WorldWideScience

Sample records for 94-4 interim measures

  1. Burn site groundwater interim measures work plan.

    Energy Technology Data Exchange (ETDEWEB)

    Witt, Jonathan L. (North Wind, Inc., Idaho Falls, ID); Hall, Kevin A. (North Wind, Inc., Idaho Falls, ID)

    2005-05-01

    This Work Plan identifies and outlines interim measures to address nitrate contamination in groundwater at the Burn Site, Sandia National Laboratories/New Mexico. The New Mexico Environment Department has required implementation of interim measures for nitrate-contaminated groundwater at the Burn Site. The purpose of interim measures is to prevent human or environmental exposure to nitrate-contaminated groundwater originating from the Burn Site. This Work Plan details a summary of current information about the Burn Site, interim measures activities for stabilization, and project management responsibilities to accomplish this purpose.

  2. 7 CFR 94.4 - Analytical methods.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 94.4 Section 94.4 Agriculture... POULTRY AND EGG PRODUCTS Mandatory Analyses of Egg Products § 94.4 Analytical methods. The majority of analytical methods used by the USDA laboratories to perform mandatory analyses for egg products are listed...

  3. Effectiveness Monitoring Report, MWMF Tritium Phytoremediation Interim Measures.

    Energy Technology Data Exchange (ETDEWEB)

    Hitchcock, Dan; Blake, John, I.

    2003-02-10

    This report describes and presents the results of monitoring activities during irrigation operations for the calendar year 2001 of the MWMF Interim Measures Tritium Phytoremediation Project. The purpose of this effectiveness monitoring report is to provide the information on instrument performance, analysis of CY2001 measurements, and critical relationships needed to manage irrigation operations, estimate efficiency and validate the water and tritium balance model.

  4. SWSA 6 interim corrective measures environmental monitoring: FY 1991 results

    International Nuclear Information System (INIS)

    In 1988, interim corrective measures (ICMs) were implemented at Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory. The SWSA 6 site was regulated under the Resource Conservation and Recovery Act (RCRA). The ICMs consist of eight large high-density polyethylene sheets placed as temporary caps to cover trenches known to contain RCRA-regulated materials. Environmental monitoring for FY 1991 consisted of collecting water levels at 13 groundwater wells outside the capped areas and 44 wells in or near the capped areas in order to identify any significant loss of hydrologic isolation of the wastes. Past annual reports show that the caps are only partially effective in keeping the waste trenches dry and that many trenches consistently or intermittently contain water

  5. SWSA 6 interim corrective measures environmental monitoring: FY 1991 results

    Energy Technology Data Exchange (ETDEWEB)

    Clapp, R.B.; Marshall, D.S.

    1992-06-01

    In 1988, interim corrective measures (ICMs) were implemented at Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory. The SWSA 6 site was regulated under the Resource Conservation and Recovery Act (RCRA). The ICMs consist of eight large high-density polyethylene sheets placed as temporary caps to cover trenches known to contain RCRA-regulated materials. Environmental monitoring for FY 1991 consisted of collecting water levels at 13 groundwater wells outside the capped areas and 44 wells in or near the capped areas in order to identify any significant loss of hydrologic isolation of the wastes. Past annual reports show that the caps are only partially effective in keeping the waste trenches dry and that many trenches consistently or intermittently contain water.

  6. Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, Operable Unit No. 2

    International Nuclear Information System (INIS)

    The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This IM/IRAP/EA identifies and evaluates interim remedial actions for removal of residual free-phase VOC contamination from three different subsurface environments at OU2. The term ''residual'' refers to the non-aqueous phase contamination remaining in the soil matrix (by capillary force) subsequent to the passage of non-aqueous or free-phase liquid through the subsurface. In addition to the proposed actions, this IM/IRAP/EA presents an assessment of the No Action Alternative. This document also considers an interim remedial action for the removal of radionuclides from beneath the 903 Pad

  7. Interim measure work plan/design for Agra, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2008-11-18

    This Interim Measure Work Plan/Design (IMWP/D) is supplemental to the Argonne document Interim Measure Conceptual Design for Remediation of Source Area Contamination at Agra, Kansas. The IMWP/D includes information required by Kansas Department of Health and Environment (KDHE) Policy BER-RS-029, Policy and Scope of Work for Interim Measures. Specific to Policy BER-RS-029 is the requirement for several documents that will ensure that an adequate amount and type of data are collected for implementation of the IMWP/D and that data quality and safe conditions are prevailed. Such information is included in the IMWP/D as follows: Appendix A: Data Acquisition Plan--Design Testing Requirements; Appendix B: Basis of Design; Appendix C: Permits; Appendix D: Quality Assurance Project Plan; Appendix E: Health and Safety Plan; and Appendix F: Operations, Maintenance, and Monitoring Schedule. The proposed remedial technology for this project is the installation of five large-diameter boreholes (LDBs) in a source area that has been identified on the property formerly used for grain storage by the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA). The goal of the LDB technology is the remediation of the source area by removal of mass quantities of contaminated soil from the vadose zone and treatment of any remaining contaminated soils that are adjacent to the source area to achieve a carbon tetrachloride concentration below 200 {micro}g/kg. Secondary to the soil remediation is the remediation of groundwater at and adjacent to the source areas. The LDB technology serves the following purposes: (1) The physical removal of contaminated soil from the identified source area. (2) Replacement of less permeable native materials (silty clay, clayey silt, and silty sand) with more permeable materials to facilitate the capture of volatilized contaminants in the vertical borehole. (3) Removal of contaminants volatilized by air sparging (AS) and extracted from the

  8. SWSA 6 interim corrective measures environmental monitoring: FY 1990 results

    Energy Technology Data Exchange (ETDEWEB)

    Ashwood, T.L.; Spalding, B.P.

    1991-07-01

    This report presents the results and conclusions from a multifaceted monitoring effort associated with the high-density polyethylene caps installed in Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory (ORNL) as an interim corrective measure (ICM). The caps were installed between November 1988 and June 1989 to meet Resource Conservation and Recovery Act (RCRA) requirements for closure of those areas of SWSA 6 that had received RCRA-regulated wastes after November 1980. Three separate activities were undertaken to evaluate the performance of the caps: (1) wells were installed in trenches to be covered by the caps, and water levels in these intratrench wells were monitored periodically; (2) samples were taken of the leachate in the intratrench wells and were analyzed for a broad range of radiological and chemical contaminants; and (3) water levels in wells outside the trenches were monitored periodically. With the exception of the trench leachate sampling, each of these activities spanned the preconstruction, construction, and postconstruction periods. Findings of this study have important implications for the ongoing remedial investigation in SWSA 6 and for the design of other ICMs. 51 figs., 2 tabs.

  9. SWSA 6 interim corrective measures environmental monitoring: FY 1990 results

    International Nuclear Information System (INIS)

    This report presents the results and conclusions from a multifaceted monitoring effort associated with the high-density polyethylene caps installed in Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory (ORNL) as an interim corrective measure (ICM). The caps were installed between November 1988 and June 1989 to meet Resource Conservation and Recovery Act (RCRA) requirements for closure of those areas of SWSA 6 that had received RCRA-regulated wastes after November 1980. Three separate activities were undertaken to evaluate the performance of the caps: (1) wells were installed in trenches to be covered by the caps, and water levels in these intratrench wells were monitored periodically; (2) samples were taken of the leachate in the intratrench wells and were analyzed for a broad range of radiological and chemical contaminants; and (3) water levels in wells outside the trenches were monitored periodically. With the exception of the trench leachate sampling, each of these activities spanned the preconstruction, construction, and postconstruction periods. Findings of this study have important implications for the ongoing remedial investigation in SWSA 6 and for the design of other ICMs. 51 figs., 2 tabs

  10. E-Area Performance Assessment Interim Measures Assessment FY2005

    Energy Technology Data Exchange (ETDEWEB)

    Stallings, M

    2006-01-31

    After major changes to the limits for various disposal units of the E-Area Low Level Waste Facility (ELLWF) last year, no major changes have been made during FY2005. A Special Analysis was completed which removes the air pathway {sup 14}C limit from the Intermediate Level Vault (ILV). This analysis will allow the disposal of reactor moderator deionizers which previously had no pathway to disposal. Several studies have also been completed providing groundwater transport input for future special analyses. During the past year, since Slit Trenches No.1 and No.2 were nearing volumetric capacity, they were operationally closed under a preliminary closure analysis. This analysis was performed using as-disposed conditions and data and showed that concrete rubble from the demolition of 232-F was acceptable for disposal in the STs even though the latest special analysis for the STs had reduced the tritium limits so that the inventory in the rubble exceeded limits. A number of special studies are planned during the next years; perhaps the largest of these will be revision of the Performance Assessment (PA) for the ELLWF. The revision will be accomplished by incorporating special analyses performed since the last PA revision as well as revising analyses to include new data. Projected impacts on disposal limits of more recent studies have been estimated. No interim measures will be applied during this year. However, it is being recommended that tritium disposals to the Components-in-Grout (CIG) Trenches be suspended until a limited Special Analysis (SA) currently in progress is completed. This SA will give recommendations for optimum placement of tritiated D-Area tower waste. Further recommendations for tritiated waste placement in the CIG Trenches will be given in the upcoming PA revision.

  11. Engineering report single-shell tank farms interim measures to limit infiltration through the vadose zone

    Energy Technology Data Exchange (ETDEWEB)

    HAASS, C.C.

    1999-10-14

    Identifies, evaluates and recommends interim measures for reducing or eliminating water sources and preferential pathways within the vadose zone of the single-shell tank farms. Features studied: surface water infiltration and leaking water lines that provide recharge moisture, and wells that could provide pathways for contaminant migration. An extensive data base, maps, recommended mitigations, and rough order of magnitude costs are included.

  12. Engineering report single-shell tank farms interim measures to limit infiltration through the vadose zone

    International Nuclear Information System (INIS)

    Identifies, evaluates and recommends interim measures for reducing or eliminating water sources and preferential pathways within the vadose zone of the single-shell tank farms. Features studied: surface water infiltration and leaking water lines that provide recharge moisture, and wells that could provide pathways for contaminant migration. An extensive data base, maps, recommended mitigations, and rough order of magnitude costs are included

  13. Subsurface Interim Measures/Interim Remedial Action Plan and Decision Document for the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2)

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) is pursuing an Interim Measure/Interim Remedial Action (IM/IRA) at the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2) at the Rocky Flats Plant (RFP). This MIRA is to be conducted to provide information that will aid in the selection and design of final remedial actions at OU2 that will address removal of suspected free-phase volatile organic compound (VOC) contamination. The Plan involves investigating the removal of residual free-phase VOCs by in situ vacuum-enhanced vapor extraction technology at 3 suspected VOC source areas within OU2. VOC-contaminated vapors extracted from the subsurface would be treated by granular activated carbon (GAC) adsorption and discharged. The Plan also includes water table depression, when applicable at the test sites, to investigate the performance of vapor extraction technology in the saturated zone. The Plan provides for treatment of any contaminated ground water recovered during the IM/IRA at existing RFP treatment facilities. The proposed MVIRA Plan is presented in the document entitled ''Proposed Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, 903 Pad, Mound, and East Trenches Areas, Operable Unit No. 2, '' dated 20 March 1992. Information concerning the proposed Subsurface IM/IRA was presented during a DOE Quarterly Review meeting held on 07 April 1992 and a public meeting held on 07 May 1992, at the Marriott Hotel in Golden, Colorado. The Responsiveness Summary presents DOE's response to all comments received at the public meeting, as well as those mailed to date to DOE during the public comment period

  14. Surface Water Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document for South Walnut Creek Basin (Operable Unit No. 2)

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) is pursuing an Interim Measure/Interim Remedial Action (IM/IRA) at the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2) at the Rocky Flats Plant (RFP). This IM/IRA is to be conducted to minimize the release from these areas of hazardous substances that pose a potential threat to the public health and environment. The Plan involved the collection of contaminated surface water at specific locations, treatment by chemical precipitation, cross-flow membrane filtration and granular activated carbon (GAC) adsorption, and surface discharge of treated water. Information for the initial configuration of the Plan is presented in the document entitled ''Proposed Interim Measures/Interim Remedial Action Plan and Decision Document, 903 Pad, Mound, and East Trenches Areas, Operable Unit No. 2'' (IM/IRAP) dated 26 September 1990. Information concerning the proposed Surface Water IM/IRA was presented during a public meeting held from 7 to 10 p.m., Tuesday, 23 October 1990, at the Westminster City Park Recreation Center in Westminster, Colorado. This Responsiveness Summary presents DOE's response to all comments received at the public meeting, as well as those mailed to DOE during the public comment period which ended 24 November 1990. There were a number of technical comments on the plan that DOE has addressed herein. It is noted that several major issues were raised by the comments. Regardless of the estimated low risk to the public from construction and water transport activities, the popular sentiment of the public, based on comments received, is strong concern over worker and public health risks from these activities. In the light of public and municipal concerns, DOE proposes to eliminate from this IM/IRA the interbasin transfer of Woman Creek seepage to the South Walnut Creek drainage and to address collection and treatment of contaminated South Walnut Creek and Woman Creek surface water under two separate IM/IRAs

  15. KSC Press Site Transformer Bldg. (K7-1205c) SWMU 074 Interim Measure Work Plan

    Science.gov (United States)

    Starr, A. Scott; Applegate, Joe

    2014-01-01

    This document presents and discusses the Interim Measure (IM) Work Plan for the Press Site Transformer Building (K7-1205C). The purpose of the proposed IM activities is to remove soil affected with polychlorinated biphenyls (PCBs) greater than the Florida Department of Environmental Protection (FDEP) residential direct-exposure Soil Cleanup Target Level (R-SCTL) of 0.5 milligrams per kilogram and encapsulate concrete exhibiting PCB concentration greater than the Toxic Substance Control Act (TSCA) threshold of 50 milligrams per kilogram.

  16. Department of Energy Plutonium ES ampersand H Vulnerability Assessment Savannah River Site interim compensatory measures

    International Nuclear Information System (INIS)

    The Savannah River Site (SRS) has recently completed a self-assessment of potential vulnerabilities associated with plutonium and other transuranic materials stored at the site. An independent Working Group Assessment Team (WGAT) appointed by DOE/ES ampersand H also performed an independent assessment, and reviewed and validated the site self-assessment. The purpose of this report is to provide a status of interim compensatory measures at SRS to address hazards in advance of any corrective actions. ES ampersand H has requested this status for all vulnerabilities ranked medium or higher with respect to potential consequences to workers, environment, and the public

  17. Mobile Launch Platform Vehicle Assembly Area (SWMU 056) Biosparge Expansion Interim Measures Work Plan

    Science.gov (United States)

    Burcham, Michael S.; Daprato, Rebecca C.

    2016-01-01

    This document presents the design details for an Interim Measure (IM) Work Plan (IMWP) for the Mobile Launch Platform/Vehicle Assembly Building (MLPV) Area, located at the John F. Kennedy Space Center (KSC), Florida. The MLPV Area has been designated Solid Waste Management Unit Number 056 (SWMU 056) under KSC's Resource Conservation and Recovery Act (RCRA) Corrective Action Program. This report was prepared by Geosyntec Consultants (Geosyntec) for the National Aeronautics and Space Administration (NASA) under contract number NNK09CA02B and NNK12CA13B, project control number ENV1642. The Advanced Data Package (ADP) presentation covering the elements of this IMWP report received KSC Remediation Team (KSCRT) approval at the December 2015 Team Meeting; the meeting minutes are included in Appendix A.

  18. SWSA 6 interim corrective measures environmental monitoring: FY 1991 results. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Clapp, R.B.; Marshall, D.S.

    1992-06-01

    In 1988, interim corrective measures (ICMs) were implemented at Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory. The SWSA 6 site was regulated under the Resource Conservation and Recovery Act (RCRA). The ICMs consist of eight large high-density polyethylene sheets placed as temporary caps to cover trenches known to contain RCRA-regulated materials. Environmental monitoring for FY 1991 consisted of collecting water levels at 13 groundwater wells outside the capped areas and 44 wells in or near the capped areas in order to identify any significant loss of hydrologic isolation of the wastes. Past annual reports show that the caps are only partially effective in keeping the waste trenches dry and that many trenches consistently or intermittently contain water.

  19. Surface Water Interim Measures/Interim Remedial Action Plan/ Environmental and Decision Document, South Walnut Creek Basin, Operable Unit No.2

    International Nuclear Information System (INIS)

    Water quality investigations have identified the presence of volatile organic compound (VOC) and radionuclide contamination of surface water at the Rocky Flats Plant (RFP). The subject interim Measures/Interim Remedial Action Plan/Environmental Assessment (IM/IRAP/EA) addresses contaminated surface water in a portion of the South Walnut Creek drainage basin located within an area identified as Operable Unit No. 2 (OU 2). There is no immediate threat to public health and the environment posed by this surface water contamination. The affected surface water is contained within the plant boundary by existing detention ponds, and is treated prior to discharge for removal of volatile contaminants and suspended particulates to which radionuclides, if present, are likely to absorb. However, there is a potential threat and the Department of Energy (DOE) is implementing this Surface Water IM/IRAP at the request of the US Environmental Protection Agency (EPA) and Colorado Department of Health (CDH). Implementation of the Surface Water IM/IRA will enhance the DOE's efforts towards containing and managing contaminated surface water, and will mitigate downgradient migration of contaminants. Another factor in implementing this IM/IRA is the length of time it will take to complete the investigations and engineering studies necessary to determine the final remedy for OU 2. 44 refs., 23 figs., 14 tabs

  20. SWSA 6 interim corrective measures environmental monitoring: FY 1990 results. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Ashwood, T.L.; Spalding, B.P.

    1991-07-01

    This report presents the results and conclusions from a multifaceted monitoring effort associated with the high-density polyethylene caps installed in Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory (ORNL) as an interim corrective measure (ICM). The caps were installed between November 1988 and June 1989 to meet Resource Conservation and Recovery Act (RCRA) requirements for closure of those areas of SWSA 6 that had received RCRA-regulated wastes after November 1980. Three separate activities were undertaken to evaluate the performance of the caps: (1) wells were installed in trenches to be covered by the caps, and water levels in these intratrench wells were monitored periodically; (2) samples were taken of the leachate in the intratrench wells and were analyzed for a broad range of radiological and chemical contaminants; and (3) water levels in wells outside the trenches were monitored periodically. With the exception of the trench leachate sampling, each of these activities spanned the preconstruction, construction, and postconstruction periods. Findings of this study have important implications for the ongoing remedial investigation in SWSA 6 and for the design of other ICMs. 51 figs., 2 tabs.

  1. Spent Fuel Test - Climax: technical measurements. Interim report, fiscal year 1982

    International Nuclear Information System (INIS)

    The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted for the US Department of Energy (DOE) under the technical direction of the Lawrence Livermore National Laboratory (LLNL). Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April to May 1980, thus initiating a test with a planned 3- to 5-year fuel storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Three exchanges of spent fuel between the SFT-C and a surface storage facility furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and two previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 2-1/2 years of the test on more than 900 channels. Data continue to be acquired from the test. Some data are now available for analysis and are presented here. Highlights of activities this year include analysis of fracture data obtained during site characterization, laboratory studies of radiation effects and drilling damage in Climax granite, improved calculations of near-field heat transfer and thermomechanical response, a ventilation effects study, and further development of the data acquisition and management systems

  2. Spent Fuel Test - Climax: technical measurements. Interim report, fiscal year 1982

    Energy Technology Data Exchange (ETDEWEB)

    Patrick, W.C.; Ballou, L.B.; Butkovich, T.R.; Carlson, R.C.; Durham, W.B.; Hage, G.L.; Majer, E.L.; Montan, D.N.; Nyholm, R.A.; Rector, N.L.

    1983-02-01

    The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted for the US Department of Energy (DOE) under the technical direction of the Lawrence Livermore National Laboratory (LLNL). Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April to May 1980, thus initiating a test with a planned 3- to 5-year fuel storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Three exchanges of spent fuel between the SFT-C and a surface storage facility furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and two previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 2-1/2 years of the test on more than 900 channels. Data continue to be acquired from the test. Some data are now available for analysis and are presented here. Highlights of activities this year include analysis of fracture data obtained during site characterization, laboratory studies of radiation effects and drilling damage in Climax granite, improved calculations of near-field heat transfer and thermomechanical response, a ventilation effects study, and further development of the data acquisition and management systems.

  3. Spent fuel test - Climax: technical measurements. Interim report, Fiscal Year 1983

    Energy Technology Data Exchange (ETDEWEB)

    Patrick, W.C.; Butkovich, T.R.; Carlson, R.C.; Durham, W.B.; Ganow, H.C.; Hage, G.L.; Majer, E.L.; Montan, D.N.; Nyholm, R.A.; Rector, N.L.

    1984-02-01

    The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted as part of the Nevada Nuclear Waste Storage Investigations. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April-May 1980. The spent-fuel canisters were retrieved and the thermal sources were de-energized in March-April 1983 when test data indicated that test objectives were met during the 3-year storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. In addition to emplacement and retrieval operations, three exchanges of spent-fuel between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and three previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the 3-1/2 year duration of the test on more than 900 channels. Data acquisition from the test is now limited to instrumentation calibration and evaluation activities. Data now available for analysis are presented here. Highlights of activities this year include a campaign of in situ stress measurements, mineralogical and petrological studies of pretest core samples, microfracture analyses of laboratory irradiated cores, improved calculations of near-field heat transfer and thermomechanical response during the final months of heating as well as during a six-month cool-down period, metallurgical analyses of selected test components, and further development of the data acquisition and data management systems. 27 references, 68 figures, 10 tables.

  4. Spent fuel test - Climax: technical measurements. Interim report, Fiscal Year 1983

    International Nuclear Information System (INIS)

    The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted as part of the Nevada Nuclear Waste Storage Investigations. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April-May 1980. The spent-fuel canisters were retrieved and the thermal sources were de-energized in March-April 1983 when test data indicated that test objectives were met during the 3-year storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. In addition to emplacement and retrieval operations, three exchanges of spent-fuel between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and three previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the 3-1/2 year duration of the test on more than 900 channels. Data acquisition from the test is now limited to instrumentation calibration and evaluation activities. Data now available for analysis are presented here. Highlights of activities this year include a campaign of in situ stress measurements, mineralogical and petrological studies of pretest core samples, microfracture analyses of laboratory irradiated cores, improved calculations of near-field heat transfer and thermomechanical response during the final months of heating as well as during a six-month cool-down period, metallurgical analyses of selected test components, and further development of the data acquisition and data management systems. 27 references, 68 figures, 10 tables

  5. Contingency interim measure for the public water supply at Barnes, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2009-07-09

    This document presents a conceptual design for a contingency interim measure (IM) for treatment of the public water supply system at Barnes, Kansas, should this become necessary. The aquifer that serves the public water supply system at Barnes has been affected by trace to low concentrations of carbon tetrachloride and its degradation product, chloroform. Investigations conducted on behalf of the CCC/USDA by Argonne National Laboratory (Argonne 2008a) have demonstrated that groundwater at the Barnes site is contaminated with carbon tetrachloride at concentrations exceeding the Kansas Tier 2 risk-based screening level (RBSL) and the EPA maximum contaminant level (MCL) of 5.0 {micro}g/L for this compound. The Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) formerly operated a grain storage facility in Barnes, approximately 800 ft east-southeast of the public water supply wells. Carbon tetrachloride was used in the treatment of grain. Another potential source identified in an investigation conducted for the KDHE (PRC 1996) is the site of a former agriculture building owned by the local school district (USD 223). This building is located immediately east of well PWS3. The potential contingency IM options evaluated in this report include the treatment of groundwater at the public water supply wellheads and the provision of an alternate water supply via Washington County Rural Water District No.2 (RWD 2). This document was developed in accordance with KDHE Bureau of Environmental Remediation (BER) Policy No.BER-RS-029 (Revised) (KDHE 2006a), supplemented by guidance from the KDHE project manager. Upon the approval of this contingency IM conceptual design by the KDHE, the CCC/USDA will prepare a treatment system design document that will contain the following elements: (1) Description of the approved contingency IM treatment method; (2) Drawings and/or schematics provided by the contractor and/or manufacturer of the approved technology; (3) A

  6. Measurements of Flammable Gas Generation from Saltstone Containing Actual Tank 48H Waste (Interim Report)

    Energy Technology Data Exchange (ETDEWEB)

    Cozzi, A. D.; Crowley, D. A.; Duffey, J. M.; Eibling, R. E.; Jones, T. M.; Marinik, A. R.; Marra, J. C.; Zamecnik, J. R

    2005-06-01

    The Savannah River National Laboratory was tasked with determining the benzene release rates in saltstone prepared with tetraphenylborate (TPB) concentrations ranging from 30 mg/L to 3000 mg/L in the salt fraction and with test temperatures ranging from ambient to 95 C. Defense Waste Processing Facility Engineering (DWPF-E) provided a rate of benzene evolution from saltstone of 2.5 {micro}g/L/h saltstone (0.9 {micro}g/kg saltstone/h [1.5 {micro}g/kg saltstone/h x 60%]) to use as a Target Rate of Concern (TRC). The evolution of benzene, toluene, and xylenes from saltstone containing actual Tank 48H salt solution has been measured as a function of time at several temperatures and concentrations of TPB. The Tank 48H salt solution was aggregated with a DWPF recycle simulant to obtain the desired TPB concentrations in the saltstone slurry. The purpose of this interim report is to provide DWPF-E with an indication of the trends of benzene evolution. The data presented are preliminary; more data are being collected and may alter the preliminary results. A more complete description of the methods and materials will be included in the final report. The benzene evolution rates approximately follow an increasing trend with both increasing temperature and TPB concentration. The benzene release rates from 1000 mg/L TPB at 95 C and 3000 mg/L TPB at 75 C and 95 C exceeded the recovery-adjusted 0.9 mg/kg saltstone/h TRC (2.5 {micro}g/L saltstone/h), while all other conditions resulted in benzene release rates below this TRC. The toluene evolution rates for several samples exceeded the TRC initially, but all dropped below the TRC within 2-5 days. The toluene emissions appear to be mainly dependent on the fly ash and are independent of the TPB level, indicating that toluene is not generated from TPB.

