.W. Washington, DC 20585-2040 November 2003 Software Quality Assurance Criteria for Safety Analysis Codes November 2003 INTENTIONALLY BLANK ii Software Quality Assurance Criteria

  9. 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.

  10. 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.

  11. 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.

  12. A multi-criteria decision analysis assessment of waste paper management options

    SciTech Connect (OSTI)

    Hanan, Deirdre; Burnley, Stephen; Cooke, David

    2013-03-15

    Highlights: ► Isolated communities have particular problems in terms of waste management. ► An MCDA tool allowed a group of non-experts to evaluate waste management options. ► The group preferred local waste management solutions to export to the mainland. ► Gasification of paper was the preferred option followed by recycling. ► The group concluded that they could be involved in the decision making process. - Abstract: The use of Multi-criteria Decision Analysis (MCDA) was investigated in an exercise using a panel of local residents and stakeholders to assess the options for managing waste paper on the Isle of Wight. Seven recycling, recovery and disposal options were considered by the panel who evaluated each option against seven environmental, financial and social criteria. The panel preferred options where the waste was managed on the island with gasification and recycling achieving the highest scores. Exporting the waste to the English mainland for incineration or landfill proved to be the least preferred options. This research has demonstrated that MCDA is an effective way of involving community groups in waste management decision making.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. Sanitary Landfill Groundwater Monitoring Report (Data Only) - First Quarter 1999

    SciTech Connect (OSTI)

    Chase, J.

    1999-05-26

    This report contains analytical data for samples taken during First Quarter 1999 from wells of the LFW series located at the Sanitary Landfill at the Savannah River Site (SRS). This report presents monitoring results that equaled or exceeded the Safe Drinking Water Act final Primary Drinking Water Standards or screening levels, established by the U.S. Environmental Proteciton Agency, the South Carolina final Primary Drinking Water Standard for lead, or the SRS flagging criteria.

  19. Technical Qualification Program Self-Assessment Report - Los Alamos Site

    Office of Environmental Management (EM)

    Office - 2007 | Department of Energy 07 Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2007 The Federal Technical Capability Manual requires periodic self-assessment of the effectiveness of the implementation of the Manual and the Technical Qualification Program utilizing a defined set of Objectives and Criteria. The assessment documented by this report is the first periodic review conducted at LASO to meet this requirement. The assessment results are

  20. 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

  1. AUDIT REPORT

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

    Audit Report on the "Management and Oversight of ... Project and Cold War through the production of plutonium. ... risks, the Richland Operations Office and the Office of ...

  2. 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...

  3. FINAL REPORT

    Office of Scientific and Technical Information (OSTI)

    FINAL REPORT Analytical and Elemental Analysis of Air and Soil Samples Facility and Public ... Information 4 Background 5 Stormwater Pollution 5 Erosion and Sediment Control Workshop ...

  4. AUDIT REPORT

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

    Washington, DC 20585 June 2, 2015 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report: "The Status of Cleanup at the ...

  5. AUDIT REPORT

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

    Activities at Y-12 include retrieving and storing nuclear materials, helping fuel the Nation's ... In June 2004, the Office of Inspector General's report on Management of the ...

  6. ASSESSMENT REPORT

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

    Inspector General SUBJECT: INFORMATION: Assessment Report on "Audit Coverage of Cost Allowability for Babcock & Wilcox Technical Services Pantex LLC During Fiscal Year 2013 ...

  7. SPECIAL REPORT

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

    public understanding of energy and its interaction with the economy and the environment. ... that the weekly and monthly data and statistics reported by EIA had been ...

  8. ASSESSMENT REPORT

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

    REPORT Audit Coverage of Cost Allowability for Lawrence Livermore National Security, LLC, ... 27, 2015 MEMORANDUM FOR THE MANAGER, LIVERMORE FIELD OFFICE FROM: David Sedillo, ...

  9. Corrective measures evaluation report for Tijeras Arroyo groundwater.

    SciTech Connect (OSTI)

    Witt, Johnathan L; Orr, Brennon R.; Dettmers, Dana L.; Hall, Kevin A.; Howard, M. Hope

    2005-08-01

    This Corrective Measures Evaluation report was prepared as directed by a Compliance Order on Consent issued by the New Mexico Environment Department to document the process of selecting the preferred remedial alternative for Tijeras Arroyo Groundwater. Supporting information includes background concerning the site conditions and potential receptors and an overview of work performed during the Corrective Measures Evaluation. The evaluation of remedial alternatives included identifying and describing four remedial alternatives, an overview of the evaluation criteria and approach, comparing remedial alternatives to the criteria, and selecting the preferred remedial alternative. As a result of the Corrective Measures Evaluation, monitored natural attenuation of the contaminants of concern (trichloroethene and nitrate) is the preferred remedial alternative for implementation as the corrective measure for Tijeras Arroyo Groundwater. Design criteria to meet cleanup goals and objectives and the corrective measures implementation schedule for the preferred remedial alternative are also presented.

  10. H-Area Acid/Caustic Basin groundwater monitoring report

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    During fourth quarter 1991, samples from the HAC monitoring wells at the H-Area Acid/Caustic Basin of Savannah River Plant were analyzed for indicator parameters, turbidity, major ions, volatile organic compounds, radionuclides, and other constituents. Monitoring results that exceeded the US Environmental Protection Agency primary drinking water standards (PDWS) and the Savannah River Site (SRS) flagging criteria and turbidity standards during the quarter, with summary results for the year, are the focus of this report. Tritium activities exceeded the PDWS in 4 wells. Iron and manganese exceeded Flag 2 criteria in 1 well, and specific conductance exceeded the Flag 2 criterion in well HAC 2. No priority pollutant (EPA, 1990) exceeded the PDWS or Flag 2 criteria in 2 wells. None of the HAC wells exceeded the SRS turbidity standard. Elevated tritium activities were found in all four HAC wells every quarter. Elevated total radium occurred in well HAC 2 during third quarter.