  7. CMM Interim Check (U)

    Energy Technology Data Exchange (ETDEWEB)

    Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-03-23

    Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length. Unfortunately, several nonconformance reports have been generated to document the discovery of a certified machine found out of tolerance during a calibration closeout. In an effort to reduce risk to product quality two solutions were proposed – shorten the calibration cycle which could be costly, or perform an interim check to monitor the machine’s performance between cycles. The CMM interim check discussed makes use of Renishaw’s Machine Checking Gauge. This off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. Data was gathered, analyzed, and simulated from seven machines in seventeen different configurations to create statistical process control run charts for on-the-floor monitoring.

  8. Staying the return of aliens from Europe through interim measures: the case-law of the European Commission and the European Court of Human Rights

    OpenAIRE

    Burbano Herrera, Clara; Haeck, Yves

    2011-01-01

    The Strasbourg case-law demonstrates a clear tendency to protect aliens through interim measures in case of imminent deportation. Usually but not uniquely those persons claim(ed) before the supervisory organs to be in a situation of extreme gravity in case of forcible return to their country of origin because they can be subject to the death penalty, life imprisonment, persecution for their political activities, deprived of medicine/adequate medical treatment. This contribution explores which...

  9. Remote sensing measurements of real world high exhaust emitters. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    McClintock, P.

    1999-03-12

    Remote sensing measurements were taken at five primary sites in the Denver area between April 1997 and March 1998 using an RS2000 unit capable of measuring HC, CO, and NO. The RD unit also measures vehicle speed and acceleration to permit determination of the vehicle operating condition and captures an image of the vehicle plate for identification. RSD measurements were compared to results from subsequent IM240 tests for 10,000 vehicles. When average emissions measured by IM240 and RSD for each model year were plotted against each other, an excellent correlation was observed with an r{sub 2} of 0.93 for HC and 0.99 for CO. Despite the older technology NO channel, an r{sub 2} of 0.99 was obtained for NO. These results suggest that RSD measurements can be used to assess fleet emissions.

  10. Interim Columbia and Snake rivers flow improvement measures for salmon: Final Supplemental Environmental Impact Statement (SEIS)

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    Public comments are sought on this final SEIS, which supplements the 1992 Columbia River Salmon Flow Measures Options Analysis (OA)/Environmental Impact Statement (EIS). The Corps of Engineers, in cooperation with the Bonneville Power Administration and the Bureau of Reclamation proposes five alternatives to improve flows of water in the lower Columbia-Snake rivers in 1993 and future years to assist the migration of juvenile and adult anadromous fish past eight hydropower dams. These are: (1) Without Project (no action) Alternative, (2) the 1992 Operation, (3) the 1992 Operation with Libby/Hungry Horse Sensitivity, (4) a Modified 1992 Operation with Improvements to Salmon Flows from Dworshak, and (5) a Modified 1992 Operation with Upper Snake Sensitivity. Alternative 4, Modified 1992 Operations, has been identified as the preferred alternative.

  11. Spent fuel test - Climax: technical measurements. Interim report, fiscal year 1981

    International Nuclear Information System (INIS)

    The Spent Fuel Test-Climax (SFT-C) is located 420 m below surface in the Climax granite stock on the Nevada Test Site. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized from April to May 1980, initiating the 3- to 5-year-duration test. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Technical objectives of the test led to development of a technical measurements program, which is the subject of this report. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 1-1/2 years of the test on more than 900 channels. Much of the acquired data are now available for analysis and are presented here. Highlights of activities this year include completion of site characterization field work, major modifications to the data acquisition and the management systems, and the addition of instrument evaluation as an explicit objective of the test

  12. 24 CFR 35.1330 - Interim controls.

    Science.gov (United States)

    2010-04-01

    ... controls are used for a soil area that is subject to erosion, measures shall be taken to contain the soil... specified in § 35.1320, dust control, and lead-contaminated soil control. As provided by § 35.155, interim... be removed. (f) Soil-lead hazards. (1) Interim control treatments used to control soil-lead......

  13. Environmental Assessment and Finding of No Significant Impact: Interim Measures for the Mixed Waste Management Facility Groundwater at the Burial Ground Complex at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    1999-12-08

    The U. S. Department of Energy (DOE) prepared this environmental assessment (EA) to analyze the potential environmental impacts associated with the proposed interim measures for the Mixed Waste Management Facility (MW) groundwater at the Burial Ground Complex (BGC) at the Savannah River Site (SRS), located near Aiken, South Carolina. DOE proposes to install a small metal sheet pile dam to impound water around and over the BGC groundwater seepline. In addition, a drip irrigation system would be installed. Interim measures will also address the reduction of volatile organic compounds (VOCS) from ''hot-spot'' regions associated with the Southwest Plume Area (SWPA). This action is taken as an interim measure for the MWMF in cooperation with the South Carolina Department of Health and Environmental Control (SCDHEC) to reduce the amount of tritium seeping from the BGC southwest groundwater plume. The proposed action of this EA is being planned and would be implemented concurrent with a groundwater corrective action program under the Resource Conservation and Recovery Act (RCRA). On September 30, 1999, SCDHEC issued a modification to the SRS RCRA Part B permit that adds corrective action requirements for four plumes that are currently emanating from the BGC. One of those plumes is the southwest plume. The RCRA permit requires SRS to submit a corrective action plan (CAP) for the southwest plume by March 2000. The permit requires that the initial phase of the CAP prescribe a remedy that achieves a 70-percent reduction in the annual amount of tritium being released from the southwest plume area to Fourmile Branch, a nearby stream. Approval and actual implementation of the corrective measure in that CAP may take several years. As an interim measure, the actions described in this EA would manage the release of tritium from the southwest plume area until the final actions under the CAP can be implemented. This proposed action is expected to reduce the

  14. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-06-01

    This Interim Report summarizes the research and development activities of the Superconducting Super Collider project carried out from the completion of the Reference Designs Study (May 1984) to June 1985. It was prepared by the SSC Central Design Group in draft form on the occasion of the DOE Annual Review, June 19--21, 1985. Now largely organized by CDG Divisions, the bulk of each chapter documents the progress and accomplishments to date, while the final section(s) describe plans for future work. Chapter 1, Introduction, provides a basic brief description of the SSC, its physics justification, its origins, and the R&D organization set up to carry out the work. Chapter 2 gives a summary of the main results of the R&D program, the tasks assigned to the four magnet R&D centers, and an overview of the future plans. The reader wishing a quick look at the SSC Phase I effort can skim Chapter 1 and read Chapter 2. Subsequent chapters discuss in more detail the activities on accelerator physics, accelerator systems, magnets and cryostats, injector, detector R&D, conventional facilities, and project planning and management. The magnet chapter (5) documents in text and photographs the impressive progress in successful construction of many model magnets, the development of cryostats with low heat leaks, and the improvement in current-carrying capacity of superconducting strand. Chapter 9 contains the budgets and schedules of the COG Divisions, the overall R&D program, including the laboratories, and also preliminary projections for construction. Appendices provide information on the various panels, task forces and workshops held by the CDG in FY 1985, a bibliography of COG and Laboratory reports on SSC and SSC-related work, and on private industrial involvement in the project.

  15. Interim Measures for the Tax Preservation and Enforcement Measures of the Customs of the Peoples Republic of China

    Institute of Scientific and Technical Information of China (English)

    2010-01-01

    @@ Article 1 For the purpose of regulating the Tax Preservation and enforcement measures of the Customs of the People's Republic of China, guaranteeing the state taxation and safeguarding the lawful rights and interests of taxpayers, these Measures are formulated in accordance with the Customs Law of the People's Republic of China and the Regulations of the People's Republic of China on Import and Export Duties.

  16. Mobile Launch Platform Vehicle Assembly Building Area (SWMU 056) Hot Spot 3 Bioremediation Interim Measures Work Plan, Kennedy Space Center, Florida

    Science.gov (United States)

    Whitney L. Morrison; Daprato, Rebecca C.

    2016-01-01

    This Interim Measures Work Plan (IMWP) presents an approach and design for the remediation of chlorinated volatile organic compound (CVOC) groundwater impacts using bioremediation (biostimulation and bioaugmentation) in Hot Spot 3, which is defined by the area where CVOC (trichloroethene [TCE], cis-1,2-dichloroethene [cDCE], and vinyl chloride [VC]) concentrations are greater than 10 times their respective Florida Department of Environmental Protection (FDEP) Natural Attenuation Default Concentration (NADC) [10xNADC] near the western Mobile Launch Platform (MLP) structure. The IM treatment area is the Hot Spot 3 area, which is approximately 0.07 acres and extends from approximately 6 to 22 and 41 to 55 feet below land surface (ft BLS). Within Hot Spot 3, a source zone (SZ; area with TCE concentrations greater than 1% solubility [11,000 micrograms per liter (micrograms/L)]) was delineated and is approximately 0.02 acres and extends from approximately 6 to 16 and 41 to 50 ft BLS.

  17. Interim Measures Report for the Headquarters Building Area Location of Concern (LOC) 2E East SWMU 104 John F. Kennedy Space Center, Florida

    Science.gov (United States)

    Sager, Eric D.

    2016-01-01

    The Hazardous and Solid Waste Amendment portion of the National Aeronautics and Space Administration (NASA) Resource Conservation and Recovery Act (RCRA) Permit issued by the Florida Department of Environmental Protection (FDEP), requires identification and evaluation of all known Solid Waste Management Units (SWMUs) and Locations of Concern (LOCs) located on Kennedy Space Center (KSC) property. The KSC Headquarters Building Area (KHQA) has been identified as SWMU 104 under KSC's RCRA Program. This report summarizes the Interim Measure (IM) conducted by Geosyntec Consultants (Geosyntec) for NASA under Indefinite Delivery Indefinite Quantity Contract NNK12CA13B at the KHQA to mitigate potential exposure to polychlorinated biphenyl (PCB)-affected media at the eastern side of LOC 2E. The IM activities were conducted in June and July 2015 to remediate PCBs above the FDEP Residential Direct-Exposure (R-) Soil Cleanup Target Level (SCTL) of 0.5 milligram per kilogram (mg/kg) established by Chapter 62-777, Florida Administrative Code. The IM was performed in accordance with the IM Work Plan (IMWP) approved by the FDEP, dated August 2012. IM activities were conducted in accordance with the KSC Generic PCB Work Plan (NASA 2007).

  18. CMM Interim Check Design of Experiments (U)

    Energy Technology Data Exchange (ETDEWEB)

    Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-07-29

    Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length and include a weekly interim check to reduce risk. The CMM interim check makes use of Renishaw’s Machine Checking Gauge which is an off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. As verification on the interim check process a design of experiments investigation was proposed to test a couple of key factors (location and inspector). The results from the two-factor factorial experiment proved that location influenced results more than the inspector or interaction.

  19. Development of an EMF Measurments Database, EMF Rapid Program, Project #5, Interim Report: April 1995-December 1996

    Energy Technology Data Exchange (ETDEWEB)

    T. Dan Bracken, Inc.

    1998-03-01

    The EMF Measurements Database project is being implemented by T. Dan Bracken, Inc. as part of the EMF Research and Public Information Dissemination (EMF RAPID) Program. The Database is a collection of data sets that relate to measurement of electric and/or magnetic fields. This report describes activities during the period January 1997 to March 1998. Primary goals for the EMF Measurements Database are to develop a database structure that can accommodate the diversity of EMF data sets, provide guidance for production of future EMF data sets, and serve as an accessible repository of EMF measurement data. Specific objectives of the EMF Measurements Database are: o to presewe study descriptions, results and data; o to provide readily accessible, well-documented data; and - o to facilitate communication among researchers. In addition, the EMF Measurements Database will encourage additional analysis of existing data sets, facilitate analysis of data from multiple projects, support design of new studies, and permit future issues in EMF exposure assessment to be addressed with existing data. Preservation of study descriptions and data is accomplished with a formal, but open, structure. Specifications have been developed for the various elements of the database. Each data set in the database is formally described by a metadata file. The structured metadata file describes the origin, development, logical and physical structure, and distribution mechanism for each data set. The metadata for each data set is generated according to a specification developed for the EMF Measurements Database. The actual measurement data is contained in data products for each data set. The number and type of data product will vary by data set. Most of the data products available from the EMF Measurements Database can be downloaded from an Internet site. For some data sets, the data products will be maintained by other patties who may have their own access procedures.

  20. Assessment report of research and development on 'the abolition measures of nuclear facilities and associated technology development' and 'radioactive waste treatment and disposal and associated technology development' (Interim report)

    International Nuclear Information System (INIS)

    Japan Atomic Energy Agency (JAEA) consulted the 'Evaluation Committee for Nuclear Cycle Backend Program Promotion' to perform the interim evaluation of 'the abolition measures of nuclear facilities and associated technology development' project and 'radioactive waste treatment and disposal and associated technology development' project in accordance with the 'Guideline for evaluation of government R and D activities', the 'Guideline for evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology (MEXT)' and the 'Operational rule for evaluation of R and D activities' by JAEA. In response to JAEA's request, the Committee decided the evaluation method and performed the interim evaluation of both projects from the viewpoints of purposes, plans, results and so on. As a result of review, the Committee concluded that both projects were proceeded adequately. (author)

  1. Development of an EMF Measurements Database, EMF Rapid Program, Project #5, Interim Report: April 1995-December 1996

    Energy Technology Data Exchange (ETDEWEB)

    T. Dan Bracken, Inc.

    1997-04-01

    The EMF measurement data sets in existence today were compiled with varying goals and techniques. Consequently, they have different information content as well as varying logical and physical structure. Future studies will continue to pursue varying goals and utilize techniques that cannot be known in advance. Primary goals for the EMF Measurements Database developed under the Department of Energy EMF RAPID Program are to develop a database structure that can accommodate the diversity of EMF data sets, provide guidance for production of future EMF data sets, and serve as an accessible repository of EMF measurement data. Specific objectives of the EMF Measurements Database are: o to preserve study descriptions, results and data; o to provide readily accessible, well-documented data; and o to facilitate communication among researchers. In addition, the EMF Measurements Database will encourage additional analysis of existing data sets, facilitate analysis of data from multiple projects, support design of new studies, and permit future issues in EMF exposure assessment to be addressed with existing data. Preservation of study descriptions and data is accomplished with a formal, but open, structure. Specifications have been developed for the various elements of the database. Each data set in the database is formally described by a metadata file. The structured metadata file describes the origin, development, logical and physical structure and distribution mechanism for each data set. The metadata for each data set is generated according to a specification developed for the EMF Measurements Database. The actual measurement data is contained in data Products for each data set. The number and type of data product will vary by data set. Most of the data products in the possession of the EMF Measurements Database are available for download from an Internet site. For some data sets, the data products will be maintained by other parties who may have their own access procedures

  2. Methods development for measuring and classifying flammability/combustibility of refrigerants. Interim report, task 2 - test plan

    Energy Technology Data Exchange (ETDEWEB)

    Heinonen, E.W.; Tapscott, R.E. [Univ. of New Mexico, Albuquerque, NM (United States)

    1994-07-01

    Regulations on alternative refrigerants and concerns for the environment are forcing the refrigeration industry to consider the use of potentially flammable fluids to replace CFC fluids currently in use. The objectives of this program are to establish the conditions under which refrigerants and refrigerant blends exhibit flammability and to develop appropriate methods to measure flammability.

  3. Interim storage study report

    Energy Technology Data Exchange (ETDEWEB)

    Rawlins, J.K.

    1998-02-01

    High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

  4. Interim Design Report

    OpenAIRE

    Abrams, R.; Agarwalla, S.; A. Alekou; Andreopoulos, C.; Ankenbrandt, C.; Antusch, S.; M. Apollonio(19, d); Aslaninejad, M.; J. Back; P. Ballett; Barker, G.; Beard, K.; Benedetto, E; Bennett, J.; Berg, J.

    2011-01-01

    The International Design Study for the Neutrino Factory (the IDS-NF) was established by the community at the ninth "International Workshop on Neutrino Factories, super-beams, and beta- beams" which was held in Okayama in August 2007. The IDS-NF mandate is to deliver the Reference Design Report (RDR) for the facility on the timescale of 2012/13. In addition, the mandate for the study [3] requires an Interim Design Report to be delivered midway through the project as a step on the way to the RD...

  5. Quality assurance plan for the Molten Salt Reactor Experiment Remediation Project at the Oak Ridge National Laboratory. Phase 1 -- Interim corrective measures and Phase 2 -- Purge and trap reactive gases

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    This Quality Assurance Plan (QAP) identifies and describes the systems utilized by the Molten Salt Reactor Experiment Remediation Project (MSRERP) personnel to implement the requirements and associated applicable guidance contained in the Quality Program Description Y/QD-15 Rev. 2 (Energy Systems 1995f). This QAP defines the quality assurance (QA) requirements applicable to all activities and operations in and directly pertinent to the MSRERP Phase 1--Interim Corrective Measures and Phase 2--Purge and Trap objectives. This QAP will be reviewed, revised, and approved as necessary for Phase 3 and Phase 4 activities. This QAP identifies and describes the QA activities and procedures implemented by the various Oak Ridge National Laboratory support organizations and personnel to provide confidence that these activities meet the requirements of this project. Specific support organization (Division) quality requirements, including the degree of implementation of each, are contained in the appendixes of this plan.

  6. Interim Design Report

    CERN Document Server

    Abrams, R J; Alekou, A; Andreopoulos, C; Ankenbrandt, C M; Antusch, S; Apollonio, M; Aslaninejad, M; Back, J; Ballett, P; Barker, G; Beard, K B; Benedetto, E; Bennett, J R J; Berg, J S; Bhattacharya, S; Blackmore, V; Blennow, M; Blondel, A; Bogacz, A; Bonesini, M; Bontoiu, C; Booth, C; Bromberg, C; Brooks, S; Bross, A; Caretta, O; Cervera-Villanueva, A; Choubey, S; Cline, D; Cobb, J; Coloma, P; Coney, L; Cummings, M A C; Davenne, T; de Gouvea, A; Densham, C; Ding, X; Donini, A; Dornan, P; Dracos, M; Dufour, F; Eccleston, R; Edgecock, R; Efthymiopoulos, I; Ellis, M; Fernandez-Martinez, E; Fernow, R; Flanagan, G; Gallardo, J C; Gandhi, R; Garoby, R; Gavela, B; Geer, S; Gilardoni, S; Gomez-Cadenas, J J; Goswami, S; Graves, V B; Gupta, R; Hanson, G; Harrison, P; Hart, T; Hernandez, P; Huber, P; Indumathi, D; Johnson, R P; Johnstone, C; Karadzhov, Y; Kelliher, D; Kirk, H; Kopp, J; Kudenko, Y; Kuno, Y; Kurup, A; Kyberd, P; Laing, A; Li, T; Lindner, M; Long, K; Pavon, J Lopez; Loveridge, P; Machida, S; Majumdar, D; Maltoni, M; Martin-Albo, J; Martini, M; Matev, R; McDonald, K T; McFarland, A; Meloni, D; Mezzetto, M; Migliozzi, P; Mishra, S R; Mokhov, N; Mondal, N; Morfin, J; Mori, Y; Morozov, V; Neuffer, D; Ota, T; Palladino, V; Parke, S; Pascoli, S; Pasternak, J; Peltoniemi, J; Petti, R; Planche, T; Popovic, M; Pozimski, J; Prior, G; Prior, C; Rees, G; Rigolin, S; Roberts, T J; Roblin, Y; Rogers, C; Samulyak, R; Schwetz, T; Simos, N; Sinha, N; Skoro, G; Snopok, P; Soler, F J P; Souchlas, N; Strait, J; Stratakis, D; Striganov, S; Tang, J; Thomason, J W G; Tortora, L; Tsenov, R; Winter, W; Witte, H; Yasuda, O; Yoshikawa, C Y; Zisman, M

    2011-01-01

    The International Design Study for the Neutrino Factory (the IDS-NF) was established by the community at the ninth "International Workshop on Neutrino Factories, super-beams, and beta- beams" which was held in Okayama in August 2007. The IDS-NF mandate is to deliver the Reference Design Report (RDR) for the facility on the timescale of 2012/13. In addition, the mandate for the study [3] requires an Interim Design Report to be delivered midway through the project as a step on the way to the RDR. This document, the IDR, has two functions: it marks the point in the IDS-NF at which the emphasis turns to the engineering studies required to deliver the RDR and it documents baseline concepts for the accelerator complex, the neutrino detectors, and the instrumentation systems. The IDS-NF is, in essence, a site-independent study. Example sites, CERN, FNAL, and RAL, have been identified to allow site-specific issues to be addressed in the cost analysis that will be presented in the RDR. The choice of example sites shou...

  7. Ontario interim market

    International Nuclear Information System (INIS)

    Ontario's White Paper outlined the government's plan to restructure the electric power industry to an open market by the year 2000. Bill 35, when passed, will be the legislation required to start the process of electricity restructuring laid out in the White Paper. In the section dealing with the Independent Market Operator, the White Paper states that the Ontario government, as a transitional step to an open market, will introduce an element of competition into the industry by establishing an interim market for replacement power and impose a discipline on Ontario Hydro. Unfortunately, this transitional step did not live up to its billing and has had a minimal impact on both Ontario Hydro and the marketplace. Nevertheless, the experiment has provided a peek into the future of electricity and power pricing in Ontario, by making price information available and posted on the Internet. This paper examines how informative this experience has been and looks at the year just past in perspective. One of the notable developments was that the threat of a power shortage as a result of shutting down seven of Ontario Hydro's nuclear reactors, did not materialize. Ontario Hydro's fossil fuel generation plants were able to step into the breach and generate enough energy to make up for the reduction in nuclear production, and did so within the allowable limit for acid gas emissions. Some interesting developments in pricing electric power exported to the US in the summer of of 1998 are also reviewed for what they can teach us about the value of transparency and full price disclosure. 2 figs

  8. An Interim President Sets the Stage

    Science.gov (United States)

    Guardo, Carol J.

    2006-01-01

    An interim president often plays a crucial role in leading a college or university. In some instances, the interim can address and resolve troublesome issues and thus clear the way for the new president to generate progress. In others, the interim stays the course so that the institution maintains its momentum and seizes strategic opportunities to…

  9. 32 CFR 776.82 - Interim suspension.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 5 2010-07-01 2010-07-01 false Interim suspension. 776.82 Section 776.82... Complaint Processing Procedures § 776.82 Interim suspension. (a) Where the Rules Counsel determines there is... interim suspension, pending completion of a professional responsibility investigation. The...

  10. 22 CFR 127.8 - Interim suspension.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Interim suspension. 127.8 Section 127.8 Foreign... Interim suspension. (a) The Managing Director of the Directorate of Defense Trade Controls or the Director of the Office of Defense Trade Controls Compliance is authorized to order the interim suspension...

  11. Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

    Science.gov (United States)

    Favalli, A.; Vo, D.; Grogan, B.; Jansson, P.; Liljenfeldt, H.; Mozin, V.; Schwalbach, P.; Sjöland, A.; Tobin, S. J.; Trellue, H.; Vaccaro, S.

    2016-06-01

    The purpose of the Next Generation Safeguards Initiative (NGSI)-Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI-SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute 137Cs count rate and the 154Eu/137Cs, 134Cs/137Cs, 106Ru/137Cs, and 144Ce/137Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity's behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. The results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.

  12. Spent Fuel Behaviour During Interim Storage

    International Nuclear Information System (INIS)

    Objective: Review of spent fuel data relevant for future storage in Spain Perform destructive and non-destructive examinations on irradiated and non-irradiated fuel rods relevant to Spanish spent fuel management. Research approach: Among the programmes initiated in the last years (finished or about to be finished) one may highlight the following ones: • Isotopic measurements on high burnup fuels: up to 75 GW·d·t(U)-1 PWR and 53 GW·d·t(U)-1 BWR peak values; • Mechanical tests on high burnup PWR (ZIRLO) cladding and BWR (Zry-2) cladding samples; • Mechanical tests on unirradiated ZIRLO rods. Influence of hydrides content; • Modelling of mechanical tests with unirradiated claddings; • Interim storage creep modelling; • Burnup measurement equipment; • Fuel database

  13. Big Oaks National Wildlife Refuge : Interim Plans : 2000

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This interim plan for Big Oaks National Wildlife Refuge cover an interim comprehensive conservation plan, a hunting and fishing plan and an interim compatibility...

  14. Resurgence of measles in a country of elimination: interim assessment and current control measures in the Republic of Korea in early 2014

    Directory of Open Access Journals (Sweden)

    Tae Un Yang

    2015-04-01

    Full Text Available Since the beginning of 2014, the Republic of Korea has experienced a resurgence of measles cases. Among the 220 cases confirmed as measles during epidemiological weeks 1–20 (December 29, 2013 to May 17, 2014, 10 imported cases were identified. The predominant genotype was B3, which reflects the circulating measles virus in adjacent countries. Even with the verification of measles elimination in March 2014 by the World Health Organization, recent importation has been related to international travel. Targeted control measures have been implemented in addition to proper isolation and patient care. A vigilant surveillance system and high levels of vaccine coverage should be maintained to sustain the measles elimination status.

  15. 45 CFR 1623.6 - Interim funding.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 4 2010-10-01 2010-10-01 false Interim funding. 1623.6 Section 1623.6 Public Welfare Regulations Relating to Public Welfare (Continued) LEGAL SERVICES CORPORATION SUSPENSION PROCEDURES § 1623.6 Interim funding. (a) Pending the completion of suspension proceedings under this...

  16. THESAURUS OF ERIC DESCRIPTORS (INTERIM) JANUARY 1967.

    Science.gov (United States)

    1967

    THE "THESAURUS OF ERIC DESCRIPTORS (INTERIM)" SUPERSEDES, AND REPRESENTS A REFINEMENT OF, THE "THESAURUS OF ERIC DESCRIPTORS." THE INTERIM ISSUE IS A PRELIMINARY ERIC SYSTEM TOOL AND IS NOT TO BE CONSIDERED A COMPLETE REPRESENTATION OF THE FINAL PRODUCT. THIS REFINEMENT IS THE RESULT OF TWO MAJOR PROJECTS--(1) THE INCORPORATION OF SUGGESTIONS…

  17. 15 CFR 904.322 - Interim action.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Interim action. 904.322 Section 904... Sanctions and Denials Permit Sanction for Violations § 904.322 Interim action. (a) To protect marine resources during the pendency of an action under this subpart, in cases of willfulness, or as...

  18. Fusion Breeder Program interim report

    International Nuclear Information System (INIS)

    This interim report for the FY82 Fusion Breeder Program covers work performed during the scoping phase of the study, December, 1981-February 1982. The goals for the FY82 study are the identification and development of a reference blanket concept using the fission suppression concept and the definition of a development plan to further the fusion breeder application. The context of the study is the tandem mirror reactor, but emphasis is placed upon blanket engineering. A tokamak driver and blanket concept will be selected and studied in more detail during FY83

  19. Solid waste burial grounds interim safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Saito, G.H.

    1994-10-01

    This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

  20. Solid waste burial grounds interim safety analysis

    International Nuclear Information System (INIS)

    This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment

  1. The Limitation of Implementing Interim Measures For Social Assistance and Its Perfection%《社会救助暂行办法》实施的局限性及其完善∗

    Institute of Scientific and Technical Information of China (English)

    谢勇才; 王茂福

    2016-01-01

    The Interim Measures for Social Assistance is the first administrative regulations to co-ordinate and regulate the social as⁃sistance system since the founding of the PRC. Its achievements are mainly reflected in the construction of a complete social assistance system, break the urban and rural segmentation of social assistance system and adhere to the people-oriented idea. And it also has many disadvantages, such as the legislative status is not high, the terms of the license are too many, central and local fiscal responsi⁃bility is not clear, the punishment of illegal efforts is not strong enough and the particularity of the migrant workers is disregarded etc. In order to overcome these difficulties and improve the social relief system, the government should take a series of measures to protect the basic life of poverty groups, improve the legal status, introduce detailed rules for the implementation of regulation, clear central and local financial responsibility, increase the intensity of punishment for illegal and pay attention to the particularity of the migrant work⁃ers, and so on.%《社会救助暂行办法》是新中国成立以来第一部统筹和规范各项社会救助制度的行政法规,其成就主要体现在构建了完整的社会救助体系、破除了社会救助制度的城乡二元分割、恪守了以人为本的立法理念三个方面。但它也存在诸多局限,如立法位阶不高、授权条款偏多、央地财政责任不清晰、对违法的惩罚力度不够以及忽视农民工的特殊性等。政府应采取一系列措施,如提升法律位阶、出台法规实施细则、明晰央地财政责任、加大对违法的惩罚力度以及重视农民工的特殊性等,以完善社会救助制度,进而织牢保障贫困群体基本生活的最后安全网。

  2. Evaluating the agreement between measurements and models of net ecosystem exchange at different times and time scales using wavelet coherence: an example using data from the North American Carbon Program Site-Level Interim Synthesis

    Directory of Open Access Journals (Sweden)

    P. C. Stoy

    2013-02-01

    Full Text Available Earth system processes exhibit complex patterns across time, as do the models that seek to replicate these processes. Model output may or may not be significantly related to observations at different times and on different frequencies. Conventional model diagnostics provide an aggregate view of model-data agreement, but usually do not identify the time and frequency patterns of model misfit, leaving unclear the steps required to improve model response to environmental drivers that vary on characteristic frequencies. Wavelet coherence can quantify the times and frequencies at which models and measurements are significantly different. We applied wavelet coherence to interpret the predictions of twenty ecosystem models from the North American Carbon Program (NACP Site-Level Interim Synthesis when confronted with eddy covariance-measured net ecosystem exchange (NEE from ten ecosystems with multiple years of available data. Models were grouped into classes with similar approaches for incorporating phenology, the calculation of NEE, and the inclusion of foliar nitrogen (N. Models with prescribed, rather than prognostic, phenology often fit NEE observations better on annual to interannual time scales in grassland, wetland and agricultural ecosystems. Models that calculate NEE as net primary productivity (NPP minus heterotrophic respiration (HR rather than gross ecosystem productivity (GPP minus ecosystem respiration (ER fit better on annual time scales in grassland and wetland ecosystems, but models that calculate NEE as GPP – ER were superior on monthly to seasonal time scales in two coniferous forests. Models that incorporated foliar nitrogen (N data were successful at capturing NEE variability on interannual (multiple year time scales at Howland Forest, Maine. Combined with previous findings, our results suggest that the mechanisms driving daily and annual NEE variability tend to be correctly simulated, but the magnitude of these fluxes is often

  3. AGR-1 Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Machael Abbott

    2009-08-01

    Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010.

  4. Radon Measurements in Schools: An Interim Report.

    Science.gov (United States)

    Environmental Protection Agency, Washington, DC. Office of Radiation Programs.

    Radon-222 is a colorless, odorless, tasteless, radioactive gas that occurs naturally in soil, rocks, underground water, and air. The United States Environmental Protection Agency (EPA) and other scientific organizations have identified an increased risk of lung cancer associated with exposure to elevated levels of radon in homes. Schools in many…

  5. Effect of Interim Annealing on Mechanical Strength of TFA-MOD Derived YBCO Coated Conductors

    Science.gov (United States)

    Takagi, Y.; Nakaoka, K.; Nakamura, T.; Yoshizumi, M.; Kiss, T.; Izumi, T.; Shiohara, Y.

    TFA-MOD derived YBCO tapes are expected for many applications due to cost-efficiency. In some applications, uniformity and mechanical strength are required for tapes. A 205 m-long YBCO tape was fabricated with high and uniform Ic performance throughout the tape by adopting the interim annealing before the conversion process. The effect of the interim annealing on the crystal growth mechanism of YBCO has been studied focusing on the relationship between the interim annealing conditions and delamination, in this work. Delamination strength was evaluated in the samples prepared with and without interim annealing by the stud pull method. Measurements were carried out on 50 different points for each sample and the results were analyzed statistically. The difference between the two samples was remarkably seen in the delamination strength below 60 MPa. The conventionally annealed sample had more points with low delamination strength below 60 MPa than the interim annealed one. The cross sectional images of both samples observed by SEM showed that there were few pores within the interim annealed superconducting layer, although conventional superconducting layer had many pores. These results suggest that the pores within YBCO layer might be origins to be propagated for delamination at low strength.

  6. Russian River Interim Action Management Plan

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — An interim action plan is presented to guide the 1979 management of the Kenai National Moose Range's portion of the lower Russian River and its confluence with the...

  7. Interim and End States, Sellafield, United Kingdom

    International Nuclear Information System (INIS)

    The Sellafield PFSP is an uncovered external pond, currently in the pre-decommissioning waste retrieval phase. Further consideration is now being given to the next phases of decommissioning, including defining interim states and the end state for the facility

  8. Dosimetry at an interim storage for spent nuclear fuel.

    Science.gov (United States)

    Králík, M; Kulich, V; Studeny, J; Pokorny, P

    2007-01-01

    The Czech nuclear power plant Dukovany started its operation in 1985. All fuel spent from 1985 up to the end of 2005 is stored at a dry interim storage, which was designed for 60 CASTOR-440/84 casks. Each of these casks can accommodate 84 fuel assemblies from VVER 440 reactors. Neutron-photon mixed fields around the casks were characterized in terms of ambient dose equivalent measured by standard area dosemeters. Except this, neutron spectra were measured by means of a Bonner sphere spectrometer, and the measured spectra were used to derive the corresponding ambient dose equivalent due to neutrons. PMID:17526479

  9. Dosimetry at an interim storage for spent nuclear fuel.

    Science.gov (United States)

    Králík, M; Kulich, V; Studeny, J; Pokorny, P

    2007-01-01

    The Czech nuclear power plant Dukovany started its operation in 1985. All fuel spent from 1985 up to the end of 2005 is stored at a dry interim storage, which was designed for 60 CASTOR-440/84 casks. Each of these casks can accommodate 84 fuel assemblies from VVER 440 reactors. Neutron-photon mixed fields around the casks were characterized in terms of ambient dose equivalent measured by standard area dosemeters. Except this, neutron spectra were measured by means of a Bonner sphere spectrometer, and the measured spectra were used to derive the corresponding ambient dose equivalent due to neutrons.

  10. CANDU spent fuel dry storage interim technique

    International Nuclear Information System (INIS)

    CANDU heavy water reactor is developed by Atomic Energy of Canada (AECL) it has 40 years of design life. During operation, the reactor can discharge a lot of spent fuels by using natural uranium. The spent fuel interim storage should be considered because the spent fuel bay storage capacity is limited with 6 years inventory. Spent fuel wet interim storage technique was adopted by AECL before 1970s, but it is diseconomy and produced extra radiation waste. So based on CANDU smaller fuel bundle dimension, lighter weight, lower burn-up and no-critical risk, AECL developed spent fuel dry interim storage technique which was applied in many CANDU reactors. Spent fuel dry interim storage facility should be designed base on critical accident prevention, decay heat removal, radiation protection and fissionable material containment. According to this introduction, analysis spent fuel dry interim storage facility and equipment design feature, it can be concluded that spent fuel dry interim storage could be met with the design requirement. (author)

  11. Methods Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    R. Sam Alessi; Tami Grimmett; Leng Vang; Dave McGrath

    2010-09-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V&V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  12. Interim Hanford Waste Management Plan

    International Nuclear Information System (INIS)

    The September 1985 Interim Hanford Waste Management Plan (HWMP) is the third revision of this document. In the future, the HWMP will be updated on an annual basis or as major changes in disposal planning at Hanford Site require. The most significant changes in the program since the last release of this document in December 1984 include: (1) Based on studies done in support of the Hanford Defense Waste Environmental Impact Statement (HDW-EIS), the size of the protective barriers covering contaminated soil sites, solid waste burial sites, and single-shell tanks has been increased to provide a barrier that extends 30 m beyond the waste zone. (2) As a result of extensive laboratory development and plant testing, removal of transuranic (TRU) elements from PUREX cladding removal waste (CRW) has been initiated in PUREX. (3) The level of capital support in years beyond those for which specific budget projections have been prepared (i.e., fiscal year 1992 and later) has been increased to maintain Hanford Site capability to support potential future missions, such as the extension of N Reactor/PUREX operations. The costs for disposal of Hanford Site defense wastes are identified in four major areas in the HWMP: waste storage and surveillance, technology development, disposal operations, and capital expenditures

  13. Interim Measures for the Tax Preservation And Enforcement Measures of the Customs of The People's Republic of China%中华人民共和国海关税收保全和强制措施暂行办法

    Institute of Scientific and Technical Information of China (English)

    2010-01-01

    @@ Article 1 For the purpose of regulating the Tax Preservation and enforcement measures of the Customs of the People's Republic of China,guaranteeing the state taxation and safeguarding the lawful rights and interests of taxpayers,these Measures are formulated in accordance with the Customs Law of the People's Republic of China and the Regulations of the People's Republic of China on Import and Export Duties.

  14. EMCS Retrofit Analysis - Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Diamond, R.C.; Salsbury, T.I.; Bell, G.C.; Huang, Y.J.; Sezgen, A.O.; Mazzucchi, R.; Romberger, J.

    1999-03-01

    This report presents the interim results of analyses carried out in the Phillip Burton Federal Building in San Francisco from 1996 to 1998. The building is the site of a major demonstration of the BACnet communication protocol. The energy management and control systems (EMCS) in the building were retrofitted with BACnet compatible controllers in order to integrate certain existing systems on one common network. In this respect, the project has been a success. Interoperability of control equipment from different manufacturers has been demonstrated in a real world environment. Besides demonstrating interoperability, the retrofits carried out in the building were also intended to enhance control strategies and capabilities, and to produce energy savings. This report presents analyses of the energy usage of HVAC systems in the building, control performance, and the reaction of the building operators. The report does not present an evaluation of the performance capabilities of the BACnet protocol. A monitoring system was installed in the building that parallels many of the EMCS sensors and data were archived over a three-year period. The authors defined pre-retrofit and post-retrofit periods and analyzed the corresponding data to establish the changes in building performance resulting from the retrofit activities. The authors also used whole-building energy simulation (DOE-2) as a tool for evaluating the effect of the retrofit changes. The results of the simulation were compared with the monitored data. Changes in operator behavior were assessed qualitatively with questionnaires. The report summarizes the findings of the analyses and makes several recommendations as to how to achieve better performance. They maintain that the full potential of the EMCS and associated systems is not being realized. The reasons for this are discussed along with possible ways of addressing this problem. They also describe a number of new technologies that could benefit systems of the type

  15. Interim Financial Reporting in Function of Proper Decision Makind

    OpenAIRE

    Kacanski, Slobodan; Tomašević, Stevan; Vlaović-Begović, Sanja

    2014-01-01

    This paper analyses the attributes of interim financial reporting, as well as performs overview and interpretation of International Accounting Standard 34 which deals with this issue. The paper emphasizes risk and effects of interim financial statements implementation in decision making process. Time and cost limitations significantly influence the level of reliability on interim repors since those reports were not audited. This paper analyses the attributes of interim financial reporting,...

  16. Interim-Management: A paradox for leadership research?

    OpenAIRE

    Bruns, Jürgen; Kabst, Rüdiger

    2005-01-01

    The study focuses on Interim-Management as a so far rarely discussed phenomenon of the flexible firm. Contradicting popular leadership perception, the authors argue that Interim-Management does not constitute a leadership paradox but can be explained by established organization theory. In particular, transaction cost economics as well as resource-based view help explain the utilization of Interim-Management. Furthermore, the authors show that Interim-Management constitutes a response to reduc...

  17. Design review report FFTF interim storage cask

    Energy Technology Data Exchange (ETDEWEB)

    Scott, P.L.

    1995-01-03

    Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location.

  18. Haiti; Interim Poverty Reduction Strategy Paper: Joint Staff Advisory Note

    OpenAIRE

    International Monetary Fund

    2007-01-01

    This Joint Staff Advisory Note focuses on the Interim Poverty Reduction Strategy Paper (I-PRSP) for Haiti. The I-PRSP outlines the main areas of actions envisaged by the authorities to reduce poverty as well as the steps to be undertaken in the preparation of the full Poverty Reduction Strategy. The I-PRSP presents a good diagnostic of the current dimensions of poverty in Haiti. It also covers well the authorities’ macroeconomic objectives and the broad measures necessary to reach these obj...

  19. Seal capability of interim post and core crown with temporary cements

    Directory of Open Access Journals (Sweden)

    Guilherme Bönecker-Valverde

    2010-06-01

    Full Text Available The purpose of the present study was to evaluate the in vitro seal capability of interim post and core crown restorations. Eighty teeth were selected and divided into 8 groups. Four experimental groups received interim posts and core crowns. Half of each group was decoronated at the cementum-enamel junction, groups PCCH and PCZO. The other half was sectioned 2 mm coronal to the cementum-enamel junction, groups PCrZO and PCrCH. The interim post and core crowns were luted with Rely X Temp NE, groups PCrZO and PCZO; Hydro C was used for Groups PCrCH and PCCH. The control groups, PC and PCr, received uncoated post and core crowns; groups OTg and OT were left without interim post and core crowns and were totally open. Infiltration was accessed by dye exposure followed by demineralization of the teeth. The length of the infiltration was measured using digital images taken from the specimens. The images were inserted into the Image Tool 3.0 software. Kruskal-Wallis analysis of variance and Dunn's multiple comparison method were used to test for significant differences among test groups (P < .05. Groups PCrZO and PCrCH showed the least dye penetration, followed by groups PCZO and PCCH. Teeth restored with interim post and core crowns will be subject to leakage. Ethics Committee: 095/2008.

  20. The Study on Regulations of Interim Spent Fuel Storage Facility in Japan

    International Nuclear Information System (INIS)

    The expansion of nuclear power generation inevitably result in the increase of spent nuclear fuel generation. Every year ∼700t of spent nuclear fuels are accumulated and total of 10,761t of spent nuclear fuels generated from 20 reactors are stored within the reactor sites by the end of 2009. If this trend is maintained, it is expected that Korea will have ∼30,000t of spent nuclear fuel by 2030. The capacity of pools in reactor sites is expected to be reached from 2016 and Korea need to prepare measures including the introduction of interim storage facility urgently. Considering the domestic situation described so far, it is be very necessary to survey and analyze the regulations of interim storage facilities of advanced countries. This report excerpts and analyzes the report of Japanese Nuclear Energy Safety Organization (JNES) on the regulations of interim storage facilities which was issues before the construction of the Mutz Interim Storage Facility. This report will be effectively used for the preparation of interim storage facility of Korea

  1. 340 waste handling facility interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    VAIL, T.S.

    1999-04-01

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

  2. Disposal facility data for the interim performance

    International Nuclear Information System (INIS)

    The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

  3. LANDFILL BIOREACTOR PERFORMANCE, SECOND INTERIM REPORT

    Science.gov (United States)

    A bioreactor landfill is a landfill that is operated in a manner that is expected to increase the rate and extent of waste decomposition, gas generation, and settlement compared to a traditional landfill. This Second Interim Report was prepared to provide an interpretation of fie...

  4. 12 CFR 268.505 - Interim relief.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 3 2010-01-01 2010-01-01 false Interim relief. 268.505 Section 268.505 Banks and Banking FEDERAL RESERVE SYSTEM (CONTINUED) BOARD OF GOVERNORS OF THE FEDERAL RESERVE SYSTEM RULES..., eligibility for a within-grade increase, or the completion of the service requirement for career tenure,...

  5. 33 CFR 385.38 - Interim goals.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 3 2010-07-01 2010-07-01 false Interim goals. 385.38 Section 385.38 Navigation and Navigable Waters CORPS OF ENGINEERS, DEPARTMENT OF THE ARMY, DEPARTMENT OF DEFENSE PROGRAMMATIC REGULATIONS FOR THE COMPREHENSIVE EVERGLADES RESTORATION PLAN Ensuring Protection of the...

  6. 340 waste handling facility interim safety basis

    International Nuclear Information System (INIS)

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people

  7. 78 FR 63276 - Interim Policy, FAA Review of Solar Energy System Projects on Federally Obligated Airports

    Science.gov (United States)

    2013-10-23

    ... Federal Aviation Administration Interim Policy, FAA Review of Solar Energy System Projects on Federally... federally obligated airports to construct solar energy systems on airport property. FAA is adopting an... for measuring ocular impact of proposed solar energy systems which are effective upon publication....

  8. 78 FR 37719 - Interim Final Determination To Defer Sanctions; California; South Coast Air Quality Management...

    Science.gov (United States)

    2013-06-24

    ... approval of revisions to the South Coast Air Quality Management District's (SCAQMD) portion of the... Quality Management District Proposed Contingency Measures for the 2007 PM 2.5 SIP'' (dated October 2011... AGENCY 40 CFR Part 52 Interim Final Determination To Defer Sanctions; California; South Coast Air...

  9. Interim storage facility for spent fuel

    International Nuclear Information System (INIS)

    The spent fuel generated from the operation of a nuclear power plant is to be treated in the reprocessing plant in Rokkasho, Aomori. At present, spent fuel is stored in the nuclear power plant until it is reprocessed. However the amount of spent fuel generated exceeds the capacity of the reprocessing plant. Hence an additional spent fuel storage facility is needed for the nuclear fuel cycle. The spent fuel interim storage facility is the first institution in Japan that stores spent fuel outside of the nuclear power plant site. Our company has received an order for internal equipment for this facility. This paper introduces an overview of the interim storage facility for spent fuel. (author)

  10. Pathways to deep decarbonization - Interim 2014 Report

    International Nuclear Information System (INIS)

    The interim 2014 report by the Deep Decarbonization Pathways Project (DDPP), coordinated and published by IDDRI and the Sustainable Development Solutions Network (SDSN), presents preliminary findings of the pathways developed by the DDPP Country Research Teams with the objective of achieving emission reductions consistent with limiting global warming to less than 2 deg. C. The DDPP is a knowledge network comprising 15 Country Research Teams and several Partner Organizations who develop and share methods, assumptions, and findings related to deep decarbonization. Each DDPP Country Research Team has developed an illustrative road-map for the transition to a low-carbon economy, with the intent of taking into account national socio-economic conditions, development aspirations, infrastructure stocks, resource endowments, and other relevant factors. The interim 2014 report focuses on technically feasible pathways to deep decarbonization

  11. Gaz de France interim financial report 2007

    International Nuclear Information System (INIS)

    This financial report contains the unaudited condensed financial statements of Gaz de France Group for the first half ended June 30, 2007, which were reviewed by the audit committee on August 27, 2007 and by the board of directors at its meeting on August 28, 2007. It includes forward-looking statements concerning the objectives, strategies, financial position, future operating results and the operations of Gaz de France Group. These statements reflect the Group's current perception of its activities and the markets in which it operates, as well as various estimates and assumptions considered to be reasonable. Content: interim management report (highlights of the first half of 2007, revenues and results for the period, financial structure, data on outstanding stock, outlook); interim consolidated financial statements (consolidated statements of income, consolidated balance sheets, consolidated statements of cash flows, recognized income and expenses, statements of changes in shareholders' equity, note to the consolidated financial statements); statement by the person responsible for the interim financial report; statutory auditors' report. (J.S.)

  12. Interim report - geotechnical site assessment methodology. Vol.1

    International Nuclear Information System (INIS)

    An interim report summarizing the research conducted on geotechnical site assessment methodology at the Carwynnen test mine in Cornwall. The geological setting of the test site in the Cornubian granite batholith is described. The effect of structure imposed by discontinuities on the engineering behaviour of rock masses is discussed and the scanline survey method of obtaining data on discontinuities in the rock mass is described. The requirement for remote geophysical methods of characterizing the mass is discussed and initial experiments using seismic and ultrasonic velocity measurements are reported. Computer programs to perform statistical analysis of the discontinuity patterns are described. Overcoring and hydraulic fracturing methods of determining the in-situ stress are briefly described and the results of a programme of in-situ stress measurements using the overcoring method are reported. (author)

  13. T-TY Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring FY10 Report

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Z. F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Strickland, Christopher E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Field, Jim G. [Washington River Protection Solutions, Inc., Richland, WA (United States); Parker, Danny L. [Washington River Protection Solutions, Inc., Richland, WA (United States)

    2011-01-01

    The U.S. Department of Energy’s Office of River Protection has constructed interim surface barriers over a portion of the T and TY tank farms as part of the Interim Surface Barrier Demonstration Project. The interim surface barriers (hereafter referred to as the surface barriers or barriers) are designed to minimize the infiltration of precipitation into the soil zones containing radioactive contaminants and minimize the movement of the contaminants. As part of the demonstration effort, vadose zone moisture is being monitored to assess the effectiveness of the barriers at reducing soil moisture. Solar-powered systems were installed to continuously monitor soil water conditions at four locations in the T (i.e., instrument Nests TA, TB, TC, and TD) and the TY (i.e., instrument Nests TYA and TYB) Farms beneath the barriers and outside the barrier footprint as well as site meteorological conditions. Nests TA and TYA are placed in the area outside the barrier footprint and serve as controls, providing subsurface conditions outside the influence of the surface barriers. Nest TB provides subsurface measurements to assess surface-barrier edge effects. Nests TC, TD, and TYB are used to assess changes in soil-moisture conditions beneath the interim surface barriers.