  11. OVERVIEW OF PRESSURE VESSEL DESIGN CRITERIA FOR INTERNAL DETONATION (BLAST) LOADING

    SciTech Connect (OSTI)

    T. A. DUFFEY; E. A. RODRIGUEZ

    2001-05-01

    Spherical and cylindrical pressure vessels are often used to completely contain the effects of high explosions. These vessels generally fall into two categories. The first includes vessels designed for multiple use ([1]-[6]). Applications of such multiple-use vessels include testing of explosive components and bomb disposal. Because of the multiple-use requirement, response of the vessel is restricted to the elastic range. The second category consists of vessels designed for one-time use only ([7]-[9]). Vessels in this category are typically used to contain accidental explosions and are designed to efficiently utilize the significant plastic energy absorption capacity of ductile materials. Because these vessels may undergo large permanent plastic deformations, they may not be reusable. Ideally one would design a Containment Vessel according to some National or International Consensus Standard, such as the ASME Boiler and Pressure Vessel Code. Unfortunately, however, a number of issues preclude direct use of the ASME Code in its present form to the design of Containment Vessels. These issues are described in Section 2, along with a request for guidance from the PVRC as to a suitable path forward for developing appropriate ASME B&PV design guidance for Containment Vessels. Next, a discussion of the nature of impulsive loading as a result of an internal detonation of the high explosive within a Containment Vessel is described in Section 3. Ductile failure criteria utilized for LANL Containment Vessels are described in Section 4. Finally, brittle fracture criteria currently utilized by LANL are presented in Section 5. This memo is concluded with a brief summary of results and an appeal to PVRC to recommend and develop an appropriate path forward (Section 6). This path forward could be of a short-term specialized nature (e.g., Code Case) for specific guidance regarding design of the LANL Containment Vessels; a long-term development of a general design approach

  12. 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.

  13. Synthesis of economic criteria in the design of electric utility industrial conservation programs in Costa Rica

    SciTech Connect (OSTI)

    Fisher, S.C.

    1995-12-31

    This paper lays out a set of economic criteria to guide the development of electricity conservation programs for industrial customers of the Costa Rican utilities. It puts the problem of utility and other public policy formulation in the industrial conservation field into the context of ongoing economic and trade liberalization in Costa Rica, as well as the financial and political pressures with which the country`s utilities must contend. The need to bolster utility financial performance and the perennial political difficulty of adjusting power rates for inflation and devaluation, not to mention maintaining efficient real levels, puts a premium on controlling the costs of utility conservation programs and increasing the degree of cost recovery over time. Industrial conservation programs in Costa Rica must adopt a certain degree of activation to help overcome serious market failures and imperfections while at the same time avoiding significant distortion of the price signals guiding the ongoing industrial rationalization process and the reactivation of growth.

  14. 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.

  15. 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.

  16. Functional design criteria for FY 1993-2000 groundwater monitoring wells

    SciTech Connect (OSTI)

    Williams, B.A.

    1996-01-01

    The purpose of this revision is to update the Line Item Project, 93-L-GFW-152 Functional Design Criteria (FDC) to reflect changes approved in change control M-24-91-6, Engineering Change Notices (ECNs), and expand the scope to include subsurface investigations along with the borehole drilling. This revision improves the ability and effectiveness of maintaining RCRA and Operational groundwater compliance by combining borehole and well drilling with subsurface data gathering objectives. The total projected number of wells to be installed under this project has decreased from 200 and the scope has been broadened to include additional subsurface investigation activities that usually occur simultaneously with most traditional borehole drilling and monitoring well installations. This includes borehole hydrogeologic characterization activities, and vadose monitoring. These activities are required under RCRA 40 CFR 264 and 265 and WAC 173-303 for site characterization, groundwater and vadose assessment and well placement.

  17. 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.

  18. Special Report

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

    Special Report 1501 MACY DRIVE ROSWELL, GA 30076 PH +1 770 642-7745 FX +1 770 643-2954 Impact of DOE Inventory Sales on the Nuclear Fuel Markets January | 2015 A PUBLICATION OF UXC.COM PREPARED FOR Cameco Corporation - NOTICE - The Ux Consulting Company, LLC ("UxC") shall have title to, ownership of, and all proprietary rights in this Report. Under United States federal copyright law (17 USC 101 et seq.) it is illegal to reproduce this Report by any means without written permission

  19. 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.

  20. Special Report

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

    Special Report 1501 MACY DRIVE ROSWELL, GA 30076 PH +1 770 642-7745 FX +1 770 643-2954 ... negative impact on the uranium spot price is projected to average about 14.1% per year. ...

  1. 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.

  2. 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.

  3. AUDIT REPORT

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

    Management of the Startup of the Sodium-Bearing Waste Treatment Facility DOE-OIG-16-09 ... SUBJECT: INFORMATION: Audit Report on "Management of the Startup of the Sodium-Bearing ...

  4. 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...

  5. SANDIA REPORT

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

    ... Reported By entries must exactly match user login IDs as contained in the XFRACAS System Wide Information template for each user (e.g., John Q. Doe"s SON login ID is 26 JQDOE). ...

  6. 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 ...

  7. SANDIA REPORT

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

    ... shear web; both on a 5-MW offshore wind turbine in the present report. Sensitivity analyses were carried out for the detection strategies of rotor imbalance and shear web disbond ...

  8. SUMMARY REPORT

    Energy Savers [EERE]

    SUMMARY REPORT Department of Energy's Implementation of Selected Controls as Defined in the Cybersecurity Act of 2015 DOE-OIG-16-14 August 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 August 4, 2016 MEMORANDUM FOR THE SECRETARY FROM: Rickey R. Hass Acting Inspector General SUBJECT: INFORMATION: Summary Report on the "Department of Energy's Implementation of Selected Controls as Defined in the

  9. 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

  10. 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.