  14. T Tank Farm Interim Cover Test - Design Plan

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Z. F.; Keller, Jason M.

    2006-07-01

    The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank in 1973. Many of the contaminants from that leak still reside within the vadose zone beneath the T Tank Farm. CH2M Hill Hanford Group, Inc. seeks to minimize movement of this residual contaminant plume by placing an interim cover on the surface. Such a cover is expected to prevent infiltrating water from reaching the plume and moving it further. Pacific Northwest National Laboratory has prepared a design plan to monitor and determine the effectiveness of the interim cover. A three-dimensional numerical simulation of water movement beneath a cover was conducted to guide the design of the plan. Soil water content, water pressure, and temperature will be monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. In fiscal year 2006, two instrument nests will be installed, one inside and one outside of the proposed cover. In fiscal year 2007, two additional instrument nests, both inside the proposed cover, will be installed. Each instrument nest contains a neutron access tube and a capacitance probe (to measure water content), and four heat-dissipation units (to measure pressure head and temperature). A datalogger and a meteorological station will be installed outside of the fence. Two drain gauges will be installed in locations inside and outside the cover for the purpose of measuring soil water flux.

  15. 47 CFR 51.715 - Interim transport and termination pricing.

    Science.gov (United States)

    2010-10-01

    ... has neither established transport and termination rates based on forward-looking economic cost studies... 47 Telecommunication 3 2010-10-01 2010-10-01 false Interim transport and termination pricing. 51... Telecommunications Traffic § 51.715 Interim transport and termination pricing. (a) Upon request from...

  16. Presidential Transition: The Experience of Two Community College Interim Presidents

    Science.gov (United States)

    Thompson, Matthew D.

    2010-01-01

    The purpose of this qualitative case study was to understand the experiences of two community college interim presidents, their characteristics, and how they led institutions following an abrupt presidential departure. There were two fundamental questions framing this research study, 1. How do two interim community college presidents lead…

  17. 50 CFR 660.720 - Interim protection for sea turtles.

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 9 2010-10-01 2010-10-01 false Interim protection for sea turtles. 660.720 Section 660.720 Wildlife and Fisheries FISHERY CONSERVATION AND MANAGEMENT, NATIONAL OCEANIC AND... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§...

  18. 47 CFR 73.404 - Interim hybrid IBOC DAB operation.

    Science.gov (United States)

    2010-10-01

    ... RADIO BROADCAST SERVICES Digital Audio Broadcasting § 73.404 Interim hybrid IBOC DAB operation. (a) The... test operation pursuant to § 73.1620, may commence interim hybrid IBOC DAB operation with digital... No. 99-325. FM stations are permitted to operate with hybrid digital effective radiated power...

  19. Site development interim removable dental prosthesis.

    Science.gov (United States)

    Pasquinelli, Kirk L; Sze, Alexander J; Matosian, Alex J

    2016-07-01

    Transitioning a patient with partial edentulism through hard and soft tissue grafting to an implant restoration with an interim removable dental prosthesis (IRDP) presents a challenge to the restorative dentist. The management of grafted sites requires care, and without the appropriate design, an IRDP may impede surgical outcomes and place the graft at risk for displacement or necrosis. A site development IRDP (SDIRDP) for a grafted site must fulfill restorative goals and promote the surgical objectives for site development. A technique is described for fabricating an SDIRDP that facilitates surgical procedures and maintains prosthetic goals. PMID:26831920

  20. Central waste complex interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    Cain, F.G.

    1995-05-15

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

  1. National NIF Diagnostic Program Interim Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Warner, B

    2002-04-25

    The National Ignition Facility (NIF) has the mission of supporting Stockpile Stewardship and Basic Science research in high-energy-density plasmas. To execute those missions, the facility must provide diagnostic instrumentation capable of observing and resolving in time events and radiation emissions characteristic of the plasmas of interest. The diagnostic instrumentation must conform to high standards of operability and reliability within the NIF environment. These exacting standards, together with the facility mission of supporting a diverse user base, has led to the need for a central organization charged with delivering diagnostic capability to the NIF. The National NIF Diagnostics Program (NNDP) has been set up under the aegis of the NIF Director to provide that organization authority and accountability to the wide user community for NIF. The funds necessary to perform the work of developing diagnostics for NIF will be allocated from the National NIF Diagnostics Program to the participating laboratories and organizations. The participating laboratories and organizations will design, build, and commission the diagnostics for NIF. Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize NIF Core Diagnostics Systems and Cryogenic Target Handing Systems, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NIF Core Diagnostics Systems. Preparation of a Program Execution Plan for NIF Core Diagnostics Systems has been initiated and a current draft is provided as Attachment 1 to this document. The National NIF Diagnostics Program Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope

  2. Interim Reliability Evaluation Program procedures guide

    International Nuclear Information System (INIS)

    This document presents procedures for conducting analyses of a scope similar to those performed in Phase II of the Interim Reliability Evaluation Program (IREP). It documents the current state of the art in performing the plant systems analysis portion of a probabilistic risk assessment. Insights gained into managing such an analysis are discussed. Step-by-step procedures and methodological guidance constitute the major portion of the document. While not to be viewed as a cookbook, the procedures set forth the principal steps in performing an IREP analysis. Guidance for resolving the problems encountered in previous analyses is offered. Numerous examples and representative products from previous analyses clarify the discussion

  3. Retention of long-term interim restorations with sodium fluoride enriched interim cement

    Science.gov (United States)

    Strash, Carolyn

    Purpose: Interim fixed dental prostheses, or "provisional restorations", are fabricated to restore teeth when definitive prostheses are made indirectly. Patients undergoing extensive prosthodontic treatment frequently require provisionalization for several months or years. The ideal interim cement would retain the restoration for as long as needed and still allow for ease of removal. It would also avoid recurrent caries by preventing demineralization of tooth structure. This study aims to determine if adding sodium fluoride varnish to interim cement may assist in the retention of interim restorations. Materials and methods: stainless steel dies representing a crown preparation were fabricated. Provisional crowns were milled for the dies using CAD/CAM technology. Crowns were provisionally cemented onto the dies using TempBond NE and NexTemp provisional cements as well as a mixture of TempBond NE and Duraphat fluoride varnish. Samples were stored for 24h then tested or thermocycled for 2500 or 5000 cycles before being tested. Retentive strength of each cement was recorded using a universal testing machine. Results: TempBond NE and NexTemp cements performed similarly when tested after 24h. The addition of Duraphat significantly decreased the retention when added to TempBond NE. NexTemp cement had high variability in retention over all tested time periods. Thermocycling for 2500 and 5000 cycles significantly decreased the retention of all cements. Conclusions: The addition of Duraphat fluoride varnish significantly decreased the retention of TempBond NE and is therefore not recommended for clinical use. Thermocycling significantly reduced the retention of TempBond NE and NexTemp. This may suggest that use of these cements for three months, as simulated in this study, is not recommended.

  4. PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS

    Energy Technology Data Exchange (ETDEWEB)

    MAY TH

    2008-08-12

    The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revision includes information on additional feed tanks.

  5. Interim report and accounts 1993/94

    International Nuclear Information System (INIS)

    An interim set of accounts and reports is presented here for 1993/1994 for the health science company Amersham International. The company's research programs focus on developments in life science research, nuclear medicine and industrial quality and safety assurance, with particular expertise in the application of radioactivity to labelling and detection at the molecular level. This report which covers the half-year to 30 September 1993 shows promising financial results, with turnover, operating profits and earnings per share all having risen. All life science markets report growth although difficult trading conditions are being reported in Europe. Two products in the Healthcare business have achieved progress, a pain palliation agent for bone metastases has been launched in the United States, and European approval has been gained for a new technetium based heart imaging agent. Further growth is expected for the company. (UK)

  6. Interim Hanford Waste Management Technology Plan

    International Nuclear Information System (INIS)

    The Interim Hanford Waste Management Technology Plan (HWMTP) is a companion document to the Interim Hanford Waste Management Plan (HWMP). A reference plan for management and disposal of all existing and certain projected future radioactive Hanford Site Defense Wastes (HSDW) is described and discussed in the HWMP. Implementation of the reference plan requires that various open technical issues be satisfactorily resolved. The principal purpose of the HWMTP is to present detailed descriptions of the technology which must be developed to close each of the technical issues associated with the reference plan identified in the HWMP. If alternative plans are followed, however, technology development efforts including costs and schedules must be changed accordingly. Technical issues addressed in the HWMTP and HWMP are those which relate to disposal of single-shell tank wastes, contaminated soil sites, solid waste burial sites, double-shell tank wastes, encapsulated 137CsCl and 90SrF2, stored and new solid transuranic (TRU) wastes, and miscellaneous wastes such as contaminated sodium metal. Among the high priority issues to be resolved are characterization of various wastes including early determination of the TRU content of future cladding removal wastes; completion of development of vitrification (Hanford Waste Vitrification Plant) and grout technology; control of subsidence in buried waste sites; and development of criteria and standards including performance assessments of systems proposed for disposal of HSDW. Estimates of the technology costs shown in this report are made on the basis that all identified tasks for all issues associated with the reference disposal plan must be performed. Elimination of, consolidation of, or reduction in the scope of individual tasks will, of course, be reflected in corresponding reduction of overall technology costs

  7. TANK FARM INTERIM SURFACE BARRIER MATERIALS AND RUNOFF ALTERNATIVES STUDY

    Energy Technology Data Exchange (ETDEWEB)

    HOLM MJ

    2009-06-25

    This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

  8. Big Oaks National Wildlife Refuge : Interim Public Access Plan : 2000

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This interim plan covers public access for Big Oaks National Wildlife Refuge. Sections include introduction, safety briefing protocols, entry procedure, types of...

  9. Strategic Review of Medical Training and Career Structure Interim Report

    OpenAIRE

    Department of Health

    2013-01-01

    Click here to download Strategic Review of Medical Training and Career Structure Interim Report PDF 44kb Click here to download Strategic Review of Medical Training and Career Structure Terms of Reference PDF 59KB

  10. Walnut Creek National Wildlife Refuge : Interim hunting plan

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This interim hunting plan for Neal Smith National Wildlife Refuge (formerly Walnut Creek National Wildlife Refuge) outlines hunting guidelines for the Refuge....

  11. Interim Land Use Plan : Muscatatuck National Wildlife Refuge

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This Interim Land Use Plan for Muscatatuck NWR provides a brief history of the Refuge; summarizes present land conditions, needs, and habitat types; and provides an...

  12. Technical bases for interim storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    The experience base for water storage of spent nuclear fuel has evolved since 1943. The technology base includes licensing documentation, standards, technology studies, pool operator experience, and documentation from public hearings. That base reflects a technology which is largely successful and mundane. It projects probable satisfactory water storage of spent water reactor fuel for several decades. Interim dry storage of spent water reactor fuel is not yet licensed in the US, but a data base and documentation have developed. There do not appear to be technological barriers to interim dry storage, based on demonstrations with irradiated fuel. Water storage will continue to be a part of spent fuel management at reactors. Whether dry storage becomes a prominent interim fuel management option depends on licensing and economic considerations. National policies will strongly influence how long the spent fuel remains in interim storage and what its final disposition will be

  13. Interim research assessment 2003-2005 - Computer Science

    OpenAIRE

    Mouthaan, A.J.; Hartel, P.H.

    2007-01-01

    This report primarily serves as a source of information for the 2007 Interim Research Assessment Committee for Computer Science at the three technical universities in the Netherlands. The report also provides information for others interested in our research activities.

  14. Security of radioactive sources: Interim guidance for comment

    International Nuclear Information System (INIS)

    The paper is a brief summary of the material contained in IAEA-TECDOC-1355, Security of Radioactive Sources: Interim Guidance for Comment, covering the topics of threat assessment, Security Groups and performance objectives, and security based categorization. (author)

  15. K basins interim remedial action health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    DAY, P.T.

    1999-09-14

    The K Basins Interim Remedial Action Health and Safety Plan addresses the requirements of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as they apply to the CERCLA work that will take place at the K East and K West Basins. The provisions of this plan become effective on the date the US Environmental Protection Agency issues the Record of Decision for the K Basins Interim Remedial Action, currently planned in late August 1999.

  16. RATIO BETWEEN ACCOUNTING PRINCIPLES AND INTERIM FINANCIAL REPORTING

    OpenAIRE

    Claudia-Elena GRIGORAS-ICHIM

    2010-01-01

    In economic and financial communication, the common language is represented by accounting rules which consent the process of converting the operations afferent to economic development in figures (the situation of the one which prepares the interim financial reports) and a process to convert figures in economic transactions (the situation of the one using the interim financial reports). Therefore arises necessarily the “accounting standardization process” involving a complex of rules capable t...

  17. Dry interim spent fuel storage casks. Licensing, evaluation and operational experience

    International Nuclear Information System (INIS)

    The German concept for the external dry interim storage of spent fuel and high level wastes is based on the used of monolithic ductile iron casks which are licensed according to the transport regulations and the national Atomic Energy Act. The casks ensure the safe confinement of the radioactive inventory over long term storage periods of up to 40 years. Essential for that purpose is the double barrier containment system, consisting of two independent lids sealed with long term resistant metallic gaskets and equipped with an interspace pressure monitoring device. Since the establishment of this dry interim storage concept in Germany in the early 1980s, a great deal of experience has been accumulated and now spent fuel elements from the THTR reactor at Hamm-Uentrop and from the AVR research reactor at Juelich are loaded into CASTOR-THTR/AVR casks under dry conditions and stored in the licensed external dry interim storage facilities in Ahaus and Juelich. These are now routine procedures that started in 1992 and has so far comprise more than 200 casks. A great deal of operational experience exists and has also been gained in process optimization without any serious problems. Much more difficult are the drying and evacuation procedures for casks loaded under wet conditions in the spent fuel storage pond of a nuclear power plant. In this case, special operational procedures involving humidity measurements are applied. Different loading operations in several German power plants have been carried out since 1982 and the first wet loaded cask proposed for storage in the licensed external dry interim storage facility at Gorleben came into operation in July 1994. (author). 4 refs, 5 figs, 1 tab

  18. Evaluation of the Flexural Strength of Interim Restorative Materials in Fixed Prosthodontics

    Science.gov (United States)

    Mehrpour, Hanieh; Farjood, Ehsan; Giti, Rashin; Barfi Ghasrdashti, Alireza; Heidari, Hossein

    2016-01-01

    Statement of the Problem Mechanical properties of interim restorations are considered as important factors specially when selecting materials for long-term application or for patients with para-functional habits. Flexural strength is one of the most important components of these restorations. Purpose The purpose of this study was to compare the flexural strength of five interim restorative materials. Materials and Method Fifty identical samples sized 25×2×2-mm were made from five interim materials (TempSpan; Protemp 4, Unifast III, Trim, and Revotek LC) according to ADA specification #27. The specimens were stored in artificial saliva for 2 weeks and then thermocycled for 2500 cycles (5-55˚C). A standard three-point bending test was conducted on the specimens with a universal testing machine at a crosshead speed of 0.75mm/min. Data were analyzed by using one-way ANOVA and Tamhane’s post-hoc tests to measure the flexural strength of temporary materials. Results One of the bis-acryl resins (TempSpan) showed the highest, and the light polymerized resin (Revotek LC) showed the lowest flexural strength. The mean values of flexural strength (MPa) for the examined materials were as follow: TempSpan=120.00, Protemp 4=113.00, Unifast III=64.20, Trim= 63.73 and Revotek LC=47.16. There were significant differences between all materials except Trim and Unifast III which did not show any statistical significant difference. Conclusion Bis-acryl resins were statistically superior to traditional methacrylate and light-cured resins. Therefore, application of bis-acryl resins should be deliberated in patients with heavy occlusion and in cases that need long-term use of interim restorations. PMID:27602395

  19. 2. interim report on radiation situation in Finland from 5 to 16 May 1986

    International Nuclear Information System (INIS)

    This second interim report is a continuation of the first 'Fallout situation in Finland from April 26 to May 4' STUK-B-VALO-44. It deals with the results from external radiation measurements and analysis of environmental and foodstuff samples between 5 and 16 May, i.e. the development of the situation after the fallout peak. The whole-body counter measurements of tourists returning from the Soviet Union and from other countries in Eastern Europe after the accident are also reported

  20. The UN Interim Administration Mission in Kosovo (UNMIK

    Directory of Open Access Journals (Sweden)

    Alfonso J. Iglesias Velasco

    2001-12-01

    Full Text Available The current situation in the Province of Kosovo in the Republic of Serbia within the Yugoslav State became unsustainable in the late 1990´s as a result of the repressive policies of the Serbian authorities toward the Kosovar Albanians. International efforts tofind a peaceful solution to the conflict were unsuccessful, in large measure on account of Serbian intransigence, and the intensification of the conflict with tragic consequences for the Kosovar civilian population led the Atlantic Alliance in the spring of 1999 to a carryout a military intervention of, to say the least, dubious legality under international law, which in turn forced Serbian leaders to bow to the application of the solution worked out by the international community in the Rambouillet Accords and set down in UN Security Council Resolution 1244 (1999 of June 10, 1999. This resolution provided for two international entities in the province, one a security force (KFOR and the other civilian, the UN Interim Administration Mission (UNMIK. This paper analyzes the mission’s mandate and structure as well as the evolution of the peace process.

  1. SHORT COMMUNICATION: The kilogram redefinition—an interim solution

    Science.gov (United States)

    Flowers, J. L.; Petley, B. W.

    2005-10-01

    The role of measurements of the fundamental constants continues to be extremely valuable in underpinning the basic units of metrology. It is concluded that it might be preferable to sustain the present definition of the kilogram for an interim period by having a mise en pratique accompanying the definition, much as is currently done with the specified methods of realizing the metre. Central to this proposal is our view that there is considerable latitude in the interpretation of the present definition of the kilogram and that this can be exploited while always disseminating a consistent mass unit. This would also permit the present methods of maintaining and disseminating the kilogram to continue to be employed throughout the world where necessary at the present accuracy until the new technology could be phased in. An alternative definition of the kilogram, formulated in terms of frequency, is also introduced. This would give an ampere that fundamentally depends on the elementary charge, e, without the need to change the present definitions of the ampere and ohm.

  2. Extreme Heat Stress trends in ERA Interim 1979-2011

    Science.gov (United States)

    Buzan, J. R.; Huber, M.

    2012-12-01

    Heat stress is a function of temperature and humidity, and is therefore subject to the covariance of the two quantities. One of the robust predictions from climate change is an increase in temperatures across the planet, and therefore heat stress is projected to increase, however the covariance with humidity is less sure. It has been proposed that in future climate, significant portions of the land surface become subject to life threatening heat stress levels to humans and mammals. There are numerous methods and metrics for calculating heat stress, however, the majority use atmospheric state variables (pressure, temperature, and specific humidity), to measure the thermodynamic state of the atmosphere or estimate thermal load on humans and mammals. Here we present calculations of the evolution of heat stress for the past 3 decades using the European Centre for Medium-Range Weather Forecasts (ECMWF) ERA Interim reanalysis data product from near surface boundary layer state variables. We characterize both spatial and temporal trends with a variety of the most commonly used heat stress metrics (wet bulb temperatures, heat index, etc.). The metrics are calculated from 4x daily values to capture both the diurnal cycle and the daily peak values for these indices.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  4. Data Analysis of GPM Constellation Satellites-IMERG and ERA-Interim precipitation products over West of Iran

    Science.gov (United States)

    Sharifi, Ehsan; Steinacker, Reinhold; Saghafian, Bahram

    2016-04-01

    Precipitation is a critical component of the Earth's hydrological cycle. The primary requirement in precipitation measurement is to know where and how much precipitation is falling at any given time. Especially in data sparse regions with insufficient radar coverage, satellite information can provide a spatial and temporal context. Nonetheless, evaluation of satellite precipitation is essential prior to operational use. This is why many previous studies are devoted to the validation of satellite estimation. Accurate quantitative precipitation estimation over mountainous basins is of great importance because of their susceptibility to hazards. In situ observations over mountainous areas are mostly limited, but currently available satellite precipitation products can potentially provide the precipitation estimation needed for meteorological and hydrological applications. One of the newest and blended methods that use multi-satellites and multi-sensors has been developed for estimating global precipitation. The considered data set known as Integrated Multi-satellitE Retrievals (IMERG) for GPM (Global Precipitation Measurement) is routinely produced by the GPM constellation satellites. Moreover, recent efforts have been put into the improvement of the precipitation products derived from reanalysis systems, which has led to significant progress. One of the best and a worldwide used model is developed by the European Centre for Medium Range Weather Forecasts (ECMWF). They have produced global reanalysis daily precipitation, known as ERA-Interim. This study has evaluated one year of precipitation data from the GPM-IMERG and ERA-Interim reanalysis daily time series over West of Iran. IMERG and ERA-Interim yield underestimate the observed values while IMERG underestimated slightly and performed better when precipitation is greater than 10mm. Furthermore, with respect to evaluation of probability of detection (POD), threat score (TS), false alarm ratio (FAR) and probability

  5. Radiological characterisation of waste in interim storage building of COVRA

    International Nuclear Information System (INIS)

    At COVRA spatial dose rate distribution measurements were performed in December 2004 and December 2006 in the interim L/ILW storage building (LOG). This storage facility consists out of four large storage halls (height x width x depth 7 m x 40 m x 70 m) each with a volume of about 20000 m3. The scope of this study is to investigate the benefits of the waste storage strategy and procedures for minimization of the dose to the workers and the public. The main aim of the measurements in 2004 was: to validate the applied L/ILW storage strategy - to examine, if spatial collected data can be used to detect unforeseen differences in radiation level. The results of these measurements of spatial dose showed a number of unforeseen hotspots at different locations, so that it could be concluded that the applied storage strategy and procedures has to be improved. Further the dose rate at the height of 6 m, mainly responsible for the sky-shine dose rate, being an important part of the dose rate to the public at the site boundary, has to be reduced by more shielding. In December 2006 a second serial of spatial radiological and non-radiological data have been collected. The applied nondestructive INDSS-R (Indoor Survey System-Radiation ) method has been improved, so that the following 3-dimensional data could be collected between 0.5 m and 5.5 m: - dose rate (by pressurized ionisation chamber). nuclide depended gamma photon flux (3 x 3 NaI). - temperature and relative humidity. These last two non-radiological parameters were measured to verify the storage conditions of the waste. The main aim of these 3 dimensional collection was to verify the second stated aim of 2004. (authors)

  6. Permitting plan for the high-level waste interim storage

    International Nuclear Information System (INIS)

    This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist

  7. Safety report for Central Interim Storage facility for radioactive waste from small producers

    International Nuclear Information System (INIS)

    protection and remediation of minor defects in the facility. The safety report also incorporates the implementation projects for the inventory rearrangement and the projected waste quantities up to 2013, when the LILW repository should be available. The most important part of the safety report deals with safety analyses of all relevant operational conditions which could influence safety of the storage and its inventory, taking into account also the phase of reconstruction works. The Safety Report is prepared in accordance with the requirements of Regulation E2 (Pravilnik E2) and The Act on Ionising Radiation Protection and Nuclear Safety from 2002. After defining the objective of the safety report, the chapters deal with the following topics: The safety approach to the LILW storage, Description and location analysis of the Central interim storage, Technical characteristic of the Central interim storage, Safety analysis of the Central interim storage, Organizational measures for construction and pre-operational testing, Organizational measures for commissioning and normal operation of the Central interim storage, Operational conditions and limitations, Ionizing radiation protection service, its methods and equipment, Radioactive waste management and disposal, Review of the plans, measures and procedures to prevent radiological accidents, Quality assurance programme, Review of the measures for physical protection of the LILW storage and stored radioactive waste, Planned measures and necessary equipment for closure of the Central interim storage. The details on preparation of the Safety report, including the dilemmas and comments on different chapters, are presented in this paper. The most important findings of the safety analysis are also given.(author)

  8. Radioactive waste interim storage in Germany; Zwischenlagerung von radioaktiven Abfaellen in Deutschland

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-12-15

    The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

  9. Interim results from the characterization testing of the Engineering Development (EDM) rubidium clocks for satellite applications

    Science.gov (United States)

    Powers, Edward D., Jr.; Danzy, Fredrick

    1990-01-01

    Some interim results from the environmental testing program to evaluate the Engineering Design Model (EDM) of the EG and G Spaceborne Rubidium Clock are presented. This effort is in support of the Global Positioning System (GPS) BLOCK IIR program and is intended to characterize the performance of EG and G design for BLOCK IIR satellite applications. Two EG and G EDM units are currently under test at NRL's Clock Test Facility to measure the long-term frequency stability, drift, and frequency versus temperature characteristics.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  11. Single-shell tank interim stabilization project plan

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.E.

    1998-03-27

    Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE`s Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

  12. Interim process report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Sellin, Patrick (ed.)

    2004-08-01

    This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses.

  13. 78 FR 56750 - Interim Staff Guidance on Environmental Issues Associated With New Reactors

    Science.gov (United States)

    2013-09-13

    ... COMMISSION Interim Staff Guidance on Environmental Issues Associated With New Reactors AGENCY: Nuclear... Notice: Draft Interim Staff Guidance on Environmental Issues Associated with New Reactors. ML12326A742 Interim Staff Guidance-026, Environmental Issues Associated with New Reactors. ML12326A811...

  14. Corporate Risk Disclosure: A Content Analysis of Swedish Interim Reports

    OpenAIRE

    Khaledi, Soheila

    2014-01-01

    The aim of this research is to examine the determinants of the level of corporate risk disclosure (CRD) in the interim reports of Swedish non-financial companies. A quantitative research approach is used, the sample data of which consist of 166 firms with 4,849 interim reports over a 10-year period. By utilizing the notion of risk and its definition, I have distinguished three categories of risk, namely risk as uncertainty, risk as threat and risk as opportunity. A systematic content analysis...

  15. Interim safety basis for fuel supply shutdown facility

    International Nuclear Information System (INIS)

    This ISB in conjunction with the new TSRs, will provide the required basis for interim operation or restrictions on interim operations and administrative controls for the Facility until a SAR is prepared in accordance with the new requirements. It is concluded that the risk associated with the current operational mode of the Facility, uranium closure, clean up, and transition activities required for permanent closure, are within Risk Acceptance Guidelines. The Facility is classified as a Moderate Hazard Facility because of the potential for an unmitigated fire associated with the uranium storage buildings

  16. Wide-Field Infrared Survey Telescope (WFIRST) Interim Report

    Science.gov (United States)

    Green, J.; Schechter, P.; Baltay, C.; Bean, R.; Bennett, D.; Brown, R.; Conselice, C.; Donahue, M.; Gaudi, S.; Lauer, T.; Perlmutter, S.; Rauscher, B.; Rhodes, J.; Roellig, T.; Stern, D.; Sumi, T.; Gerhels, N.; Sambruna, R.; Barry, R. K.; Content, D.; Grady, K; Jackson, C.; Kruk, J.; Melton, M.; Rioux, N.

    2011-01-01

    The New Worlds, New Horizons (NWNH) in Astronomy and Astrophysics 2010 Decadal Survey prioritized the community consensus for ground-based and space-based observatories. Recognizing that many of the community s key questions could be answered with a wide-field infrared survey telescope in space, and that the decade would be one of budget austerity, WFIRST was top ranked in the large space mission category. In addition to the powerful new science that could be accomplished with a wide-field infrared telescope, the WFIRST mission was determined to be both technologically ready and only a small fraction of the cost of previous flagship missions, such as HST or JWST. In response to the top ranking by the community, NASA formed the WFIRST Science Definition Team (SDT) and Project Office. The SDT was charged with fleshing out the NWNH scientific requirements to a greater level of detail. NWNH evaluated the risk and cost of the JDEM-Omega mission design, as submitted by NASA, and stated that it should serve as the basis for the WFIRST mission. The SDT and Project Office were charged with developing a mission optimized for achieving the science goals laid out by the NWNH re-port. The SDT and Project Office opted to use the JDEM-Omega hardware configuration as an initial start-ing point for the hardware implementation. JDEM-Omega and WFIRST both have an infrared imager with a filter wheel, as well as counter-dispersed moderate resolution spectrometers. The primary advantage of space observations is being above the Earth's atmosphere, which absorbs, scatters, warps and emits light. Observing from above the atmosphere enables WFIRST to obtain precision infrared measurements of the shapes of galaxies for weak lensing, infrared light-curves of supernovae and exoplanet microlensing events with low systematic errors, and infrared measurements of the H hydrogen line to be cleanly detected in the 1baryon acoustic oscillation (BAO) dark energy measurements. The Infrared Astronomical

  17. 32 CFR 94.4 - Policy and procedures.

    Science.gov (United States)

    2010-07-01

    ... in DoD Instruction 1332.15, “Early Release of Military Enlisted Personnel for College or Vocational... orientation programs will include advice and assistance to interested aliens in completing and submitting...

  18. 40 CFR 266.103 - Interim status standards for burners.

    Science.gov (United States)

    2010-07-01

    ... during interim status to industrial furnaces (e.g., kilns, cupolas) that feed hazardous waste for a... HAZARDOUS WASTE MANAGEMENT FACILITIES Hazardous Waste Burned in Boilers and Industrial Furnaces § 266.103... and industrial furnaces that burn hazardous waste where such standards define the...

  19. 17 CFR 210.10-01 - Interim financial statements.

    Science.gov (United States)

    2010-04-01

    ... ACT OF 1934, PUBLIC UTILITY HOLDING COMPANY ACT OF 1935, INVESTMENT COMPANY ACT OF 1940, INVESTMENT... registrants reporting under § 210.9 shall show investment securities gains or losses separately regardless of...)(11) of Regulation S-K, (17 CFR 229.601(b)(11)). (3) If, during the most recent interim...

  20. Single Shell Tank (SST) Interim Stabilization Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    VLADIMIROFF, D.T.; BOYLES, V.C.

    2000-05-22

    This project plan establishes the management framework for the conduct of the CHG Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organization structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

  1. 46 CFR 308.103 - Insured amounts under interim binder.

    Science.gov (United States)

    2010-10-01

    ... INSURANCE War Risk Hull and Disbursements Insurance § 308.103 Insured amounts under interim binder. (a... vessel had been requisitioned for title under section 902(a) of the Merchant Marine Act, 1936, as amended (46 App. U.S.C. 1242(a)) at the time of the attachment of the insurance under said policy:...

  2. Single-shell tank interim stabilization project plan

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.E.

    1998-05-11

    This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

  3. 40 CFR 80.141 - Interim detergent gasoline program.

    Science.gov (United States)

    2010-07-01

    ... registered by its manufacturer under 40 CFR part 79 according to the specifications in paragraphs (c) (1... hearing procedures shall be informal, and the hearing shall not be subject to or governed by 40 CFR part... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Interim detergent gasoline program....

  4. Interim analysis in long-term clinical trials

    NARCIS (Netherlands)

    G.A. van Es (Gerrit Anne)

    1990-01-01

    textabstractThe purpose of this dissertation is to evaluate the usefulness of both stopping rules and estimation methods in long-term clinical trials with interim analyses. The ASPECT trial, a long-term clinical trial to assess the effect of anticoagulant therapy on mortality in patients after myoca

  5. 42 CFR 417.808 - Interim per capita payments.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 3 2010-10-01 2010-10-01 false Interim per capita payments. 417.808 Section 417.808 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES... efficiency and economy, and will not result in excessive adjustment at the end of the reporting period....

  6. ASPECTS CONCERNING INTERIM FINANCIAL REPORTING IN ROMANIA: STANDARDS AND REGULATIONS

    Directory of Open Access Journals (Sweden)

    Aristita Rotila

    2014-12-01

    Full Text Available The mechanisms employed for the communication of accounting information that is necessary for users in their economic decision-making process consist of the financial statements of an entity. All legal entities, no matter the domain of their activity, have the obligation to draw up annual financial statements for every completed financial year. For certain categories of entities, reporting obligations are also required for periods other than the annual reporting, throughout the financial year. It is the case of interim financial reporting. At the level of the international accounting framework, the aspects related to interim financial reporting are the subject of a separate standard, namely, IAS 34 Interim Financial Reporting. In Romania, the current system of accounting regulations concerning the annual financial statements comprises accounting regulations that comply with the European directives and which apply to the various categories of entities, on the one hand and, on the other, accounting regulations in line with the IFRS, which are applicable to other classes of entities from certain activity sectors. The accounting regulations that apply to each category refer to, among other things, the contents and the format of financial statements that have to be presented. Analysing the system of norms and regulations, this article identifies the requirements concerning interim financial reporting in Romania, with reference to the different types of entities.

  7. Minish Named Interim Head of Admissions at Virginia Tech

    OpenAIRE

    Virginia Tech News

    2004-01-01

    Roberta M.Minish, of Blacksburg, Va., associate dean emeritus of Virginia Tech's former College of Human Sciences and Education, has been named interim director of undergraduate admissions at the university, effective Jan. 19. She fills the position left vacant in December with the resignation of Karen Torgersen.

  8. Penalty Inflation Adjustments for Civil Money Penalties. Interim Final Rule.

    Science.gov (United States)

    2016-06-27

    In accordance with the Federal Civil Penalties Inflation Adjustment Act of 1990, as amended by the Debt Collection Improvement Act of 1996, and further amended by the Bipartisan Budget Act of 2015, section 701: Federal Civil Penalties Inflation Adjustment Act Improvements Act of 2015, this interim final rule incorporates the penalty inflation adjustments for the civil money penalties contained in the Social Security Act

  9. St. Francis Rain Garden Water Quality Sampling Interim Data Report; Total Nitrogen, Total Phosphorus, Sediments or Solids, and E. Coli for the period April to June, 2014

    Science.gov (United States)

    This interim data reported is being provided per request to the Metropolitan Sewer District (MSD) to provide summary statistics on a limited set of water quality parameters as measured at the St. Francis Rain Garden site in the Lick Run Valley as it pertains to MSD's Project Grou...

  10. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    International Nuclear Information System (INIS)

    CH2M HILL Plateau Remediation Company (CH2M HILL PRC) is proud to submit the Slightly Irradiated Fuel (SIF) Interim Disposition Project for consideration by the Project Management Institute as Project of the Year for 2010. The SIF Project was a set of six interrelated sub-projects that delivered unique stand-alone outcomes, which, when integrated, provided a comprehensive and compliant system for storing high risk special nuclear materials. The scope of the six sub-projects included the design, construction, testing, and turnover of the facilities and equipment, which would provide safe, secure, and compliant Special Nuclear Material (SNM) storage capabilities for the SIF material. The project encompassed a broad range of activities, including the following: Five buildings/structures removed, relocated, or built; Two buildings renovated; Structural barriers, fencing, and heavy gates installed; New roadways and parking lots built; Multiple detection and assessment systems installed; New and expanded communication systems developed; Multimedia recording devices added; and A new control room to monitor all materials and systems built. Project challenges were numerous and included the following: An aggressive 17-month schedule to support the high-profile Plutonium Finishing Plant (PFP) decommissioning; Company/contractor changeovers that affected each and every project team member; Project requirements that continually evolved during design and construction due to the performance- and outcome-based nature ofthe security objectives; and Restrictions imposed on all communications due to the sensitive nature of the projects In spite of the significant challenges, the project was delivered on schedule and $2 million under budget, which became a special source of pride that bonded the team. For years, the SIF had been stored at the central Hanford PFP. Because of the weapons-grade piutonium produced and stored there, the PFP had some of the tightest security on the Hanford

  11. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    NORTON SH

    2010-02-23

    CH2M HILL Plateau Remediation Company (CH2M HILL PRC) is proud to submit the Slightly Irradiated Fuel (SIF) Interim Disposition Project for consideration by the Project Management Institute as Project of the Year for 2010. The SIF Project was a set of six interrelated sub-projects that delivered unique stand-alone outcomes, which, when integrated, provided a comprehensive and compliant system for storing high risk special nuclear materials. The scope of the six sub-projects included the design, construction, testing, and turnover of the facilities and equipment, which would provide safe, secure, and compliant Special Nuclear Material (SNM) storage capabilities for the SIF material. The project encompassed a broad range of activities, including the following: Five buildings/structures removed, relocated, or built; Two buildings renovated; Structural barriers, fencing, and heavy gates installed; New roadways and parking lots built; Multiple detection and assessment systems installed; New and expanded communication systems developed; Multimedia recording devices added; and A new control room to monitor all materials and systems built. Project challenges were numerous and included the following: An aggressive 17-month schedule to support the high-profile Plutonium Finishing Plant (PFP) decommissioning; Company/contractor changeovers that affected each and every project team member; Project requirements that continually evolved during design and construction due to the performance- and outcome-based nature ofthe security objectives; and Restrictions imposed on all communications due to the sensitive nature of the projects In spite of the significant challenges, the project was delivered on schedule and $2 million under budget, which became a special source of pride that bonded the team. For years, the SIF had been stored at the central Hanford PFP. Because of the weapons-grade piutonium produced and stored there, the PFP had some of the tightest security on the Hanford

  12. Wayne Interim Storage Site environmental report for calendar year 1989, Wayne, New Jersey

    International Nuclear Information System (INIS)

    The environmental monitoring program, begun in 1984, was continued in 1989 at the Wayne Interim Storage Site (WISS), a US Department of Energy (DOE) facility located in Wayne Township, New Jersey. The WISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive material remains from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The monitoring program at WISS measures radon and thoron concentrations in air; external gamma radiation levels; and uranium, radium, and thorium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. The radiation dose was calculated for a hypothetical maximally exposed individual to verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and to assess its potential effects on public health. This report presents the findings of the environmental monitoring program conducted at the Wayne Interim Storage Site (WISS) during calendar year 1989. 26 refs., 12 figs., 16 tabs

  13. Maywood Interim Storage Site environmental report for calendar year 1989, Maywood, New Jersey

    International Nuclear Information System (INIS)

    The environmental monitoring program, which began in 1984, was continued in 1989 at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. MISS is currently used for storage of soils contaminated with low-level radioactivity. MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials are present. The monitoring program at MISS measures thoron and radon concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. The radiation dose was calculated for a hypothetical maximally exposed individual to verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and to assess its potential effects on public health. This report presents the results of the environmental monitoring program conducted at the US Department of Energy's (DOE) Maywood Interim Storage Site (MISS) during calendar year 1989. Environmental monitoring began at MISS in 1984. 19 refs., 23 figs., 14 tabs

  14. Does the radiation from the interim storage in Gorleben affect the sex ratio of newborn children?

    International Nuclear Information System (INIS)

    In the professional world but especially in public, the question is discussed whether ionizing radiation from nuclear facilities has a significant impact on the secondary sex ratio of newborn children in the vicinity of the plants. This issue is of exceptional importance in the region around Gorleben, where the opposition to nuclear facilities and activities for decades is particularly strong. At the site borders of the interim storage facility (TBL-G) of GNS the effective individual dose is about 0.2 mSv per year, mainly caused by neutron irradiation from 108 casks with high-level radioactive waste from reprocessing. In the surrounding villages there is no radiation measurable. Statistical studies allegedly have shown evidence that in some villages in the area and during certain periods, proportionately fewer girls were born in comparison to the average for the Federal Republic of Germany. Based on these purely statistical results henceforward was also alleged that neutron-induced secondary effects such as activation or secondary gamma radiation would be responsible for it. Monte Carlo calculations and special measurements yielded values of the dose at the plant border for activation products less than E-04 mSv/a and for secondary gamma radiation of about E-03 mSv/a. These results indicate that the ionizing radiation from the Gorleben interim storage facility cannot be held accountable for shifts of the secondary sex ratio.

  15. International Peer Review of Swedish Nuclear Fuel and Waste Management Company's SR-Can interim report

    International Nuclear Information System (INIS)

    demonstration (e.g. allocation of safety to different barrier functions and the role of dilution); Basis and methods for scenario selection and evaluation; Assessment of model framework for consequence analysis and compliance evaluation (e.g. justification of models, and parameters); Methods for biosphere modelling including the transition zone from basement rock to quaternary deposits and ecosystems; Methods for risk analysis, including the use of probabilistic methods, uncertainty and sensitivity analysis, estimation of probabilities, averaging of risk; and Quality assurance measures including handling of expert judgments. Among its conclusions, the IRT considers that the SR-Can Interim Report describes a logical methodology for undertaking a safety assessment that could be used as a component of a safety case to support a licence application. SKB's assessment methodology also includes some innovative and positive components, such as the use of safety function indicators and analytical models. From the IRT's perspective, the main deficiencies in SKB's programme and approach relate less to the methodology and more to the rigour with which safety assessment needs to be conducted to support a formal licence application. There are a number of areas, for example in the development of scenarios and in the management and treatment of uncertainty, where current evidence suggests a need for greater clarity and traceability. More generally, it is recommended that SKB should ensure that all aspects of the safety assessment are conducted in accordance with auditable project-specific guidance and QA procedures. In view of the above, and the fact that SKB has acknowledged that some further development work remains to be done, the IRT believes that it could be a challenge for SKB to conduct and present a safety assessment of suitable quality within the currently proposed timescale for delivery of the SR-Can assessment and the 2006 licence application

  16. Interim assessment of the VAL automated guideway transit system. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Anagnostopoulos, G.

    1981-11-01

    This report describes an interim assessment of the VAL (Vehicules Automatiques Legers or Light Automated Vehicle) AGT system which is currently under construction in Lille, France, and which is to become fully operational in December 1983. This report contains a technical description and performance data resulting from a demonstration test program performed concurrently in August 1980. VAL is the first driverless AGT urban system application in France. The system operates at grade, elevated, and in tunnels on an exclusive concrete dual-lane guideway that is 12.7 kilometers long. The configuration of the system is a push-pull loop operating between 17 on-line stations. The system is designed to provide scheduled operation at 60-second headways and a normal one-way capacity of 7440 passengers per hour per direction with 55 percent of the passengers seated. Two pneumatic-tired vehicles are coupled into a single vehicle capable of carrying 124 passengers at line speeds of 60 km/hr. During the course of the demonstration test program, VAL demonstrated that it could achieve high levels of dependability and availability and could perform safely under all perceivable conditions.

  17. Verification of the new ECMWF ERA-Interim reanalysis over France

    Science.gov (United States)

    Szczypta, C.; Calvet, J.-C.; Albergel, C.; Balsamo, G.; Boussetta, S.; Carrer, D.; Lafont, S.; Meurey, C.

    2011-02-01

    An evaluation of the global ECMWF atmospheric reanalysis ERA-Interim (with a 0.5° grid) is performed over France, based on the high resolution (8 km) SAFRAN atmospheric reanalysis. The ERA-Interim precipitation, Incoming Solar Radiation (ISR), air temperature, air humidity, and wind speed, are compared with their SAFRAN counterparts. Also, interpolated in situ ISR observations are used in order to consolidate the evaluation of this variable. The daily precipitation estimates produced by ERA-Interim over France correlate very well with SAFRAN. However, the values are underestimated by 27%. A GPCP-corrected version of ERA-Interim is less biased (13%). The ERA-Interim estimates of ISR correlate very well with SAFRAN and with in situ observations on a daily basis. Whereas SAFRAN underestimates the ISR by 6 Wm-2, ERA-Interim overestimates the ISR by 10 Wm-2. In order to assess the impact of the ERA-Interim errors, simulations of the ISBA-A-gs land surface model are performed over the SMOSREX grassland site in southwestern France using ERA-Interim (with and without GPCP rescaling) and SAFRAN. Latent and sensible heat fluxes are simulated, together with carbon dioxide fluxes. The rescaled ERA-Interim performs better than the original ERA-Interim and permits to achieve flux scores similar to those obtained with SAFRAN.

  18. Verification of the new ECMWF ERA-Interim reanalysis over France

    Directory of Open Access Journals (Sweden)

    C. Szczypta

    2011-02-01

    Full Text Available An evaluation of the global ECMWF atmospheric reanalysis ERA-Interim (with a 0.5° grid is performed over France, based on the high resolution (8 km SAFRAN atmospheric reanalysis. The ERA-Interim precipitation, Incoming Solar Radiation (ISR, air temperature, air humidity, and wind speed, are compared with their SAFRAN counterparts. Also, interpolated in situ ISR observations are used in order to consolidate the evaluation of this variable. The daily precipitation estimates produced by ERA-Interim over France correlate very well with SAFRAN. However, the values are underestimated by 27%. A GPCP-corrected version of ERA-Interim is less biased (13%. The ERA-Interim estimates of ISR correlate very well with SAFRAN and with in situ observations on a daily basis. Whereas SAFRAN underestimates the ISR by 6 Wm−2, ERA-Interim overestimates the ISR by 10 Wm−2. In order to assess the impact of the ERA-Interim errors, simulations of the ISBA-A-gs land surface model are performed over the SMOSREX grassland site in southwestern France using ERA-Interim (with and without GPCP rescaling and SAFRAN. Latent and sensible heat fluxes are simulated, together with carbon dioxide fluxes. The rescaled ERA-Interim performs better than the original ERA-Interim and permits to achieve flux scores similar to those obtained with SAFRAN.

  19. Verification of the new ECMWF ERA-Interim reanalysis over France

    Directory of Open Access Journals (Sweden)

    C. Szczypta

    2010-09-01

    Full Text Available An evaluation of the global ECMWF atmospheric reanalysis ERA-Interim (with a 0.5° grid is performed over France, based on the high resolution (8 km SAFRAN atmospheric reanalysis. The ERA-Interim precipitation, Incoming Solar Radiation (ISR, air temperature, air humidity, and wind speed, are compared with their SAFRAN counterparts. Also, interpolated in situ ISR observations are used in order to consolidate the evaluation of this variable. The daily precipitation estimates produced by ERA-Interim over France correlate very well with SAFRAN. However, the values are underestimated by 26%. A GPCP-corrected version of ERA-Interim is less biased (10–15%. The ERA-Interim estimates of ISR correlate very well with SAFRAN and with in situ observations on a daily basis. Whereas SAFRAN underestimates the ISR by 6–8 W m−2, ERA-Interim overestimates the ISR by 9–10 W m−2. In order to assess the impact of the ERA-Interim errors, simulations of the ISBA-A-gs land surface model are performed over the SMOSREX grassland site in southwestern France using ERA-Interim (with and without GPCP rescaling and SAFRAN. Latent and sensible heat fluxes are simulated, together with carbon dioxide fluxes. The rescaled ERA-Interim performs better than the original ERA-Interim and permits to achieve flux scores similar to those obtained with SAFRAN.

  20. T Tank Farm Interim Surface Barrier Demonstration--Vadose Zone Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Z. F.; Keller, Jason M.; Strickland, Christopher E.

    2007-04-01

    The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank in 1973. Many of the contaminants from that leak still reside within the vadose zone beneath the T Tank Farm. CH2M Hill Hanford Group, Inc. seeks to minimize movement of this residual contaminant plume by placing an interim barrier on the surface. Such a barrier is expected to prevent infiltrating water from reaching the plume and moving it further. A plan has been prepared to monitor and determine the effectiveness of the interim surface barrier. Soil water content and water pressure will be monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. In fiscal year 2006, two instrument nests were installed. Each instrument nest contains a neutron probe access tube, a capacitance probe, four heat-dissipation units, and a drain gauge to measure soil water flux. A meteorological station has been installed outside of the fence. In fiscal year 2007, two additional instrument nests are planned to be installed beneath the proposed barrier.