  11. 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...

  12. 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

  13. 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

  14. 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.

  15. Final Report

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

    352 Regulatory and Utility Solutions to Advance SunShot Initiative Goals Interstate Renewable Energy Council, Inc. FINAL REPORT Project Title: "Regulatory and Utility Solutions to Advance SunShot Initiative Goals" Covering Period: 09/01/11 through 02/28/15 Date of Report: 04/20/2015 Recipient: Interstate Renewable Energy Council, Inc. (IREC) Award Number: DE-EE0005352 Working Partners: Keyes, Fox & Wiedman LLP Michael T. Sheehan Sherwood Associates, Inc. Kris Mayes Law Firm (KMLF)

  16. 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

  17. 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

  18. 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?

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

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

    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. 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.

  1. 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.

  2. 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.

  3. Creating a spatial multi-criteria decision support system for energy related integrated environmental impact assessment

    SciTech Connect (OSTI)

    Wanderer, Thomas Herle, Stefan

    2015-04-15

    By their spatially very distributed nature, profitability and impacts of renewable energy resources are highly correlated with the geographic locations of power plant deployments. A web-based Spatial Decision Support System (SDSS) based on a Multi-Criteria Decision Analysis (MCDA) approach has been implemented for identifying preferable locations for solar power plants based on user preferences. The designated areas found serve for the input scenario development for a subsequent integrated Environmental Impact Assessment. The capabilities of the SDSS service get showcased for Concentrated Solar Power (CSP) plants in the region of Andalusia, Spain. The resulting spatial patterns of possible power plant sites are an important input to the procedural chain of assessing impacts of renewable energies in an integrated effort. The applied methodology and the implemented SDSS are applicable for other renewable technologies as well. - Highlights: • The proposed tool facilitates well-founded CSP plant siting decisions. • Spatial MCDA methods are implemented in a WebGIS environment. • GIS-based SDSS can contribute to a modern integrated impact assessment workflow. • The conducted case study proves the suitability of the methodology.

  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. Characterization of Tank 23H Supernate Per Saltstone Waste Acceptance Criteria Analysis Requirements -2005

    SciTech Connect (OSTI)

    Oji, L

    2005-05-05

    Variable depth Tank 23H samples (22-inch sample [HTF-014] and 185-inch sample [HTF-013]) were pulled from Tank 23H in February, 2005 for characterization. The characterization of the Tank 23H low activity waste is part of the overall liquid waste processing activities. This characterization examined the species identified in the Saltstone Waste Acceptance Criteria (WAC) for the transfer of waste into the Salt-Feed Tank (SFT). The samples were delivered to the Savannah River National Laboratory (SRNL) and analyzed. Apart from radium-226 with an average measured detection limit of < 2.64E+03 pCi/mL, which is about the same order of magnitude as the WAC limit (< 8.73E+03 pCi/mL), none of the species analyzed was found to approach the limits provided in the Saltstone WAC. The concentration of most of the species analyzed for the Tank 23H samples were 2-5 orders of magnitude lower than the WAC limits. The achievable detection limits for a number of the analytes were several orders of magnitude lower than the WAC limits, but one or two orders of magnitude higher than the requested detection limits. Analytes which fell into this category included plutonium-241, europium-154/155, antimony-125, tin-126, ruthenium/rhodium-106, selenium-79, nickel-59/63, ammonium ion, copper, total nickel, manganese and total organic carbon.

  6. Characterization of Tank 23H Supernate Per Saltstone Waste Acceptance Criteria Analysis Requirements-2005

    SciTech Connect (OSTI)

    Oji, L

    2005-06-01

    Variable depth Tank 23H samples (22-inch sample [HTF-014] and 185-inch sample [HTF-013]) were pulled from Tank 23H in February, 2005 for characterization. The characterization of the Tank 23H low activity waste is part of the overall liquid waste processing activities. This characterization examined the species identified in the Saltstone Waste Acceptance Criteria (WAC) for the transfer of waste into the Salt-Feed Tank (SFT). The samples were delivered to the Savannah River National Laboratory (SRNL) and analyzed. Apart from radium-226 with an average measured detection limit of < 2.64E+03 pCi/mL, which is about the same order of magnitude as the WAC limit (< 8.73E+03 pCi/mL), none of the species analyzed was found to approach the limits provided in the Saltstone WAC. The concentration of most of the species analyzed for the Tank 23H samples were 2-5 orders of magnitude lower than the WAC limits. The achievable detection limits for a number of the analytes were several orders of magnitude lower than the WAC limits, but one or two orders of magnitude higher than the requested detection limits. Analytes which fell into this category included plutonium-241, europium-154/155, antimony-125, tin-126, ruthenium/rhodium-106, selenium-79, nickel-59/63, ammonium ion, copper, total nickel, manganese and total organic carbon.

  7. Criteria for optimization of recycling processes of primary and secondary copper

    SciTech Connect (OSTI)

    Dusts, S.; Piret, N.L.

    1995-12-31

    Primary and secondary copper smelting dusts are being generated in varying quantities with very dissimilar characteristics due to the different compositions of feed materials and the type of process utilized. After categorizing the multitude of dust types, the criteria for on-site and off-site recycling of smelter dust in terms of type and concentrations of the accompanying elements are established. Thereby, consideration is given to the important aspects of: optimization of copper recovery; quality of copper product; valorization of accompanying elements; elimination and disposal of deleterious impurities; minimization of impact on operation; effects on operating costs; and environmental impacts of dust treatment on overall process. Existing commercial, emerging and proposed copper smelting dusts, pyrometallurgical as well as hydrometallurgical, treatment schemes are reviewed and evaluated technically, economically and environmentally in an attempt to streamline the vast number of proposed options. Thereby, the high selectivity achievable in hydrometallurgical dust processing due to it being complementary to the smelting process, is expected to be given increased consideration. 81 refs., 11 figs., 11 tabs.

  8. 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.

  9. 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.

  10. 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

  11. 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.

  12. Technical basis and proposal for deriving sediment quality criteria for metals

    SciTech Connect (OSTI)

    Ankley, G.T.; Toro, D.M. di |; Hansen, D.J.; Berry, W.J.

    1996-12-01

    In developing sediment quality criteria (SQC) for metals, it is essential that bioavailability be a prime consideration. Different studies have shown that while dry weight metal concentrations in sediments are not predictive of bioavailability, metal concentrations in interstitial (pore) water are correlated with observed biological effects. A key partitioning phase controlling cationic metal activity and toxicity in the sediment-interstitial water system is acid-volatile sulfide (AVS). Acid-volatile sulfide binds, on a mole-to-mole basis, a number of cationic metals of environmental concern (cadmium, copper, nickel, lead, zinc) forming insoluble sulfide complexes with minimal biological availability. Short-term (10-d) laboratory studies with a variety of marine and freshwater benthic organisms have demonstrated that when AVS concentrations in spiked or field-collected sediments exceed those of metals simultaneously extracted with the AVS, interstitial water metal concentrations remain below those predicted to cause effects, and toxicity does not occur. Similar observations have been made in life-cycle laboratory toxicity tests with amphipods and chironomids in marine and freshwater sediments spiked with cadmium and zinc, respectively. In addition, field colonization experiments, varying in length from several months to more than 1 year, with cadmium- or zinc-spiked freshwater and marine sediments, have demonstrated a lack of biological effects when there is sufficient AVS to limit interstitial water metal concentrations. These studies on metal bioavailability and toxicity in sediments serve as the basis for proposed SQC for the metals cadmium, copper, nickel, lead, and zinc.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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."

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

    SciTech Connect (OSTI)

    Liu, Hu-Chen; Wu, Jing; Li, Ping

    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.

  19. 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.

  20. 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

  1. Multiple stakeholders in multi-criteria decision-making in the context of Municipal Solid Waste Management: A review

    SciTech Connect (OSTI)

    Soltani, Atousa; Hewage, Kasun; Reza, Bahareh; Sadiq, Rehan

    2015-01-15

    Highlights: • We review Municipal Solid Waste Management studies with focus on multiple stakeholders. • We focus on studies with multi-criteria decision analysis methods and discover their trends. • Most studies do not offer solutions for situations where stakeholders compete for more benefits or have unequal voting powers. • Governments and experts are the most participated stakeholders and AHP is the most dominant method. - Abstract: Municipal Solid Waste Management (MSWM) is a complicated process that involves multiple environmental and socio-economic criteria. Decision-makers look for decision support frameworks that can guide in defining alternatives, relevant criteria and their weights, and finding a suitable solution. In addition, decision-making in MSWM problems such as finding proper waste treatment locations or strategies often requires multiple stakeholders such as government, municipalities, industries, experts, and/or general public to get involved. Multi-criteria Decision Analysis (MCDA) is the most popular framework employed in previous studies on MSWM; MCDA methods help multiple stakeholders evaluate the often conflicting criteria, communicate their different preferences, and rank or prioritize MSWM strategies to finally agree on some elements of these strategies and make an applicable decision. This paper reviews and brings together research on the application of MCDA for solving MSWM problems with more focus on the studies that have considered multiple stakeholders and offers solutions for such problems. Results of this study show that AHP is the most common approach in consideration of multiple stakeholders and experts and governments/municipalities are the most common participants in these studies.

  2. Comparison Report

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

    Report 2009 Department of Energy Annual Employee Survey Results -vs- 2006 & 2008 All Federal Government Federal Human Capital Survey Results This is a summary-by-question of DOE's responses to the 2009 Annual Employee Survey compared to corresponding items on the 2006 and 2008 Federal Human Capital Surveys. This summary displays results by Positive, Neutral, Negative, and where applicable, Do Not Know or No Basis to Judge responses. As shown below, for each response scale two responses are

  3. SPECIAL REPORT

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

    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 Act) (5 U.S.C. 552) provides

  4. SPECIAL REPORT

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

    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

  5. 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

  6. AUDIT REPORT

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

    Implementation of the Department of Energy's CyberOne Initiative OAI-L-16-11 June 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 June 17, 2016 MEMORANDUM FOR THE CHIEF FINANCIAL OFFICER CHIEF INFORMATION OFFICER FROM: Sarah B. Nelson Assistant Inspector General for Audits and Administration Office of Inspector General SUBJECT: INFORMATION: Audit Report on the "Implementation of the Department of Energy's

  7. AUDIT REPORT

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

    the Office of Science's Management of the Isotope Program OAI-L-16-12 July 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 July 1, 2016 MEMORANDUM FOR THE DIRECTOR, OFFICE OF SCIENCE FROM: Sarah B. Nelson Assistant Inspector General for Audits and Administration Office of Inspector General SUBJECT: INFORMATION: Audit Report for the "Followup on the Office of Science's Management of the Isotope

  8. 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.

  9. 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

  10. 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

  11. SANDIA REPORT

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

    5630 Unlimited Release Printed June 2016 Site Environmental Report for 2015 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

  12. Final Report

    SciTech Connect (OSTI)

    Marchant, Gary E.

    2013-04-23

    This is the final report of a two year project entitled "Governing Nanotechnology Risks and Benefits in the Transition to Regulation: Innovative Public and Private Approaches." This project examined the role of new governance or "soft law" mechanisms such as codes of conduct, voluntary programs and partnership agreements to manage the risks of emerging technologies such as nanotechnology. A series of published or in publication papers and book chapters are attached.