  1. Maywood Interim Storage Site: Annual environmental report for calendar year 1990, Maywood, New Jersey

    International Nuclear Information System (INIS)

    Environmental monitoring of the US Department of Energy's (DOE) Maywood Interim Storage Site (MISS) and surrounding area began in 1984. MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The MISS Environmental monitoring programs was established to accommodate facility characteristics, applicable regulations, hazard potential, quantities and concentrations of materials released, extent and use of affected land and water, and local public interest or concern. The environmental monitoring program at MISS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium, radium-226, and thorium-232 concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in surface water, sediment, and groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) standards; federal, state, and local applicable or relevant and appropriate requirements (ARARs); and/or DOE derived concentration guidelines (DCGs). Environmental standards, ARARs, and DCGs are established to protect public health and the environment. Results from the 1990 environmental monitoring program show that concentrations of the contaminants of concern were all below applicable standards. Because the site is used only for interim storage and produces no processing effluents, all monitoring, except for radon and direct gamma radiation, was done on a quarterly basis. 18 refs., 17 figs., 28 tabs

  2. Methods for assessing environmental impacts of a FUSRAP property-cleanup/interim-storage remedial action

    International Nuclear Information System (INIS)

    This document provides a description of a property-cleanup/interim-storage action, explanation of how environmental impacts might occur, comprehensive treatment of most potential impacts that might occur as a result of this type of action, discussion of existing methodologies for estimating and assessing impacts, justification of the choice of specific methodologies for use in FUSRAP environmental reviews, assessments of representative impacts (or expected ranges of impacts where possible), suggested mitigation measures, and some key sources of information. The major topical areas covered are physical and biological impacts, radiological impacts, and socioeconomic impacts. Some project-related issues were beyond the scope of this document, including dollar costs, specific accident scenarios, project funding and changes in Congressional mandates, and project management (contracts, labor relations, quality assurance, liability, emergency preparedness, etc.). These issues will be covered in other documents supporting the decision-making process. Although the scope of this document covers property-cleanup and interim-storage actions, it is applicable to other similar remedial actions. For example, the analyses discussed herein for cleanup activities are applicable to any FUSRAP action that includes site cleanup

  3. Identification and intercomparison of surface-based inversions over Antarctica from IASI, ERA-Interim, and Concordiasi dropsonde data

    Science.gov (United States)

    Boylan, Patrick; Wang, Junhong; Cohn, Stephen A.; Hultberg, Tim; August, Thomas

    2016-08-01

    Surface-based temperature inversions (SBIs) occur frequently over Antarctica and play an important role in climate and weather. Antarctic SBIs are examined during the austral spring of 2010 using measurements from dropsondes, ERA-Interim Atmospheric Reanalysis Model, and the recently released version 6 of the Infrared Atmospheric Sounding Interferometer (IASI) level 2 product. A SBI detection algorithm is applied to temperature profiles from these data sets. The results will be used to determine if satellite and reanalysis products can accurately characterize SBIs, and if so, then they may be used to study SBIs outside of the spring 2010 study period. From the dropsonde data, SBIs occur in 20% of profiles over sea ice and 54% of profiles over land. IASI and ERA-Interim surface air temperatures are found to be significantly warmer than dropsonde observations at high plateau regions, while IASI surface air temperatures are colder over sea ice. IASI and ERA-Interim have a cold bias at nearly all levels above the surface when compared to the dropsonde. SBIs are characterized by their frequency, depth, and intensity. It is found that SBIs are more prevalent, deeper, and more intense over the continent than over sea ice, especially at higher surface elevations. Using IASI and ERA-Interim data the detection algorithm has a high probability of detection of SBIs but is found to severely overestimate the depth and underestimate the intensity for both data sets. These overestimation and underestimation are primarily due to the existence of extremely shallow inversion layers that neither satellite nor reanalysis products can resolve.

  4. EMDEX Project Residential Study: Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Bracken, T.D.; Rankin, R.F.; Alldredge, J.R.; Senior, R.S. (Bracken (T. Dan), Inc., Portland, OR (United States))

    1993-02-01

    The Electric and Magnetic Field Project for Utilities - The EMDEX Project Residential Study described in this report was designed to examine residential magnetic field measurements by collecting magnetic field measurements and other data at utility employee residences over a 25 month period. The specific objectives of this study were: to investigate relationships between residential wire code category and magnetic field measurements; to investigate relationships between various types of magnetic field measurements; and to study residential magnetic field measurements over time. This report presents the results of the first 17 months of data collection. The residences of up to 12 employees were selected at each of 39 EPRI member utilities. Information about the house and nearby electric power system were collected along with a variety of magnetic field measurement data. A universal wire code scheme for electric power system wiring was used to classify houses in five wire code categories: very high current configuration (VHCC); ordinary high current configuration (OHCC); ordinary low current configuration (OLCC); very low current configuration (VLCC), and underground (UG). Measurements were made up to 5 times at each of 380 houses. For each measurement period the site coordinator used an EMDEX magnetic field meter to obtain measurements at specific locations in and around the house. This was followed by three days of measurements during which both long-term data at a fixed location and personal exposure data were collected. Analysis indicated that: VHCC category houses generally had higher magnetic field levels than the other categories; the overlap in distributions of summary measures was considerable for all wire code categories; this overlap made wire code category a poor predictor of residential magnetic field levels at residences as vice versa.

  5. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    International Nuclear Information System (INIS)

    This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage

  6. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    Energy Technology Data Exchange (ETDEWEB)

    Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J. [Pacific Northwest Lab., Richland, WA (United States); Nass, R. [Nuclear Fuel Services, Inc. (United States)

    1995-08-01

    This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage.

  7. Rosiglitazone evaluated for cardiovascular outcomes--an interim analysis

    DEFF Research Database (Denmark)

    Home, Philip D; Pocock, Stuart J; Beck-Nielsen, Henning;

    2007-01-01

    group). The primary end point was hospitalization or death from cardiovascular causes. RESULTS: Because the mean follow-up was only 3.75 years, our interim analysis had limited statistical power to detect treatment differences. A total of 217 patients in the rosiglitazone group and 202 patients......BACKGROUND: A recent meta-analysis raised concern regarding an increased risk of myocardial infarction and death from cardiovascular causes associated with rosiglitazone treatment of type 2 diabetes. METHODS: We conducted an unplanned interim analysis of a randomized, multicenter, open...... in the control group had the adjudicated primary end point (hazard ratio, 1.08; 95% confidence interval [CI], 0.89 to 1.31). After the inclusion of end points pending adjudication, the hazard ratio was 1.11 (95% CI, 0.93 to 1.32). There were no statistically significant differences between the rosiglitazone...

  8. Terrestrial gravity data analysis for interim gravity model improvement

    Science.gov (United States)

    1987-01-01

    This is the first status report for the Interim Gravity Model research effort that was started on June 30, 1986. The basic theme of this study is to develop appropriate models and adjustment procedures for estimating potential coefficients from terrestrial gravity data. The plan is to use the latest gravity data sets to produce coefficient estimates as well as to provide normal equations to NASA for use in the TOPEX/POSEIDON gravity field modeling program.

  9. 105-H Reactor Interim Safe Storage Project Final Report

    International Nuclear Information System (INIS)

    The following information documents the decontamination and decommissioning of the 105-H Reactor facility, and placement of the reactor core into interim safe storage. The D and D of the facility included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, decontamination, demolition of the structure, and restoration of the site. The ISS work also included construction of the safe storage enclosure, which required the installation of a new roofing system, power and lighting, a remote monitoring system, and ventilation components.

  10. Waste Encapsulation and Storage Facility interim operational safety requirements

    CERN Document Server

    Covey, L I

    2000-01-01

    The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

  11. Report on interim storage of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    The report on interim storage of spent nuclear fuel discusses the technical, regulatory, and economic aspects of spent-fuel storage at nuclear reactors. The report is intended to provide legislators state officials and citizens in the Midwest with information on spent-fuel inventories, current and projected additional storage requirements, licensing, storage technologies, and actions taken by various utilities in the Midwest to augment their capacity to store spent nuclear fuel on site.

  12. Species management in aquatic habitats WRc RD Interim 1997

    OpenAIRE

    1997-01-01

    This is the Species management in aquatic Habitats WRc Interim 1997 document produced by the Environment Agency in 1997. This document reports progress on R&D Project 640, which aims to provide information on species of conservation value of particular relevance to the Environment Agency, in relation to its activities affecting aquatic environments. A range of stand-alone outputs is being produced, comprising Species Action Plans, practical management guidelines for Agency staff and third par...

  13. Interim Sanitary Landfill Groundwater Monitoring Report. 1997 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site (SRS). These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 (formerly dWP-087A) and as part of the SRS Groundwater Monitoring Program.

  14. Loss of approval for interim storage by time schedule

    International Nuclear Information System (INIS)

    The Act ''Gesetz zur Suche und Auswahl eines Standortes fuer ein Endlager fuer Waerme entwickelnde radioaktive Abfaelle'' on the search and selection of a site for a repository for heat-generating radioactive waste as also other acts insert a new topic for interim site storage. The operation should be restricted for 40 years. This part of the act is analysed with respect to future requirements for the storage of waste.

  15. Penalty Inflation Adjustments for Civil Money Penalties. Interim Final Rule.

    Science.gov (United States)

    2016-06-27

    In accordance with the Federal Civil Penalties Inflation Adjustment Act of 1990, as amended by the Debt Collection Improvement Act of 1996, and further amended by the Bipartisan Budget Act of 2015, section 701: Federal Civil Penalties Inflation Adjustment Act Improvements Act of 2015, this interim final rule incorporates the penalty inflation adjustments for the civil money penalties contained in the Social Security Act PMID:27373014

  16. 105-H Reactor Interim Safe Storage Project Final Report

    Energy Technology Data Exchange (ETDEWEB)

    E.G. Ison

    2008-11-08

    The following information documents the decontamination and decommissioning of the 105-H Reactor facility, and placement of the reactor core into interim safe storage. The D&D of the facility included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, decontamination, demolition of the structure, and restoration of the site. The ISS work also included construction of the safe storage enclosure, which required the installation of a new roofing system, power and lighting, a remote monitoring system, and ventilation components.

  17. Interim data report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Vahlund, Fredrik [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

    2004-08-01

    This document is the interim data report in the project SR-Can. The purpose of the data report is to present input data, with uncertainty estimates, for the SR-Can assessment calculations. Besides input data, the report also describes the standardised procedures used when deriving the input data and the corresponding uncertainty estimates. However, in the present interim version of the report (written in the initial stage of the project when site characterisation has yet not been completed) the standardised procedures have not been possible to apply for most of the data and, in order to present a compilation of the data used in the assessment, much of the input data is presented without following the standardised procedures. This will however be changed for the final version of the SR-Can data report, in order to show the methodology that will be used in the final version one example of how input data will be presented is included (migration data for buffer) . The recommended input data for the assessment calculations are, for the interim version, mainly based on SR 97 Beberg data, these are merely presented without any background or uncertainty discussion (this is presented in the SR 97 data report)

  18. Interim Dry Storage of Spent Fuel in Casks

    International Nuclear Information System (INIS)

    French option for the back end of the fuel cycle is reprocessing of used fuel and recycling the fissile material, except some very specific fuel stored in vaults (dry conditions). Used fuel management solutions studied by AREVA for various countries allow for either direct transport to the reprocessing plant, or interim storage and transport after storage of used fuel. Interim storage solutions are wet storage or dry storage (DSC, metal casks or vault systems). When the decision on used fuel management has been postponed, some extension of interim storage duration is considered, therefore it becomes necessary to study used fuel and cask material behaviour and deterioration mechanisms. One objective of this R&D was to review research efforts on spent fuel behaviour and Dry storage experience in casks. Particularly we were interested in the assessment of retrievability of fuel after storage for further use. A review therefore, was made of the effect of storage time/ temperatures and of loading/ drying operation on used fuel integrity. R&D programmes were also carried out on the evaluation of cask materials in long term, especially materials susceptible to degradation

  19. INTERIM ANALYSIS OF THE CONTRIBUTION OF HIGH-LEVEL EVIDENCE FOR DENGUE VECTOR CONTROL.

    Science.gov (United States)

    Horstick, Olaf; Ranzinger, Silvia Runge

    2015-01-01

    This interim analysis reviews the available systematic literature for dengue vector control on three levels: 1) single and combined vector control methods, with existing work on peridomestic space spraying and on Bacillus thuringiensis israelensis; further work is available soon on the use of Temephos, Copepods and larvivorous fish; 2) or for a specific purpose, like outbreak control, and 3) on a strategic level, as for example decentralization vs centralization, with a systematic review on vector control organization. Clear best practice guidelines for methodology of entomological studies are needed. There is a need to include measuring dengue transmission data. The following recommendations emerge: Although vector control can be effective, implementation remains an issue; Single interventions are probably not useful; Combinations of interventions have mixed results; Careful implementation of vector control measures may be most important; Outbreak interventions are often applied with questionable effectiveness. PMID:26506739

  20. The Interim Financial Reporting in the Spirit of the IAS 34 Norm

    OpenAIRE

    2008-01-01

    The role of an interim financial reporting is to allow the information users to acknowledge the activity of an entity on period shorter than financial exercise from the perspective of the available profits and cash flows generated as well as from the point of view of its financial position and liquidity. The interim financial reporting includes a complete or condensed set of financial statements which target to update the last financial reporting, usually the annual report. The interim financ...

  1. Immobilized high-level waste interim storage alternatives generation and analysis and decision report

    Energy Technology Data Exchange (ETDEWEB)

    CALMUS, R.B.

    1999-05-18

    This report presents a study of alternative system architectures to provide onsite interim storage for the immobilized high-level waste produced by the Tank Waste Remediation System (TWRS) privatization vendor. It examines the contract and program changes that have occurred and evaluates their impacts on the baseline immobilized high-level waste (IHLW) interim storage strategy. In addition, this report documents the recommended initial interim storage architecture and implementation path forward.

  2. Effect of polyester fiber reinforcement on the mechanical properties of interim fixed partial dentures

    OpenAIRE

    N. Gopichander; K.V. Halini Kumarai; Vasanthakumar, M

    2015-01-01

    Background: Different reinforcements currently available for interim fixed partial denture (FPD) materials do not provide the ideal strength for long-term use. Therefore, the aim of this investigation was to develop a more ideal provisional material for long-term use with better mechanical properties. This study evaluated the effectiveness of polyester fiber reinforcement on different interim FPD materials. Methods: Thirty resin-bonded FPDs were constructed from three provisional interim F...

  3. High level waste interim storge architecture selection - decision report

    Energy Technology Data Exchange (ETDEWEB)

    Calmus, R.B.

    1996-09-27

    The U.S. Department of Energy (DOE) has embarked upon a course to acquire Hanford Site tank waste treatment and immobilization services using privatized facilities (RL 1996a). This plan contains a two-phased approach. Phase I is a proof-of-principle/connnercial demonstration- scale effort and Phase II is a fiill-scale production effort. In accordance with the planned approach, interim storage and disposal of various products from privatized facilities are to be DOE fumished. The high-level waste (BLW) interim storage options, or alternative architectures, were identified and evaluated to provide the framework from which to select the most viable method of Phase I BLW interim storage (Calmus 1996). This evaluation, hereafter referred to as the Alternative Architecture Evaluation, was performed to established performance and risk criteria (technical merit, cost, schedule, etc.). Based on evaluation results, preliminary architectures and path forward reconunendations were provided for consideration in the architecture decision- maldng process. The decision-making process used for selection of a Phase I solidified BLW interim storage architecture was conducted in accordance with an approved Decision Plan (see the attachment). This decision process was based on TSEP-07,Decision Management Procedure (WHC 1995). The established decision process entailed a Decision Board, consisting of Westinghouse Hanford Company (VY`HC) management staff, and included appointment of a VTHC Decision Maker. The Alternative Architecture Evaluation results and preliminary recommendations were presented to the Decision Board members for their consideration in the decision-making process. The Alternative Architecture Evaluation was prepared and issued before issuance of @C-IP- 123 1, Alternatives Generation and Analysis Procedure (WI-IC 1996a), but was deemed by the Board to fully meet the intent of WHC-IP-1231. The Decision Board members concurred with the bulk of the Alternative Architecture

  4. Interim rules amending ERISA disclosure requirements for group health plans--DoL. Interim rules with request for comments.

    Science.gov (United States)

    1997-04-01

    This document contains interim rules governing the content of the summary plan description (SPD) for group health plans, the furnishing of summaries of material reductions in covered services or benefits by group health plans, and the disclosure of SPD and related information through electronic media. The rules contained in this document implement amendments to the disclosure provisions of the Employee Retirement Income Security Act of 1974 (ERISA) enacted as part of the Health Insurance Portability and Accountability Act of 1996 (HIPAA) and the Newborns' and Mothers' Health Protection Act of 1996 (NMHPA). Interested persons are invited to submit comments on the interim rules for consideration by the Department in developing final rules. The rules contained in this document are being adopted on an interim basis to accommodate statutorily established time frames intended to ensure that sponsors and administrators of group health plans, as well as participants and beneficiaries covered by such plans, have timely guidance concerning compliance with the recently enacted amendments to ERISA. PMID:10166825

  5. Status of Galileo interim radiation electron model

    Science.gov (United States)

    Garrett, H. B.; Jun, I.; Ratliff, J. M.; Evans, R. W.; Clough, G. A.; McEntire, R. W.

    2003-01-01

    Measurements of the high energy, omni-directional electron environment by the Galileo spacecraft Energetic Particle Detector (EDP) were used to develop a new model of Jupiter's trapped electron radiation in the jovian equatorial plane for the range 8 to 16 Jupiter radii.

  6. Labour Force Survey: interim reweighting 2007

    OpenAIRE

    Nicholas Palmer; Matthew Hughes

    2008-01-01

    Outlines the reasons for making revisions and the impact of new population figures on headline labour market indicatorsOn 14 November 2007, the Office for National Statistics (ONS) published revised Labour Force Survey aggregate measures in the Labour Market Statistics First Release to take account of the latest available population estimates. This article firstly describes the various new and revised population estimates and the time periods affected. This is supported by tables and charts i...

  7. Magnetosphere imager science definition team interim report

    Science.gov (United States)

    Armstrong, T. P.; Johnson, C. L.

    1995-01-01

    For three decades, magnetospheric field and plasma measurements have been made by diverse instruments flown on spacecraft in may different orbits, widely separated in space and time, and under various solar and magnetospheric conditions. Scientists have used this information to piece together an intricate, yet incomplete view of the magnetosphere. A simultaneous global view, using various light wavelengths and energetic neutral atoms, could reveal exciting new data nd help explain complex magnetospheric processes, thus providing a clear picture of this region of space. This report documents the scientific rational for such a magnetospheric imaging mission and provides a mission concept for its implementation.

  8. Environmental survey of two interim dumpsites, Middle Atlantic Bight from 05 November 1973 to 10 November 1973 (NODC Accession 7501280)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — A second oceanographic survey cruise was made to an interim municipal sludge dumpsite and initially to an interim dumpsite for the disposal of industrial acid waste...

  9. An Interim Report on NASA's Draft Space Technology Roadmaps

    Science.gov (United States)

    2011-01-01

    NASA has developed a set of 14 draft roadmaps to guide the development of space technologies under the leadership of the NASA Office of the Chief Technologist (OCT). Each of these roadmaps focuses on a particular technology area (TA). The roadmaps are intended to foster the development of advanced technologies and concepts that address NASA's needs and contribute to other aerospace and national needs. OCT requested that the National Research Council conduct a study to review the draft roadmaps, gather and assess relevant community input, and make recommendations and suggest priorities to inform NASA's decisions as it finalizes its roadmaps. The statement of task states that "based on the results of the community input and its own deliberations, the steering committee will prepare a brief interim report that addresses high-level issues associated with the roadmaps, such as the advisability of modifying the number or technical focus of the draft NASA roadmaps." This interim report, which does not include formal recommendations, addresses that one element of the study charge. NASA requested this interim report so that it would have the opportunity to make an early start in modifying the draft roadmaps based on feedback from the panels and steering committee. The final report will address all other tasks in the statement of task. In particular, the final report will include a prioritization of technologies, will describe in detail the prioritization process and criteria, and will include specific recommendations on a variety of topics, including many of the topics mentioned in this interim report. In developing both this interim report and the final report to come, the steering committee draws on the work of six study panels organized by technical area, loosely following the organization of the 14 roadmaps, as follows: A Panel 1: Propulsion and Power TA01 Launch Propulsion Systems TA02 In-Space Propulsion Technologies TA03 Space Power and Energy Storage Systems TA13

  10. Interim summary report of the safety case 2009

    International Nuclear Information System (INIS)

    Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy), Posiva is preparing to submit a construction license application for the final disposal spent nuclear fuel at the Olkiluoto site, Finland, by the end of the year 2012. Disposal will take place in a geological repository implemented according to the KBS-3 method. The long-term safety section supporting the license application will be based on a safety case that, according to the internationally adopted definition, will be a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository. The present Interim Summary Report represents a major contribution to the development of this safety case. The report has been compiled in accordance with Posiva's current plan for preparing this safety case. A full safety case for the KBS-3V variant will be developed to support the Preliminary Safety Assessment Report (PSAR) in 2012. The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository. Current understanding of the evolution of the disposal system indicates that, except a few unlikely circumstances affecting a small number of canisters, spent fuel will remain isolated, and the radionuclides contained within the canisters, for hundreds of thousands of years or more, in accordance with the base scenario. Confidence in this base scenario derives, in the first place, from the

  11. A links manipulator simulation program interim report

    International Nuclear Information System (INIS)

    A computer program to simulate the performance of the Heysham II rail-following manipulator has been developed. The program is being used to develop and test the rail-following control algorithms which will be used to control movements of the manipulator when it is operating below the gas baffle dome. The simulation includes the dynamic responses of the manipulator joint drives, excluding friction, backlash and compliance. It also includes full details of the manipulator's geometry. A method is given whereby the actual manipulator dynamics can be written into the program once these have been established by measurement. The program is written in FORTRAN and runs on a Perkin-Elmer 3220 mini-computer. The simulation program responds to velocity demands on the individual joints. These will normally come from the control program, in which they will be manually controlled by a joystick. A sigma 5664 colour graphics generator is programmed to display the current position of the manipulator. (UK)

  12. Summary Interim Report on Findings and Interim Themes from Phase 1 of the review of Allied Health Professions (AHP) support for children/young people with a statement of special educational needs (SEN)

    OpenAIRE

    Public Health Agency

    2015-01-01

    Summary Interim Report on Findings and Interim Themes from Phase 1 of the review of Allied Health Professions (AHP) support for children/young people with a statement of special educational needs (SEN)This interim report is outlining the service principles agreed by the Project Board and the themes identified throughout engagement and information gathering.

  13. Interim Financial Reporting in the Perspective of harmonization of the Romanian Accountancy with the International Financial Reporting Standards

    OpenAIRE

    Bunea-Bontas, Cristina Aurora

    2007-01-01

    The main objective of the interim financial reporting is to present, timely and regularly, information concerning the enterprise’s capacity to generate earnings and cash flows and its financial position and liquidity. International Accounting Standard 34 “Interim Financial Reporting” concerns the financial statements for an interim period. According to IAS 34, the interim financial report includes a complete or condensed set of financial statements, elaborated for a shorter period than a full...

  14. The Effect of Incorporation, Orientation and Silane Treatment of Glass Fibers on the Fracture Resistance of Interim Fixed Partial Dentures

    OpenAIRE

    Basant, Gupta; Reddy, Y G

    2011-01-01

    Fracture of interim fixed partial dentures (FPD) is of important concern to the dental surgeon, especially with long-span fixed partial dentures or areas of heavy occlusal stress. Polymers used in interim FPDs, reinforced with glass fibers have shown to have a positive effect on the fracture resistance of interim FPDs. Since little research has been done on the influence of silane treated glass fibers on the fracture resistance of interim FPDs, this study was conducted to evaluate the effect ...

  15. 42 CFR 417.572 - Budget and enrollment forecast and interim reports.

    Science.gov (United States)

    2010-10-01

    ... of each contract period. The forecast must be based on financial and statistical data and records... 42 Public Health 3 2010-10-01 2010-10-01 false Budget and enrollment forecast and interim reports... forecast and interim reports. (a) Annual submittal. The HMO or CMP must submit an annual operating...

  16. Interim storage of wastes and refuse derived fuels; Zwischenlagerung von Abfaellen und Ersatzbrennstoffen

    Energy Technology Data Exchange (ETDEWEB)

    Thome-Kozmiensky, K.J.; Versteyl, A.; Beckmann, M. (eds.)

    2006-07-01

    Authors comment on interim storage of municipal wastes and refuse derived fuels. Topics of the 16 contributions are: Logistics and engineering, planning, estimation of storage time, cost and commitment, amend ment of the regulations, penal risks of interim storage, material flow management at waste incinerators, fire prevention, environmental risk, insurances. (uke)

  17. Interim format and content for a physical security plan for nuclear power plants

    International Nuclear Information System (INIS)

    The document serves as interim guidance to assist the licensee or applicant in the preparation of a physical security plan. It is to be used in conjunction with interim acceptance criteria for physical security programs, which will be distributed at a later date

  18. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-06-02

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  19. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-04-09

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  20. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    International Nuclear Information System (INIS)

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis

  1. 78 FR 40199 - Draft Spent Fuel Storage and Transportation Interim Staff Guidance

    Science.gov (United States)

    2013-07-03

    ... COMMISSION Draft Spent Fuel Storage and Transportation Interim Staff Guidance AGENCY: Nuclear Regulatory... Regulatory Commission (NRC) requests public comment on Draft Spent Fuel Storage and Transportation Interim... given in NUREG-1927 ``Standard Review Plan for Renewal of Spent Fuel Dry Cask Storage System...

  2. Effects of Interim Assessments across the Achievement Distribution: Evidence From an Experiment

    Science.gov (United States)

    Konstantopoulos, Spyros; Li, Wei; Miller, Shazia R.; van der Ploeg, Arie

    2016-01-01

    We use data from a large-scale experiment conducted in Indiana in 2009-2010 to examine the impact of two interim assessment programs (mCLASS and Acuity) across the mathematics and reading achievement distributions. Specifically, we focus on whether the use of interim assessments has a particularly strong effect on improving outcomes for low…

  3. 32 CFR 643.36 - Policy-Interim leasing of excess properties to facilitate economic readjustment.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 4 2010-07-01 2010-07-01 true Policy-Interim leasing of excess properties to facilitate economic readjustment. 643.36 Section 643.36 National Defense Department of Defense (Continued) DEPARTMENT OF THE ARMY (CONTINUED) REAL PROPERTY REAL ESTATE Policy § 643.36 Policy—Interim leasing of...