  13. Report Template

    Office of Environmental Management (EM)

    (03-94) Replaces EIA-459B U.S. DEPARTMENT OF ENERGY FEDERAL ASSISTANCE MILESTONE PLAN OMB Control No. 1910-0400 Public reporting burden for this collection of information is estimated to average 1 hour per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of information. Send comments regarding this burden estimate or any other aspect of this collection of information,

  14. Annual Reports

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

    412 Archive Data (The EIA-412 survey has been terminated.) The EIA-412 "Annual Electric Industry Financial Report" collected information such as income statements, balance sheets, sales and purchases, and transmission line data. Form EIA-412 data Schedules Year 2 Electric Balance Sheet 3 Electric Income Statement 4 Electric Plant 5 Taxes, Tax Equivalents, Contributions, and Services During Year 6 Sales of Electricity for Resale (Account 447) 7 Electric Operation and Maintenance

  15. AUDIT REPORT

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

    Enriched Uranium Operations at the Y-12 National Security Complex DOE-OIG-16-13 July 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 July 14, 2016 MEMORANDUM FOR THE SECRETARY FROM: Rickey R. Hass Acting Inspector General SUBJECT: INFORMATION: Audit Report on "Enriched Uranium Operations at the Y-12 National Security Complex" BACKGROUND The Y-12 National Security Complex (Y-12) performs critical

  16. 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 technology'; while in US it is the techno- logy metals'. Unknown to most lay persons, these elements make possible the high-tech world we take for granted today - from electronics, medical technologies and novel green' energy solutions, to supporting a myriad of essential telecommunications and de- fence systems. These elements have come to be recognised as the vital cog in the world of technology owing to

  17. 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)

  18. Responses to Frequently Asked Questions on DOE O 232.2, Occurrence Reporting and Processing of Operations Information

    Broader source: Energy.gov [DOE]

    The intent of the Responses to Frequently Asked Questions (FAQ) on DOE O 232.2 is to provide additional insights for DOE facility personnel consideration and judgment when categorizing reportable occurrences in accordance with the Occurrence Reporting Criteria contained in DOE O 232.2.

  19. 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.

  20. 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.

  1. 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.

  2. Technical Qualification Program Self-Assessment Report - NNSA Production

    Office of Environmental Management (EM)

    Office - 2014 | Department of Energy NNSA Production Office - 2014 Technical Qualification Program Self-Assessment Report - NNSA Production Office - 2014 In preparation for the upcoming Chief for Defense Nuclear Safety (CDNS) review, a self-assessment of NNSA Production Office (NPO) oversight of the B&W Pantex Plant and the Y-12 National Security Complex was completed from October 2013 - January 2014. The scope included all available CDNS Criteria, Review, and Approach Documents (CRADS)

  3. 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)

  4. F-Area Acid/Caustic Basin groundwater monitoring report

    SciTech Connect (OSTI)

    Not Available

    1992-06-01

    During first 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 Primary Drinking Water Standards (PDWS) and the Savannah River Site flagging criteria and turbidity standards during the quarter are the focus of this report.

  5. ASSESSMENT REPORT

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

    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

  6. ASSESSMENT REPORT

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

    the University of California During Fiscal Years 2013 and 2014 Under Department of Energy Contract No. DE-AC02-05CH11231 OAI-V-16-10 June 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 June 28, 2016 MEMORANDUM FOR THE MANAGER, BERKELEY SITE OFFICE FROM: David Sedillo Deputy Assistant Inspector General for Audits and Inspections Office of Inspector General SUBJECT: INFORMATION: Assessment Report on "Audit

  7. 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

  8. 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.

  9. ASSESSMENT REPORT

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

    UT-Battelle LLC During Fiscal Year 2014 Under Department of Energy Contract No. DE-AC05-00OR22725 OAI-V-16-11 July 2016 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 July 29, 2016 MEMORANDUM FOR THE MANAGER, OAK RIDGE NATIONAL LABORATORY SITE OFFICE FROM: Debra K. Solmonson Deputy Assistant Inspector General for Audits and Inspections Office of Inspector General SUBJECT: INFORMATION: Assessment Report on the

  10. Final report

    SciTech Connect (OSTI)

    Dutta, Pulak

    2013-04-01

    The overall goal of this project was the exploration of new ways to make organic and hybrid (organic-inorganic) materials for energy-related applications. Towards this end, our research focused on the structure and behavior of molecular monolayers at interfaces (including floating monolayers, transferred Langmuir-Blodgett monolayers, and self-assembled monolayers), as well as the biomimetic nucleation of inorganic crystals at soft-hard interfaces. The project resulted in a number of 'firsts' and other notable achievements, which are described in the report.

  11. 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

  12. 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).

  13. 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.

  14. Spent Nuclear Fuel (SNF) Project Acceptance Criteria for Light Water Reactor Spent Fuel Storage System [OCRWM PER REV2

    SciTech Connect (OSTI)

    JOHNSON, D.M.

    2000-12-20

    As part of the decommissioning of the 324 Building Radiochemical Engineering Cells there is a need to remove commercial Light Water Reactor (LWR) spent nuclear fuel (SNF) presently stored in these hot cells. To enable fuel removal from the hot cells, the commercial LWR SNF will be packaged and shipped to the 200 Area Interim Storage Area (ISA) in a manner that satisfies site requirements for SNF interim storage. This document identifies the criteria that the 324 Building Radiochemical Engineering Cell Clean-out Project must satisfy for acceptance of the LWR SNF by the SNF Project at the 200 Area ISA. In addition to the acceptance criteria identified herein, acceptance is contingent on adherence to applicable Project Hanford Management Contract requirements and procedures in place at the time of work execution.

  15. 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).

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

    Office of Environmental Management (EM)

    8 AUDIT REPORT THE COST REDUCTION INCENTIVE PROGRAM AT THE SAVANNAH RIVER SITE U.S. DEPARTMENT OF ENERGY OFFICE OF INSPECTOR GENERAL OFFICE OF AUDIT SERVICES May 1998 ER-B-98-08 Overview Introduction and Objective .........................................................1 Observations and Conclusions.................................................. 3 Response to Internal Assessment Details of Finding ......................................................................4 Recommendations and

  17. 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...