  4. Interim Action Proposed Plan for the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit; FINAL

    International Nuclear Information System (INIS)

    The purpose of this Interim Action Proposed Plan (IAPP) is to describe the preferred interim remedial action for addressing the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit and to provide an opportunity for public input into the remedial action selection process

  5. Performance of ERA-Interim wave data in the nearshore waters around India

    Digital Repository Service at National Institute of Oceanography (India)

    SanilKumar, V.; Naseef, T.M.

    the Interim European Centre for Medium-Range Weather Forecasts (ECMWF) Re-Analysis [ERA-Interim (ERA-I)] wave height and period data in the nearshore waters around India. The difference between the ERA-I significant wave height (SWH) and the buoy SWH varies...

  6. 76 FR 59394 - Energy Conservation Program for Consumer Products: Publication of the Extension of Interim Waiver...

    Science.gov (United States)

    2011-09-26

    ... multiple defrost cycles, and requested comments on Samsung's petition. 76 FR 16760 (March 25, 2011... comment period on its interim final rule for the refrigerator test procedure. 76 FR 57612 (Sept. 15, 2011...: Publication of the Extension of Interim Waiver Granted to Samsung Electronics America, Inc. From...

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  8. Hanford low-level tank waste interim performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Mann, F.M.

    1996-09-16

    The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single- and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and its performance as early as possible in the project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

  9. Hanford low-level tank waste interim performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Mann, F.M.

    1997-09-12

    The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

  10. Republic of Congo; Interim Poverty Reduction Strategy Paper Progress Report

    OpenAIRE

    International Monetary Fund

    2005-01-01

    This paper examines Congo’s Interim Poverty Reduction Strategy Paper (I-PRSP). Congo’s I-PRSP explains the features and causes of poverty in Congo. It provides a short- and medium-term vision of development as well as a strategic orientation for a return to sustainable and equitable growth. The main objective is steady poverty reduction. The choice and implementation of strategic orientations and priority actions in the I-PRSP are consistent with the government’s commitment to rebuilding the ...

  11. Hanford low-level tank waste interim performance assessment

    International Nuclear Information System (INIS)

    The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives

  12. 77 FR 55232 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-03; Compliance With...

    Science.gov (United States)

    2012-09-07

    ... COMMISSION Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-03; Compliance With...: Nuclear Regulatory Commission (NRC). ACTION: Japan Lessons-Learned Project Directorate Interim Staff... Final Japan Lessons-Learned Project Directorate (JLD) Interim Staff Guidance (ISG),...

  13. 77 FR 55231 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-02; Compliance With...

    Science.gov (United States)

    2012-09-07

    ... COMMISSION Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-02; Compliance With...: Nuclear Regulatory Commission (NRC). ACTION: Japan Lessons-Learned Project Directorate interim staff... Final Japan Lessons-Learned Project Directorate Interim Staff Guidance (JLD-ISG),...

  14. Advantages on dry interim storage for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, L.S. [Centro Tecnologico da Marinha em Sao Paulo, Av. Professor Lineu Prestes 2468, 05508-900 Sao Paulo (Brazil); Rzyski, B.M. [IPEN/ CNEN-SP, 05508-000 Sao Paulo (Brazil)]. e-mail: romanato@ctmsp.mar.mil.br

    2006-07-01

    When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

  15. Glass packages in interim storage; Les verres dans les stockages

    Energy Technology Data Exchange (ETDEWEB)

    Jacquet-Francillon, N.

    1994-10-01

    This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO{sub 2}. The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ``source term`` models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs.

  16. Climate change : we are at risk : interim report

    International Nuclear Information System (INIS)

    Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs

  17. Nuclear waste: Is there a need for federal interim storage

    International Nuclear Information System (INIS)

    The Congress created the Monitored Retrievable Storage Review Commission to provide a report on the need for a Federal monitored retrievable storage facility (MRS) as part of the Nation's nuclear waste management system. The Commission concludes that the MRS as presently described in the law, which links the capacity and schedule of operation of the MRS to a permanent geologic repository, cannot be justified. The Commission finds, however, that while no single factor would favor an MRS over the No-MRS option, cumulatively the advantages of an MRS would justify the building of an MRS if: there were no linkages between the MRS and the repository; the MRS could be constructed at an early date; and the opening of the repository were delayed considerably beyond its presently scheduled date of operation. The Commission therefore recommends that the Congress take the following actions: Authorize construction of a Federal Emergency Storage facility with a capacity limit of 2,000 metric tons of uranium; Authorize construction of a User-Funded Interim Storage facility with a capacity limit of 5,000 metric tons of uranium; Reconsider the subject of interim storage by the year 2000

  18. Climate change : we are at risk : interim report

    Energy Technology Data Exchange (ETDEWEB)

    Oliver, D.; Wiebe, J.

    2003-06-01

    Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs.

  19. Interim sanitary landfill groundwater monitoring report. 1996 Annual report

    Energy Technology Data Exchange (ETDEWEB)

    Bagwell, L.A.

    1997-01-01

    Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site. These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 and as part of the SRS Groundwater Monitoring Program. Trichlorofluoromethane and 1,1,1-trichloroethane were elevated in one sidegradient well and one downgradient well during 1996. Zinc was elevated in three downgradient wells and also was detected in the associated laboratory blanks for two of those wells. Specific conductance was elevated in one background well and one sidegradient well. Barium and copper exceeded standards in one sidegradient well, and dichloromethane (a common laboratory contaminant) was elevated in another sidegradient well. Barium, copper, and dichloromethane were detected in the associated blanks for these wells, also. The groundwater flow direction in the Steed Pond Acquifer (Water Table) beneath the Interim Sanitary Landfill was to the southeast (universal transverse Mercator coordinates). The flow rate in this unit was approximately 210 ft/year during first quarter 1996 and 180 ft/yr during third quarter 1996.

  20. Interim FEP report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Skagius, Kristina (ed.) [Kemakta Konsult AB, Stockholm (Sweden)

    2004-08-01

    This report describes the work with identification and structuring of features, events and processes (FEPs) that has been carried out within the scope of the SR-Can safety assessment up to the time of the interim reporting of the project. The overall objective of the work is to develop a database of features, events and processes in a format that would facilitate both a systematic analysis of FEPs and documentation of the FEP analysis as well as facilitate revisions and updates to be made in connection with new safety assessments. This overall objective also includes the development of procedures for a systematic FEP analysis as well as to apply these procedures in order to arrive at an SR-Can version of the FEP database. The work started by implementing the content of the SR 97 Process report into a database format suitable for import and processing of FEP information from other sources. The SR 97 version of the database was systematically audited against the NEA database with Project FEPs, version 1.2. In addition, an earlier audit of the SR 97 process report against the interaction matrices developed for a deep repository of the KBS-3 type was revisited and updated. Relevant FEPs from the audit were sorted into three main categories in the SR-Can database i) FEPs related to the initial states of the repository system, ii) FEPs related to internal processes of the repository system, and iii) FEPs related to external impacts on the repository system. These groups of FEPs were further processed for making decisions on how to handle these FEPs in the assessment. Biosphere processes were not included in the SR 97 Process report and there is thus not the same basis for updating these descriptions as for the engineered barriers and the geosphere. All biosphere FEPs from the audit have therefore been compiled in a single category in the database, but remain to be further handled. FEPs were also categorised as irrelevant or as being related to methodology on a general

  1. DEMONSTRATION OF THE DOE INTERIM ENERGY CONSERVATION STANDARDS FOR NEW FEDERAL RESIDENTIAL BUILDINGS

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A. D.; Baechler, H. C.; Di Massa, F. V.; Lucas, R. G.; Shankle, D. L.

    1992-01-01

    In accordance with federal legislation, the U.S. Department of Energy (DOE) has sponsored a study to demonstrate use of its Interim Energy Conservation Standards for New Federal Residential Buildings. The demonstration study was conducted by DOE and the Pacific Northwest Laboratory (PNL). The demonstration is the second step in a three-step process: I) development of interim standards, 2) demonstration of the interim standards, and 3) development of final standards. The standards are mandatory for federal agency housing procurements. Nevertheless, PNL found at the start of the demonstration that agency use of the interim standards had been minimal. The purpose of the standards is to improve the energy efficiency of federal housing and increase the use of nondepletable energy sources. In accordance with the legislation, the standards were to be performance-based rather than prescribing specific energy conservation measures. To fulfill this aspect of the legislation, the standards use a computer software program called COSTSAFR which generates a point system that individualizes the standards to specific projects based on climate, housing type, and fuel costs. The standards generate minimum energy-efficiency requirements by applying the life-cycle cost methodology developed for federal projects. For the demonstration, PNL and DOE chose five federal agency housing projects which had been built in diverse geographic and climate regions. Participating agencies were the Air Force, the Army (which provided two case studies), the Navy, and the Department of Health and Human Services. PNL worked with agency housing procurement officials and designers/architects to hypothetically apply the interim standards to the procurement and design of each housing project. The demonstration started at the point in the project where agencies would establish their energyefficiency requirements for the project and followed the procurement process through the designers' use of the point

  2. Evaluation and Analysis of SEASAT-A Scanning Multichannel Microwave Radiometer (SSMR) Antenna Pattern Correction (APC) Algorithm. Sub-task 4: Interim Mode T Sub B Versus Cross and Nominal Mode T Sub B

    Science.gov (United States)

    Kitzis, J. L.; Kitzis, S. N.

    1979-01-01

    The brightness temperature data produced by the SMMR Antenna Pattern Correction algorithm are evaluated. The evaluation consists of: (1) a direct comparison of the outputs of the interim, cross, and nominal APC modes; (2) a refinement of the previously determined cos beta estimates; and (3) a comparison of the world brightness temperature (T sub B) map with actual SMMR measurements.

  3. Project management plan for Reactor 105-C Interim Safe Storage project

    International Nuclear Information System (INIS)

    Reactor 105-C (located on the Hanford Site in Richland, Washington) will be placed into an interim safe storage condition such that (1) interim inspection can be limited to a 5-year frequency; (2) containment ensures that releases to the environmental are not credible under design basis conditions; and (3) final safe storage configuration shall not preclude or significantly increase the cost for any decommissioning alternatives for the reactor assembly.This project management plan establishes plans, organizational responsibilities, control systems, and procedures for managing the execution of Reactor 105-C interim safe storage activities to meet programmatic requirements within authorized funding and approved schedules

  4. Operator licensing examination standards for power reactors. Interim revision 8

    International Nuclear Information System (INIS)

    These examination standards are intended to assist NRC examiners and facility licensees to better understand the processes associated with initial and requalification examinations. The standards also ensure the equitable and consistent administration of examinations for all applicants. These standards are for guidance purposes and are not a substitute for the operator licensing regulations (i.e., 10 CFR Part 55), and they are subject to revision or other changes in internal operator licensing policy. This interim revision permits facility licensees to prepare their initial operator licensing examinations on a voluntary basis pending an amendment to 10 CFR Part 55 that will require facility participation. The NRC intends to solicit comments on this revision during the rulemaking process and to issue a final Revision 8 in conjunction with the final rule

  5. Interim sanitary landfill groundwater monitoring report. 1995 annual report

    Energy Technology Data Exchange (ETDEWEB)

    Bagwell, L.

    1996-04-24

    Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site (SRS). These wells are sampled biannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500- 1120 (formerly DWP-087A) and as part of the SRS Groundwater Monitoring Program. Trichlorofluoromethane was elevated in one downgradient and one sidegradient well during 1995. Barium, 1, 1- dichloroethylene, specific conductance, and zinc exceeded standards in one well each. The elevated level of 1, 1-dichloroethylene occurred in a downgradient well. The groundwater flow direction in the Steed Pond Aquifer (Water Table) beneath the Sanitary Landfill was to the southeast (universal transverse Mercator coordinates). The flow rate in this unit was approximately 190 ft/year during first quarter 1995 and 150 ft/yr during third quarter 1995.

  6. Provisional materials: key components of interim fixed restorations.

    Science.gov (United States)

    Perry, Ronald D; Magnuson, Britta

    2012-01-01

    Clinicians have many choices of provisional materials from which to choose when fabricating interim fixed restorations. While traditional materials are still in use today, temporary materials are continuously being updated and improved upon. In addition to the functional necessities required of the provisional material, it must also provide esthetic value for the patient. This article provides an overview of provisional materials, including newer bis-acryls that have helped eliminate some of the challenges associated with traditional acrylic materials. Composite resin preformed crowns for single-unit provisional applications are also discussed, along with CAD/CAM-fabricated materials. Regardless of the material selected, a provisional restoration must maintain and protect the underlying tooth structure from ill effects. PMID:22432178

  7. Licensing Procedures for Interim Storage of Spent Fuel in Germany

    International Nuclear Information System (INIS)

    In accordance with the waste management concept in Germany spent fuel is stored in interim storage facilities for 40 years until disposal in a geological repository. The storage concept bases on dry storage of the spent fuel in metallic transport and storage casks, standing upright in halls of reinforced concrete. Storage of spent fuel as well as significant modifications of the storage require a license according to art. 6 of the Atomic Energy Act. The Federal Office for Radiation Protection (Bundesamt für Strahlenschutz - BfS) is the competent licensing authority. The mode of the licensing procedure — whether formalized or non-formalized — depends on the necessity to carry out an environmental impact assessment. Formalized licensing procedures include a public participation procedure. In the following, the licensing prodecures are illustrated and a short overview over the current licensing procedures conducted by BfS is given. (author)

  8. Corrosion behaviour of metallic containers during long term interim storages

    International Nuclear Information System (INIS)

    Two main corrosion phenomena are encountered in long term interim storage conditions: dry oxidation by the air when the temperature of high level nuclear wastes containers is high enough (roughly higher than 100 C) and corrosion phenomena as those encountered in outdoor atmospheric corrosion when the temperature of the container wall is low enough and so condensation is possible on the container walls. Results obtained with dry oxidation in air lead to predict small damages (less than 1μm on steels over 100 years at 100 C) and no drastic changes with pollutants. For atmospheric corrosion, first developments deal with a pragmatic method that gives assessments of the indoor atmospheric corrosivities. (author)

  9. SNF Interim Storage Canister Corrosion and Surface Environment Investigations

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Enos, David G. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    This progress report describes work being done at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. In order for SCC to occur, three criteria must be met. A corrosive environment must be present on the canister surface, the metal must susceptible to SCC, and sufficient tensile stress to support SCC must be present through the entire thickness of the canister wall. SNL is currently evaluating the potential for each of these criteria to be met.

  10. Advanced nuclear reactor public opinion project. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-07-25

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

  11. Interim Site Assessment and Clean-up Guidebook

    International Nuclear Information System (INIS)

    In April 1995 an Interim Site Investigation and Clean-up Guidebook (for petroleum hydrocarbon and volatile organic compound impacted sites) was developed for public use. The purpose of the Guidebook was to offer a new approach to the site cleanup process: one that reduces time, cuts costs, and establishes a defined endpoint for investigations and cleanup actions. The Guidebook provided a matrix to screen for low-risk contaminated sites. After a year of use, the Guidebook was revised in May 1996. The most notable change was in the Petroleum Hydrocarbon Section and the modification of the screening table for petroleum hydrocarbon contaminated sites. The changes considered the strong influence of lithology on contaminant transport and recognized the large attenuation of the long chain, heavy oil and tar, hydrocarbons in soils

  12. Recommended alternative for interim stabilization of Tank 241-C-103

    Energy Technology Data Exchange (ETDEWEB)

    Dukelow, G.T.; Turner, D.A. [Westinghouse Hanford Co., Richland, WA (United States); Grigsby, J.M.

    1995-04-01

    The waste in tank 241-C-103 poses several health and safety risks and potential soil contamination caused by tank leaks. To minimize the risk of contaminating the soil beneath the tank, the pumpable waste liquids are planned to be removed by salt well pumping. In addition to aqueous liquids, this tank is unique because it also contains a layer of degraded PUREX solvent floating on the aqueous liquid. The following three options for removing and storing this separable phase organic solvent have been proposed and studied: transferring the organic solvent and pumpable aqueous liquids using existing salt well pumping equipment and procedures to a double-shell tank (DST) for storage; removing most of the organic solvent using a skimmer pump, then salt well pumping the remaining pumpable liquids to a different DST for storage; removing most of the organic solvent to an aboveground storage tank for eventual treatment or offsite transfer, and then salt well pumping the remaining pumpable liquids to a DST for interim storage. As a result of evaluating these three options and a no pumping option, the recommended action is to transfer both the organic solvent and pumpable aqueous liquid to a DST for storage using existing salt well pumping equipment. The evaluation considers the following criteria: public health and safety, worker safety, environmental compliance, engineering feasibility, and cost. The options compared these factors. Two key areas drove the selection of the recommended approach: the minimization of potential soil contamination from tank leaks caused the (interim stabilization by salt well pumping) options to be rated more highly than the no pumping option; and cost and implementation factors caused the transfer and storage to DST using existing tank farm salt well pumping equipment option to rate higher than the skimming options. Other factors have only a second order effect on the selection process. Evaluation results are described in this report.

  13. ICPP radioactive liquid and calcine waste technologies evaluation. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, J.A.; Pincock, L.F.; Christiansen, I.N.

    1994-06-01

    The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until recently, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, changing world events have raised questions concerning the need to recover and recycle this material. In April 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the management and disposition of radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste) and 3,800 cubic meters (m{sup 3}) of calcine waste are in inventory at the ICPP. Legal drivers and agreements exist obligating the INEL to develop, demonstrate, and implement technologies for safe and environmentally sound treatment and interim storage of radioactive liquid and calcine waste. Candidate treatment processes and waste forms are being evaluated using the Technology Evaluation and Analysis Methodology (TEAM) Model. This process allows decision makers to (1) identify optimum radioactive waste treatment and disposal form alternatives; (2) assess tradeoffs between various optimization criteria; (3) identify uncertainties in performance parameters; and (4) focus development efforts on options that best satisfy stakeholder concerns. The Systems Analysis technology evaluation presented in this document supports the DOE in selecting the most effective radioactive liquid and calcine waste management plan to implement in compliance with established regulations, court orders, and agreements.

  14. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

  15. Intra-Service Section 7 Evaluation Consultation/Conference/Concurrence : Walnut Creek NWR Interim Hunting Plan

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This Section 7 Evaluation for the Neal Smith NWR Interim Hunting Plan states that the hunting program is not likely to adversely affect listed species on the...

  16. Big Oaks National Wildlife Refuge : Environmental Action Statement, Environmental Assessment, Interim Hunting and Fishing Plan : 2004

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This document contains the Environmental Action Statement, Environmental Assessment, and Interim Hunting and Fishing Plan for Big Oaks National Wildlife Refuge from...

  17. Basis for Interim Operation for the K-Reactor in Cold Standby

    International Nuclear Information System (INIS)

    The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993)

  18. Interim report for defining brine and oil threats in the Patoka River National Wildlife Refuge [2002

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — The following interim report is a list of activities being performed in conjunction with the study of oil brine effects on crayfish in the Patoka River National...

  19. Interim report for defining brine and oil threats in the Patoka River National Wildlife Refuge [2001

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — The following interim report is a list of activities being performed in conjunction with the study of oil brine effects on crayfish in the Patoka River National...

  20. Flammable gas deflagration consequence calculations for the tankwaste remediation system basis for interim operation

    Energy Technology Data Exchange (ETDEWEB)

    Van Vleet, R.J., Westinghouse Hanford

    1996-09-23

    This paper calculates the radiological dose consequences and the toxic exposures for deflagration accidents at various Tank Waste Remediation System facilities. These will be used in support of the Tank Waste Remediation System Basis for Interim Operation.

  1. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    International Nuclear Information System (INIS)

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  2. LANDFILLS AS BIOREACTORS: RESEARH AT THE OUTER LOOP LANDFILL, LOUISVILLE, KENTUCKY; FIRST INTERIM REPORT

    Science.gov (United States)

    Interim report resulting from a cooperative research and development agreement (CRADA) between US EP A's Officeof Research and Development - National Risk Management Research Laboratory and a n ongoing field demonstrationof municipal waste landfills being operated as bioreact...

  3. Decommissioning and dismantling of nuclear reactors and nuclear spent fuel interim storage in Germany

    International Nuclear Information System (INIS)

    The authors visited Germany in April 2013 to investigate state of reactor decommissioning and dismantling and interim storage of spent fuels reflecting nuclear power phaseout policy after the Fukushima accident. They visited interim storage facilities of radioactive wastes (ZLN, Zwischenlanger Nord) and central active workshop (ZAW, Zentrale Aktive Werkstatt) at Greifswald, and interim storage facilities of spent fuels at Philippsburg. CASTOR (Cask for Storage and Transport of Radioactive Material) was used for interim storage of spent fuels and high-level wastes for 40 years. Amount of wastes produced by decommissioning and dismantling was estimated 1800 ktons consisting of 1200 ktons non-radioactive and 600 ktons radioactive wastes, 500 ktons of which could be decontaminated less than clearance level and 100 ktons of which were obliged to be stored as radioactive wastes. New geological repository site for high level radioactive wastes should be found and developed. (T. Tanaka)

  4. Loke T. Kok named interim dean of College of Agriculture and Life Sciences

    OpenAIRE

    Owczarski, Mark

    2009-01-01

    Loke T. Kok of Blacksburg, professor and head of the Department of Entomology in the College of Agriculture and Life Sciences at Virginia Tech, has been named the college's interim dean effective March 1.

  5. Basis for Interim Operation for the K-Reactor in Cold Standby

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, B.

    1998-10-19

    The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993).

  6. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    Energy Technology Data Exchange (ETDEWEB)

    T. A. Lee

    2005-09-15

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  7. 76 FR 15028 - Airport Improvement Program (AIP): Interim Policy Regarding Access to Airports From Residential...

    Science.gov (United States)

    2011-03-18

    ... Improvement Program (AIP): Policy Regarding Access to Airports From Residential Property (75 FR 54946..., Safety Management System for Certificated Airports (75 FR 62008, October 7, 2010). However, the agency... Federal Aviation Administration Airport Improvement Program (AIP): Interim Policy Regarding Access...

  8. Will interim storage sites become ultimate storage sites?; Werden aus Zwischenlager Endlager?

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, W.P. [ia GmbH - Wissensmanagement und Ingenieurleistungen, Muenchen (Germany)

    2007-07-01

    According to a Prognos study, the maximum interim storage capacity required in Germany in 2008 will be 4 - 5 million cubic metres. Interim storage is necessary because there are not sufficient options for disposal. The stored waste will be combusted, so that German incinerators will be capable of running at full capacity until 2013. From mere disposal systems, incinerators are rapidly becoming waste-to-energy systems that will make a contribution to power supply. (orig.)

  9. Verification of the new ECMWF ERA-Interim reanalysis over France

    OpenAIRE

    Szczypta, C; J.-C. Calvet; Albergel, C.; Balsamo, G.; S. Boussetta; D. Carrer; S. Lafont; Meurey, C.

    2010-01-01

    An evaluation of the global ECMWF atmospheric reanalysis ERA-Interim (with a 0.5° grid) is performed over France, based on the high resolution (8 km) SAFRAN atmospheric reanalysis. The ERA-Interim precipitation, Incoming Solar Radiation (ISR), air temperature, air humidity, and wind speed, are compared with their SAFRAN counterparts. Also, interpolated in situ ISR observations are used in order to consolidate the evaluation of this variable. The daily precipitation estimates produced by ERA-I...

  10. Verification of the new ECMWF ERA-Interim reanalysis over France

    OpenAIRE

    Szczypta, C; Calvet, J.-C.; Albergel, C.; Balsamo, G.; S. Boussetta; D. Carrer; S. Lafont; Meurey, C.

    2011-01-01

    An evaluation of the global ECMWF atmospheric reanalysis ERA-Interim (with a 0.5° grid) is performed over France, based on the high resolution (8 km) SAFRAN atmospheric reanalysis. The ERA-Interim precipitation, Incoming Solar Radiation (ISR), air temperature, air humidity, and wind speed, are compared with their SAFRAN counterparts. Also, interpolated in situ ISR observations are used in order to consolidate the evaluation of this variable. The daily precipitation estimates produced by ERA-I...