  18. 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.

  19. 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.

  20. Report on reports: nuclear energy

    SciTech Connect (OSTI)

    Darmstadter, J.

    1982-11-01

    A joint report by the Nuclear Energy Agency (of the OECD) and the International Energy Agency, nuclear energy prospects to 2000 surveys the factors shaping the future of nuclear power in the 24-country OECD grouping, 13 of whom were operating nuclear power plants as of the end of 1981. Among the factors reviewed are the long-term economic outlook and its effect on total energy consumption, the role of electricity within aggregate energy use, and the economic and policy determinants governing nuclear's future contribution to electric power capacity and generation. The way in which public confidence bears on the nuclear outlook is mentioned as one of the considerations in the policy process, but this is given rather short shrift for an issue which many feel to be at the heart of the present-day nuclear power dilemma. The report describes areas in which nuclear power could offer notable advantages: 1) competitive electricity costs; 2) resource adequacy; 3) security of supply; and 4) environmental integrity. (JMT)

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. H-Area Acid/Caustic Basin groundwater monitoring report, third quarter 1992

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    During third quarter 1992, samples from the four HAC monitoring wells at the H-Area Acid/Caustic Basin received comprehensive analyses. Monitoring results that exceeded the US Environmental Protection Agency's Primary Drinking Water Standards (PDWS) or the Savannah River Site (SRS) flagging criteria or turbidity standards during the quarter are the focus of this report.

  6. Commercial Vehicle Safety Alliance (CVSA)/Department of Energy (DOE) cooperative agreement final report

    SciTech Connect (OSTI)

    Slavich, Antoinette; Daust, James E.

    1999-10-01

    This S and T product is a culmination of the activities, including research of the Commercial Vehicle Safety Alliance (CVSA) in developing and implementing inspection procedures and the out-of-service criteria for states and tribes to use when inspecting HRCQ and Transuranic shipments of radioactive materials. The report also contains the results of a pilot study to test the procedures.

  7. FY 2013 Reports - Hanford Site

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

    Impact Statements Environmental Management Performance Reports FY 2016 Reports FY 2015 Reports FY 2014 Reports FY 2013 Reports FY 2012 Reports FY 2011 Reports FY 2010 ...

  8. FY 2011 Reports - Hanford Site

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

    Impact Statements Environmental Management Performance Reports FY 2016 Reports FY 2015 Reports FY 2014 Reports FY 2013 Reports FY 2012 Reports FY 2011 Reports FY 2010 ...

  9. FY 2016 Reports - Hanford Site

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

    Impact Statements Environmental Management Performance Reports FY 2016 Reports FY 2015 Reports FY 2014 Reports FY 2013 Reports FY 2012 Reports FY 2011 Reports FY 2010 ...

  10. FY 2015 Reports - Hanford Site

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

    Impact Statements Environmental Management Performance Reports FY 2016 Reports FY 2015 Reports FY 2014 Reports FY 2013 Reports FY 2012 Reports FY 2011 Reports FY 2010 ...

  11. FY 2014 Reports - Hanford Site

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

    Impact Statements Environmental Management Performance Reports FY 2016 Reports FY 2015 Reports FY 2014 Reports FY 2013 Reports FY 2012 Reports FY 2011 Reports FY 2010 ...

  12. FY 2012 Reports - Hanford Site

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

    Impact Statements Environmental Management Performance Reports FY 2016 Reports FY 2015 Reports FY 2014 Reports FY 2013 Reports FY 2012 Reports FY 2011 Reports FY 2010 ...

  13. FY 2010 Reports - Hanford Site

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

    Impact Statements Environmental Management Performance Reports FY 2016 Reports FY 2015 Reports FY 2014 Reports FY 2013 Reports FY 2012 Reports FY 2011 Reports FY 2010 ...

  14. 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).

  15. 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.

  16. 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.

  17. Final report

    SciTech Connect (OSTI)

    Joseph H. Simmons; Tracie J. Bukowski

    2002-08-07

    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.

  18. 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.

  19. 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.

  20. 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.

  1. MONTICELLO PROJECTS FEDERAL FACILITIES AGREEMENT REPORT Report...

    Office of Legacy Management (LM)

    PROJECTS FEDERAL FACILITIES AGREEMENT REPORT Report Period: January 1- March 31, 2006 DOE Project Coordinator: Ray Plieness HIGHLIGHTS The Federal Facilities Agreement meeting was ...

  2. Biogas Opportunities Roadmap Progress Report (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    Biogas Opportunities Roadmap Progress Report Citation Details In-Document Search Title: Biogas Opportunities Roadmap Progress Report In support of the Obama Administration's ...

  3. 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.

  4. 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.

  5. 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.

  6. 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

  7. H-area acid/caustic basin groundwater monitoring report

    SciTech Connect (OSTI)

    Thompson, C.Y.

    1992-06-01

    During first quarter 1992, samples from the four HAC monitoring wells at the H-Area Acid/Caustic Basin of Savannah River Plant 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 Primary Drinking Water Standards (PDWS) and the Savannah River Site (SRS) flagging criteria and turbidity standards during the quarter are the focus of this report. Tritium exceeded the PDWS in HAC 1, 2, 3, and 4 during first quarter 1992. Tritium activities in upgradient well HAC 4 appeared similar to tritium levels in well HAC 1, 2, and 3. Specific conductance and manganese exceeded Flag 2 criteria in wells HAC 2 and 3, respectively. No well samples exceeded the SRS turbidity standard.

  8. 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 ...

  9. Multi-criteria evaluation in strategic environmental assessment for waste management plan, a case study: The city of Belgrade

    SciTech Connect (OSTI)

    Josimović, Boško Marić, Igor; Milijić, Saša

    2015-02-15

    Highlights: • The paper deals with the specific method of multi-criteria evaluation applied in drafting the SEA for the Belgrade WMP. • MCE of the planning solutions, assessed according to 37 objectives of the SEA and four sets of criteria, was presented in the matrix form. • The results are presented in the form of graphs so as to be easily comprehensible to all the participants in the decision-making process. • The results represent concrete contribution proven in practice. - Abstract: Strategic Environmental Assessment (SEA) is one of the key instruments for implementing sustainable development strategies in planning in general; in addition to being used in sectoral planning, it can also be used in other areas such as waste management planning. SEA in waste management planning has become a tool for considering the benefits and consequences of the proposed changes in space, also taking into account the capacity of space to sustain the implementation of the planned activities. In order to envisage both the positive and negative implications of a waste management plan for the elements of sustainable development, an adequate methodological approach to evaluating the potential impacts must be adopted and the evaluation results presented in a simple and clear way, so as to allow planners to make relevant decisions as a precondition for the sustainability of the activities planned in the waste management sector. This paper examines the multi-criteria evaluation method for carrying out an SEA for the Waste Management Plan for the city of Belgrade (BWMP). The method was applied to the evaluation of the impacts of the activities planned in the waste management sector on the basis of the environmental and socioeconomic indicators of sustainability, taking into consideration the intensity, spatial extent, probability and frequency of impact, by means of a specific planning approach and simple and clear presentation of the obtained results.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. Weekly Petroleum Status Report

    Gasoline and Diesel Fuel Update (EIA)

    Please go to the redesigned Weekly Petroleum Status Report.

  17. 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 Lynea Koshar 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

  18. 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.

  19. 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.

  20. EM Landfill Workshop Report - November 21, 2008

    Office of Environmental Management (EM)

    ... He developed WACFACS - the Waste Acceptance Criteria Forecasting and Analysis Capability ... responsible improving operational safety, costs, and schedule for decommissioning, ...

  1. 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.

  2. 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.

  3. 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.

  4. Aerodynamic Design Criteria for Class 8 Heavy Vehicles Trailer Base Devices to Attain Optimum Performance

    SciTech Connect (OSTI)

    Salari, K; Ortega, J

    2010-12-13

    Lawrence Livermore National Laboratory (LLNL) as part of its Department of Energy (DOE), Energy Efficiency and Renewable Energy (EERE), and Vehicle Technologies Program (VTP) effort has investigated class 8 tractor-trailer aerodynamics for many years. This effort has identified many drag producing flow structures around the heavy vehicles and also has designed and tested many new active and passive drag reduction techniques and concepts for significant on the road fuel economy improvements. As part of this effort a database of experimental, computational, and conceptual design for aerodynamic drag reduction devices has been established. The objective of this report is to provide design guidance for trailer base devices to improve their aerodynamic performance. These devices are commonly referred to as boattails, base flaps, tail devices, and etc. The information provided here is based on past research and our most recent full-scale experimental investigations in collaboration with Navistar Inc. Additional supporting data from LLNL/Navistar wind tunnel, track test, and on the road test will be published soon. The trailer base devices can be identified by 4 flat panels that are attached to the rear edges of the trailer base to form a closed cavity. These devices have been engineered in many different forms such as, inflatable and non-inflatable, 3 and 4-sided, closed and open cavity, and etc. The following is an in-depth discussion with some recommendations, based on existing data and current research activities, of changes that could be made to these devices to improve their aerodynamic performance. There are 6 primary factors that could influence the aerodynamic performance of trailer base devices: (1) Deflection angle; (2) Boattail length; (3) Sealing of edges and corners; (4) 3 versus 4-sided, Position of the 4th plate; (5) Boattail vertical extension, Skirt - boattail transition; and (6) Closed versus open cavity.

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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.

  11. 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.

  12. 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

  13. K-Area Acid/Caustic Basin groundwater monitoring report

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    During fourth quarter 1991, samples from the KAC monitoring wells at the K-Area Acid/Caustic Basin of Savannah River Plant were analyzed for indicator parameters, turbidity, major ions, volatile organic compounds, radionuclides, and other constituents. Monitoring results that exceeded the US Environmental Protection Agency Primary Drinking Water Standards (PDWS) and the Savannah River Site (SRS) flagging criteria and turbidity standards during the quarter, with summary results for the year, are presented in this report. No constituents exceeded the PDWS at the K-Area Acid/Caustic Basin. Iron and total organic halogens exceeded Flag 2 criteria in sidegradient-to-downgradient well KAC 7 but not in other KAC wells. No priority pollutants (EPA, 1990) exceeded the PDWS or the Flag 2 criteria in wells KAC 1 and 3. None of the KAC wells exceeded the SRS turbidity standard. Lead exceeded the PDWS in well KAC 7 during first quarter. No other constituent exceeded the PDWS at the K-Area Acid/Caustic Basin during the year.

  14. 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 2015AnnualReportcover NERSC Annual Report 2015 Download Image: 2015AnnualReportcover.png | png | 542 KB Download File: 2015NERSCAnnualReportFinal.pdf | pdf | 4.8 MB 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:

  15. 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.

  16. 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)].

  17. 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 ...

  18. EIR Report Template

    Office of Environmental Management (EM)

    Report Template An EIR typically results in both a Draft and Final EIR Report. Where follow-up actions are required, a Corrective Action Plan (CAP) Review Report and Addendum to ...

  19. 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 ...

  20. 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.

  1. Pulsed power peer review committee report.

    SciTech Connect (OSTI)

    Not Available

    2004-08-01

    As part of meeting the GRPA (Government Performance and Results Act) requirements and to provide input to Sandia's annual Performance Evaluation Assessment Report (PEAR) to the National Nuclear Security Administration in FY2004, a 14-member external review committee chaired by Dr. Alvin Trivelpiece was convened by Sandia National Laboratories (SNL) on May 4-6, 2004 to review Sandia National Laboratories' Pulsed Power Programs. The scope of the review included activities in high energy density physics (HEDP), inertial confinement fusion (ICF), radiation/weapon physics, the petawatt laser initiative (PW) and fast ignition, equation-of state studies, radiation effects science and lethality, x-ray radiography, ZR development, basic research and pulsed power technology research and development, as well as electromagnetics and work for others. In his charge to the Committee, Dr. Jeffrey P. Quintenz, Director of Pulsed Power Sciences (Org. 1600) asked that the evaluation and feedback be based on three criteria: (1) quality of technical activities in science, technology, and engineering, (2) programmatic performance, management, and planning, and (3) relevance to national needs and agency missions. In addition, the director posed specific programmatic questions. The accompanying report, produced as a SAND document, is the report of the Committee's finding.

  2. 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

  3. 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 materials and 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

  4. 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.

  5. K-Area Acid/Caustic Basin groundwater monitoring report

    SciTech Connect (OSTI)

    Thompson, C.Y.

    1992-09-01

    During second quarter 1992, samples from the seven older KAC monitoring wells at the K-Area Acid/Caustic Basin were analyzed for herbicides, indicator parameters, major ions, pesticides, radionuclides, turbidity, and other constituents. New wells FAC 8 and 9 received the first of four quarters of comprehensive analyses and GC/MS VOA (gas chromatograph/ mass spectrometer volatile organic analyses). Monitoring results that exceeded the US Environmental Protection Agency's Primary Drinking Water Standards (PDWS) or the Savannah River Site (SRS) flagging criteria or turbidity standards during the quarter are discussed in this report.

  6. 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).

  7. 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.

  8. Reporting | Department of Energy

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

    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 ...

  9. Annual Performance Report

    Office of Legacy Management (LM)

    Department of Energy Annual Performance Report, Shiprock, New Mexico October 2014 Doc. ... 25 Annual Performance Report, Shiprock, New Mexico U.S. Department of Energy Doc. No. ...

  10. 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, ...

  11. 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 ...

  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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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,...

  18. 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...

  19. 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.

  20. Technical evaluation panel summary report. Ceramic and glass immobilization options fissile materials disposition program

    SciTech Connect (OSTI)

    Myers, B. R.; Brummond, W.; Armantrout, G.; Shaw, H.; Jantzen, C. M.; Jostons, A.; McKibben, M.; Strachan, D.; Vienna, J. D.

    1997-12-23

    This report documents the results of a technical evaluation of the merits of ceramic and glass immobilization forms for the disposition of surplus weapons-useable plutonium. The evaluation was conducted by a Technical Evaluation Panel (TEP), whose members were selected to cover a relevant range of scientific and technical expertise and represented each of the technical organizations involved in the Plutonium Immobilization Program. The TEP held a formal review at Lawrence Liver-more National Laboratory (LLNL) from July 2%August 1, 1997. Following this review, the TEP documented the review and its evaluation of the two immobilization technologies in this report to provide a technical basis for a recommendation by LLNL to the Department of Energy (DOE) for the preferred immobilization form. The comparison of the glass and ceramic forms and manufacturing processes was a tremendous challenge to the TEP. The two forms and their processes are similar in many ways. The TEP went to great effort to accurately assess what were, in many cases, fine details of the processes, unit operations, and the glass and ceramic forms themselves. The set of criteria used by the Fissile Materials Disposition Program (FMDP) in past screenings and down-selections was used to measure-the two options. One exception is that the TEP did not consider criteria that were largely nontechnical (namely international impact, public acceptance, and effects on other : DOE programs). The TEP' s measures and assessments are documented in detail. Care was taken to ensure that the data used were well documented and traceable to their source. Although no final conclusion regarding the preferred form was reached or explicitly stated in this report (this was not within the TEP' s charter), no "show stoppers" were identified for either form. Both forms appear capable of satisfying all the criteria, as interpreted by the TEP. The TEP identified a number of distinct and quantifiable differences between the forms

  1. 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.

  2. 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

  3. 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.

  4. 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.

  5. STEP Participant Survey Report

    Broader source: Energy.gov [DOE]

    STEP Participant Survey Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  6. 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

  7. 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.

  8. STEP Program Benchmark Report

    Broader source: Energy.gov [DOE]

    STEP Program Benchmark Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  9. Weekly Petroleum Status Report

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    34 A. The Energy Information ... Petroleum Supply Reporting System ......importers, exporters, bulk storage terminals, and pipelines. ...

  10. Inspection Report: IG-0778

    Broader source: Energy.gov [DOE]

    Inspection Report on The Consolidated Terrorism Watchlist Nomination Process at the Department of Energy

  11. Quarterly Progress Report

    Broader source: Energy.gov [DOE]

    Quarterly Progress Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  12. 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

  13. 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.

  14. 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

  15. 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 NOv

  16. 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

  17. ARM - Reporting Requirements

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

    StatisticsReporting Requirements 2016 Quarterly Reports First Quarter (PDF) Second Quarter (PDF) Third Quarter (PDF) Fourth Quarter (PDF) Past Quarterly Reports Historical Statistics Field Campaigns Operational Visitors and Accounts Data Archive and Usage (October 1995 - Present) Reporting Requirements As a matter of government policy, all U.S. Department of Energy user facilities, including the ARM Climate Research Facility, have a number of reporting requirements. The Facility is required to

  18. 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

  19. 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

  20. Technical Consultant Report Template

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

    TECHNICAL CONSULTING REPORT Page 1 of 1 Report Date Report By: Homeowner Address Consult Type & Date(s) Email / Telephone In Person Purpose(s) of Meeting (generally) Service(s) Undertaken Observations Recommendations a. Visual Inspection Attic Basement / Crawlspace Equipment Other b. Diagnostic Testing Blower Door Combustion Testing Other c. Written Materials Review Audit Report Proposal Other d. Other NOTE: This Report was prepared at the request of the Homeowner, based on information