  11. On-site interim storage of spent nuclear fuel: Emerging public issues

    International Nuclear Information System (INIS)

    Failure to consummate plans for a permanent repository or above- ground interim Monitored Retrievable Storage (MRS) facility for spent nuclear fuel has spurred innovative efforts to ensure at-reactor storage in an environmentally safe and secure manner. This article examines the institutional and socioeconomic impacts of Dry Cask Storage Technology (DCST)-an approach to spent fuel management that is emerging as the preferred method of on-site interim spent fuel storage by utilities that exhaust existing storage capacity

  12. Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

    International Nuclear Information System (INIS)

    This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

  13. Physical protection of shipments of irradiated reactor fuel; Interim guidance. Regulatory report

    International Nuclear Information System (INIS)

    During May, 1979, the U.S. Nuclear Regulatory Commission approved for issuance in effective form new interim regulations for strengthening the protection of spent fuel shipments against sabotage and diversion. The new regulations were issued without benefit of public comment, but comments from the public were solicited after the effective date. Based upon the public comments received, the interim regulations were amended and reissued in effective form as a final interim rule in May, 1980. The present document supersedes a previously issued interim guidance document, NUREG-0561 (June, 1979) which accompanied the original rule. This report has been revised to conform to the new interim regulations on the physical protection of shipments of irradiated reactor fuel which are likely to remain in effect until the completion of an ongoing research program concerning the response of spent fuel to certain forms of sabotage, at which time the regulations may be rescinded, modified or made permanent, as appropriate. This report discusses the amended regulations and provides a basis on which licensees can develop an acceptable interim program for the protection of spent fuel shipments

  14. Hazelwood Interim Storage Site environmental report for calendar year 1989, Hazelwood, Missouri

    International Nuclear Information System (INIS)

    The environmental monitoring program, begun in 1984, was continued during 1989 at the Hazelwood Interim Storage Site (HISS), a US Department of Energy (DOE) facility located in the City of Hazelwood, Missouri. HISS is currently used for storage of soils contaminated with residual radioactive material. HISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive material remains from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The monitoring program at HISS measures radon concentrations in air; external gamma radiation levels; and uranium, radium, and thorium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. This report presents the findings of the environmental monitoring conducted at HISS during calendar year 1989. 19 refs., 14 figs., 13 tabs

  15. Sampling and analysis plan for Wayne Interim Storage Site (WISS), Wayne, New Jersey

    International Nuclear Information System (INIS)

    This field sampling plan describes the methodology to perform an independent radiological verification survey and chemical characterization of a remediated area of the subpile at the Wayne Interim Storage Site, Wayne, New Jersey.Data obtained from collection and analysis of systematic and biased soil samples will be used to assess the status of remediation at the site and verify the final radiological status. The objective of this plan is to describe the methods for obtaining sufficient and valid measurements and analytical data to supplement and verify a radiological profile already established by the Project Remediation Management Contractor (PMC). The plan describes the procedure for obtaining sufficient and valid analytical data on soil samples following remediation of the first layer of the subpile. Samples will be taken from an area of the subpile measuring approximately 30 m by 80 m from which soil has been excavated to a depth of approximately 20 feet to confirm that the soil beneath the excavated area does not exceed radiological guidelines established for the site or chemical regulatory limits for inorganic metals. After the WISS has been fully remediated, the Department of Energy will release it for industrial/commercial land use in accordance with the Record of Decision. This plan provides supplemental instructions to guidelines and procedures established for sampling and analysis activities. Procedures will be referenced throughout this plan as applicable, and are available for review if necessary

  16. Operational Implementation of the MARSSIM Process at the Wayne Interim Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    Hays, D. C. Jr.; Trujillo, P. A. IV.; Zoller, S. G.

    2002-02-27

    This paper describes the methodologies behind the operational implementation of the Multi Agency Radiation Site Survey and Investigation Manual (MARSSIM) process at the Wayne Interim Storage Site (WISS). The United States Army Corps of Engineers (USACE) and Environmental Chemical Corporation (ECC) have implemented the MARSSIM process using various surveys producing raw data. The final remedial status of a survey unit is derived through data reduction, while maintaining a high degree of efficiency in the construction aspects of the remedial action. Data reduction of field measurements is accomplished by merging the data outputs of a Digital Global Positioning System, an exposure rate meter, and laboratory analyses to produce maps which present exposure rates, elevations, survey unit boundaries, direct measurement locations, and sampling locations on a single map. The map serves as a data-posting plot and allows the project team to easily judge the survey unit's remedial status. The operational implementation of the MARSSIM process has been successful in determining the eligibility of survey units for final status surveys at the WISS and also in demonstrating final status radiological and chemical conditions while maintaining an efficient remedial action effort.

  17. National climate change action plans: Interim report for developing and transition countries

    Energy Technology Data Exchange (ETDEWEB)

    Benioff, R.; Ness, E.; Hirst, J. [eds.

    1997-10-01

    Under its Support for National Action Plans (SNAP) initiative, the U.S. Country Studies Program is providing financial and technical assistance to 18 countries for the development of climate change action plans. Although most of the countries have not yet completed their plans, the important lessons learned thus far are valuable and should be shared with other countries and international institutions that have an interest in the process of action plan development. This interim report describes the experience of 11 countries that are the furthest along in their planning activity and who have offered to share their results to date with the larger community of interested nations. These action plans delineate specific mitigation and adaptation measures that the countries will implement and integrate into their ongoing development programs. This report focuses on the measures the countries have selected and the methods they used to prepare their action plans. This executive summary presents key lessons and common themes using a structure similar to that used in the individual country chapters.

  18. Interim main report of the safety assessment SR-Can

    International Nuclear Information System (INIS)

    This document is an interim report on the safety assessment SR-Can (SR in the acronym stands for Safety Report and Can is short for canister). The final SR-Can report will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of the present interim report is to demonstrate the methodology for safety assessment so that it can be reviewed before it is used in a license application. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark site, presently being investigated by SKB as one of the candidate for a KBS-3 repository are used to some extent as examples. However, the collected data are yet too sparse to allow an evaluation of safety for this site. An important aim of this report is to demonstrate the proper handling of requirements on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Authority are duplicated in an Appendix. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10-6 for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. Following the introductory chapter 1, this report outlines the methodology for the SR-Can assessment in chapter 2, and presents in chapters 3, 4 and 5 the initial state of the system and the plans and methods for handling external influences and internal processes, respectively. Function indicators are introduced in chapter 6 and a preliminary evaluation of these is given in chapter 7. The material presented in the first seven chapters is utilised in the scenario selection in chapter 8. Hydrogeological

  19. Interim main report of the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Allan (ed.) [and others

    2004-08-01

    This document is an interim report on the safety assessment SR-Can (SR in the acronym stands for Safety Report and Can is short for canister). The final SR-Can report will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of the present interim report is to demonstrate the methodology for safety assessment so that it can be reviewed before it is used in a license application. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark site, presently being investigated by SKB as one of the candidate for a KBS-3 repository are used to some extent as examples. However, the collected data are yet too sparse to allow an evaluation of safety for this site. An important aim of this report is to demonstrate the proper handling of requirements on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Authority are duplicated in an Appendix. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. Following the introductory chapter 1, this report outlines the methodology for the SR-Can assessment in chapter 2, and presents in chapters 3, 4 and 5 the initial state of the system and the plans and methods for handling external influences and internal processes, respectively. Function indicators are introduced in chapter 6 and a preliminary evaluation of these is given in chapter 7. The material presented in the first seven chapters is utilised in the scenario selection

  20. Dedicated-site, interim storage of high-level nuclear waste as part of the management system

    OpenAIRE

    Zen, E-an

    1980-01-01

    Dedicated-site interim storage of high-level reprocessed nuclear waste and of spent fuel rods is proposed as a long-term integral part of the systems approach of the national nuclear waste isolation program. Separation of interim sites for retrievable storage from permanent-disposal repositories should enhance ensurance of the performance of the latter; maintenance of retrievability at separate sites also has many advantages in both safety and possible use of waste as resources. Interim stora...

  1. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

  2. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

  3. International Programs and Agreements in Geothermal Energy. An Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Oppenheimer, M.; Fein, E.; Bye, J.

    1978-06-01

    This report contains the interim results of a study for the Division of Geothermal Energy on the Division's international programs and activities. The complete research program, which is scheduled to be finished i November 1978, will have the following elements: (1) an assessment of objectives that have motivated the formulation of international programs and an explanation of any changes in the evolution of those programs. These objectives will be assessed for their internal consistency, degree of governmental consensus, their practicality, the current status of their accomplishments, and the implications of their accomplishments for the role of DGE. (2) An assessment of organizational structures and teams, including the identity of key decisionmakers, the nature of the interagency process, procedures for generating nongovernmental support for international programs and the success of these procedures, and the effectiveness of the interface with foreign partners. (3) Assessment of results of international cooperative programs, which involve the development of an overall balance sheet of benefits and disbenefits attributed to each international program. (4) The formulation of future international cooperative programs based on the assessments described. These programs may involve the development of new exchanges, alteration or elimination of existing exchanges, and revisions in the management of exchanges by US government agencies.

  4. Database and Interim Glass Property Models for Hanford HLW Glasses

    International Nuclear Information System (INIS)

    The purpose of this report is to provide a methodology for an increase in the efficiency and a decrease in the cost of vitrifying high-level waste (HLW) by optimizing HLW glass formulation. This methodology consists in collecting and generating a database of glass properties that determine HLW glass processability and acceptability and relating these properties to glass composition. The report explains how the property-composition models are developed, fitted to data, used for glass formulation optimization, and continuously updated in response to changes in HLW composition estimates and changes in glass processing technology. Further, the report reviews the glass property-composition literature data and presents their preliminary critical evaluation and screening. Finally the report provides interim property-composition models for melt viscosity, for liquidus temperature (with spinel and zircon primary crystalline phases), and for the product consistency test normalized releases of B, Na, and Li. Models were fitted to a subset of the screened database deemed most relevant for the current HLW composition region

  5. DOUBLE TRACKS Test Site interim corrective action plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    The DOUBLE TRACKS site is located on Range 71 north of the Nellis Air Force Range, northwest of the Nevada Test Site (NTS). DOUBLE TRACKS was the first of four experiments that constituted Operation ROLLER COASTER. On May 15, 1963, weapons-grade plutonium and depleted uranium were dispersed using 54 kilograms of trinitrotoluene (TNT) explosive. The explosion occurred in the open, 0.3 m above the steel plate. No fission yield was detected from the test, and the total amount of plutonium deposited on the ground surface was estimated to be between 980 and 1,600 grams. The test device was composed primarily of uranium-238 and plutonium-239. The mass ratio of uranium to plutonium was 4.35. The objective of the corrective action is to reduce the potential risk to human health and the environment and to demonstrate technically viable and cost-effective excavation, transportation, and disposal. To achieve these objectives, Bechtel Nevada (BN) will remove soil with a total transuranic activity greater then 200 pCI/g, containerize the soil in ``supersacks,`` transport the filled ``supersacks`` to the NTS, and dispose of them in the Area 3 Radioactive Waste Management Site. During this interim corrective action, BN will also conduct a limited demonstration of an alternative method for excavation of radioactive near-surface soil contamination.

  6. Conceptual design of interim storage facility for CNAI

    International Nuclear Information System (INIS)

    The reduced storage capacity available in the two spent fuel pools of argentine PHWR Atucha-1 power plant, the current plans for extending the reactor operation beyond its design lifetime, and the government decision on Atucha-2 NPP construction ending, have motivated the evaluation of a dry storage option for the interim management of spent fuel assemblies. Two different designs are presently being analyzed by an expert working group, from both technical and economical points of views. Authors are proposing a modular system consisting of an arrangement of reinforced concrete structures into which welded metallic canisters loaded with 37 spent fuel assemblies each stored in horizontal position. The reinforced concrete module is designed to provide the necessary physical protection and biological shielding to the loaded canisters during long-term storage, as well as passive means to remove the spent fuel decay heat by a combination of radiation, conduction and natural air convection. In this works are presented advances in the conceptual designs for a spent nuclear fuel system to Atucha I nuclear power plant. (author)

  7. Performance testing of aged hydrogen getters against criteria for interim safe storage of plutonium bearing materials.

    Energy Technology Data Exchange (ETDEWEB)

    Shepodd, Timothy J.; Nissen, April; Buffleben, George M.

    2006-01-01

    Hydrogen getters were tested for use in storage of plutonium-bearing materials in accordance with DOE's Criteria for Interim Safe Storage of Plutonium Bearing Materials. The hydrogen getter HITOP was aged for 3 months at 70 C and tested under both recombination and hydrogenation conditions at 20 and 70 C; partially saturated and irradiated aged getter samples were also tested. The recombination reaction was found to be very fast and well above the required rate of 45 std. cc H2h. The gettering reaction, which is planned as the backup reaction in this deployment, is slower and may not meet the requirements alone. Pressure drop measurements and {sup 1}H NMR analyses support these conclusions. Although the experimental conditions do not exactly replicate the deployment conditions, the results of our conservative experiments are clear: the aged getter shows sufficient reactivity to maintain hydrogen concentrations below the flammability limit, between the minimum and maximum deployment temperatures, for three months. The flammability risk is further reduced by the removal of oxygen through the recombination reaction. Neither radiation exposure nor thermal aging sufficiently degrades the getter to be a concern. Future testing to evaluate performance for longer aging periods is in progress.

  8. Biodiversity offsets: a cost-effective interim solution to seabird bycatch in fisheries?

    Directory of Open Access Journals (Sweden)

    Sean Pascoe

    Full Text Available The concept of biodiversity offsets is well established as an approach to environmental management. The concept has been suggested for environmental management in fisheries, particularly in relation to the substantial numbers of non-target species--seabirds in particular--caught and killed as incidental bycatch during fishing activities. Substantial areas of fisheries are being closed to protect these species at great cost to the fishing industry. However, other actions may be taken to offset the impact of fishing on these populations at lower cost to the fishing industry. This idea, however, has attracted severe criticism largely as it does not address the underlying externality problems created by the fishing sector, namely seabird fishing mortality. In this paper, we re-examine the potential role of compensatory mitigation as a fisheries management tool, although from the perspective of being an interim management measure while more long-lasting solutions to the problem are found. We re-model an example previously examined by both proponents and opponents of the approach, namely the cost effectiveness of rodent control relative to fishery area closures for the conservation of a seabird population adversely affected by an Australian tuna fishery. We find that, in the example being examined, invasive rodent eradication is at least 10 times more cost effective than area closures. We conclude that, while this does not solve the actual bycatch problem, it may provide breathing space for both the seabird species and the industry to find longer term means of reducing bycatch.

  9. Wayne Interim Storage Site annual environmental report for calendar year 1991, Wayne, New Jersey

    International Nuclear Information System (INIS)

    This document describes the envirormental monitoring program at the Wayne Interim Storage Site (WISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of WISS and surrounding area began in 1984 when Congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. WISS is a National Priorities List site. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment

  10. Hazelwood Interim Storage Site annual environmental report for calendar year 1991, Hazelwood, Missouri

    International Nuclear Information System (INIS)

    This document describes the environmental monitoring program at the Hazelwood Interim Storage Site (HISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of HISS began in 1984 when the site was assigned to the US Department of Energy (DOE) as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Development Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at HISS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and radium-226, thorium-230, and total uranium concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards and DCGs are established to protect public health and the environment

  11. Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

  12. Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ''Safety Measures for Waste Tanks at Hanford Nuclear Reservation,'' of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues

  13. Interim site characterization report and ground-water monitoring program for the Hanford site solid waste landfill

    Energy Technology Data Exchange (ETDEWEB)

    Fruland, R.M.; Hagan, R.A.; Cline, C.S.; Bates, D.J.; Evans, J.C.; Aaberg, R.L.

    1989-07-01

    Federal and state regulations governing the operation of landfills require utilization of ground-water monitoring systems to determine whether or not landfill operations impact ground water at the point of compliance (ground water beneath the perimeter of the facility). A detection-level ground-water monitoring system was designed, installed, and initiated at the Hanford Site Solid Waste Landfill (SWL). Chlorinated hydrocarbons were detected at the beginning of the ground-water monitoring program and continue to be detected more than 1 year later. The most probable source of the chlorinated hydrocarbons is washwater discharged to the SWL between 1985 and 1987. This is an interim report and includes data from the characterization work that was performed during well installation in 1987, such as field observations, sediment studies, and geophysical logging results, and data from analyses of ground-water samples collected in 1987 and 1988, such as field parameter measurements and chemical analyses. 38 refs., 27 figs., 8 tabs.

  14. 4D Dynamic RNP Annual Interim Report-Year 1

    Science.gov (United States)

    Finkelsztein, Daniel M.; Sturdy, James L.; Alaverdi, Omeed; Chung, William W.; Salvano, Daniel; Klooster, Joel; Hochwarth, Joachim K.

    2010-01-01

    This Annual Interim Report summarizes the activities led by Raytheon, in collaboration with GE Aviation and SAIC, and presents the results obtained during the first year of this research effort to expand the RNP concept to 4 dimensions relative to a dynamic frame of reference. Joint Program Development Office (JPDO)Concepts of Operations for the Next Generation Air Transportation System (NextGen) considers 4 Dimension Trajectory (4DT) procedures a key enabler to Trajectory Based Operations (TBO). The JPDO defines 4DT as a precise description of an aircraft path in space and time . While NextGen assumes that this path is defined within an Earth-reference frame, many 4DT procedure implementations will require an aircraft to precisely navigate relative to a moving reference such as another aircraft to form aggregate flows or a weather cell to allow for flows to shift. Current methods of implementing routes and flight paths rely on aircraft meeting a Required Navigation Performance (RNP) specification and being equipped with a monitoring and alerting capability to annunciate when the aircraft system is unable to meet the performance specification required for the operation. Since all aircraft today operate within the NAS relative to fixed reference points, the current RNP definition is deemed satisfactory. However, it is not well understood how the current RNP construct will support NextGen 4DT procedures where aircraft operate relative to each other or to other dynamic frames of reference. The objective of this research effort is to analyze candidate 4DT procedures from both an Air Navigation Service Provider (ANSP) and aircraft perspective, to identify their specific navigational requirements, assess the shortcomings of the current RNP construct to meet these requirements, to propose an extended 4 Dimensional Dynamic RNP (4D Dynamic RNP) construct that accounts for the dynamic spatial and temporal nature of the selected 4DT procedures, and finally, to design an

  15. Basis for Interim Operation for Fuel Supply Shutdown Facility

    International Nuclear Information System (INIS)

    This document establishes the Basis for Interim Operation (BIO) for the Fuel Supply Shutdown Facility (FSS) as managed by the 300 Area Deactivation Project (300 ADP) organization in accordance with the requirements of the Project Hanford Management Contract procedure (PHMC) HNF-PRO-700, ''Safety Analysis and Technical Safety Requirements''. A hazard classification (Benecke 2003a) has been prepared for the facility in accordance with DOE-STD-1027-92 resulting in the assignment of Hazard Category 3 for FSS Facility buildings that store N Reactor fuel materials (303-B, 3712, and 3716). All others are designated Industrial buildings. It is concluded that the risks associated with the current and planned operational mode of the FSS Facility (uranium storage, uranium repackaging and shipment, cleanup, and transition activities, etc.) are acceptable. The potential radiological dose and toxicological consequences for a range of credible uranium storage building have been analyzed using Hanford accepted methods. Risk Class designations are summarized for representative events in Table 1.6-1. Mitigation was not considered for any event except the random fire event that exceeds predicted consequences based on existing source and combustible loading because of an inadvertent increase in combustible loading. For that event, a housekeeping program to manage transient combustibles is credited to reduce the probability. An additional administrative control is established to protect assumptions regarding source term by limiting inventories of fuel and combustible materials. Another is established to maintain the criticality safety program. Additional defense-in-depth controls are established to perform fire protection system testing, inspection, and maintenance to ensure predicted availability of those systems, and to maintain the radiological control program. It is also concluded that because an accidental nuclear criticality is not credible based on the low uranium enrichment

  16. Interim results from UO2 fuel oxidation tests in air

    International Nuclear Information System (INIS)

    An experimental program is being conducted at Pacific Northwest Laboratory (PNL) to extend the characterization of spent fuel oxidation in air. To characterize oxidation behavior of irradiated UO2, fuel oxidation tests were performed on declad light-water reactor spent fuel and nonirradited UO2 pellets in the temperature range of 135 to 2500C. These tests were designed to determine the important independent variables that might affect spent fuel oxidation behavior. The data from this program, when combined with the test results from other programs, will be used to develop recommended spent fuel dry-storage temperature limits in air. This report describes interim test results. The initial PNL investigations of nonirradiated and spent fuels identified the important testing variables as temperature, fuel burnup, radiolysis of the air, fuel microstructure, and moisture in the air. Based on these initial results, a more extensive statistically designed test matrix was developed to study the effects of temperature, burnup, and moisture on the oxidation behavior of spent fuel. Oxidation tests were initiated using both boiling-water reactor and pressurized-water reactor fuels from several different reactors with burnups from 8 to 34 GWd/MTU. A 105 R/h gamma field was applied to the test ovens to simulate dry storage cask conditions. Nonirradiated fuel was included as a control. This report describes experimental results from the initial tests on both the spent and nonirradiated fuels and results to date on the tests in a 105 R/h gamma field. 33 refs., 51 figs., 6 tabs

  17. Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Bonnema, Bruce Edward

    2001-09-01

    This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  18. Interim report of the task force on energy policy

    International Nuclear Information System (INIS)

    A Task Force was established by the Premier of British Columbia in August 2001 to draft an energy policy framework for the province. Based on best practices worldwide, and keeping in mind the specific energy needs of British Columbia, this framework aims at fostering energy development in British Columbia, in accordance with exemplary environmental practices. This interim report comprises the preliminary findings of the Task Force, and public input is sought before the final report is finalized and presented to government. The energy sector of British Columbia comprises hydroelectric power, oil, gas and coal resources. In addition, green energy and alternative energy technologies are being developed, such as wind, solar, and wave power, and hydrogen fuel cells. Industry and individual consumers are well served by the highly developed transmission and distribution systems for energy. Several strategic directions were identified by the Task Force for inclusion in the energy policy of British Columbia, to meet its full potential. They are: growth to ensure safe, reliable energy and take advantage of economic opportunities; diversification; competitiveness; industry restructuring and expansion; environmental imperative; government leadership; and community and First Nations' involvement. Some changes are also required for the continuing success of the energy sector in British Columbia: a move to fully competitive markets in the electricity system, the development of natural gas storage capacity in the Lower Mainland, additional considerations for coal use, and the development of alternative energy sources. It is expected that private capital and more energy supply will result from a fully competitive energy market, which in turn would lower energy costs. Jobs and income would increase as a result of the growth in the sector. Diversification makes good economic and environmental sense. tabs., figs

  19. High-spatial-resolution mapping of precipitable water vapour using SAR interferograms, GPS observations and ERA-Interim reanalysis

    Science.gov (United States)

    Tang, Wei; Liao, Mingsheng; Zhang, Lu; Li, Wei; Yu, Weimin

    2016-09-01

    A high spatial and temporal resolution of the precipitable water vapour (PWV) in the atmosphere is a key requirement for the short-scale weather forecasting and climate research. The aim of this work is to derive temporally differenced maps of the spatial distribution of PWV by analysing the tropospheric delay "noise" in interferometric synthetic aperture radar (InSAR). Time series maps of differential PWV were obtained by processing a set of ENVISAT ASAR (Advanced Synthetic Aperture Radar) images covering the area of southern California, USA from 6 October 2007 to 29 November 2008. To get a more accurate PWV, the component of hydrostatic delay was calculated and subtracted by using ERA-Interim reanalysis products. In addition, the ERA-Interim was used to compute the conversion factors required to convert the zenith wet delay to water vapour. The InSAR-derived differential PWV maps were calibrated by means of the GPS PWV measurements over the study area. We validated our results against the measurements of PWV derived from the Medium Resolution Imaging Spectrometer (MERIS) which was located together with the ASAR sensor on board the ENVISAT satellite. Our comparative results show strong spatial correlations between the two data sets. The difference maps have Gaussian distributions with mean values close to zero and standard deviations below 2 mm. The advantage of the InSAR technique is that it provides water vapour distribution with a spatial resolution as fine as 20 m and an accuracy of ˜ 2 mm. Such high-spatial-resolution maps of PWV could lead to much greater accuracy in meteorological understanding and quantitative precipitation forecasts. With the launch of Sentinel-1A and Sentinel-1B satellites, every few days (6 days) new SAR images can be acquired with a wide swath up to 250 km, enabling a unique operational service for InSAR-based water vapour maps with unprecedented spatial and temporal resolution.

  20. Report of the Fourth interim meeting of the Seabed Working Group Engineering Studies Task Group, 3-6 October 1983, at Rijks Geologische Dienst, Haarlem, The Netherlands

    International Nuclear Information System (INIS)

    This report presents the results of the fourth interim meeting of the Seabed Working Group's (SWG) Engineering Studies Task Group (ESTG). This task group is charged with determining whether the engineering technology exists to emplace waste canisters in deep ocean sediments. The fourth interim meeting, held at Rijks Geologische Dienst, Haarlem, The Netherlands, 3-6 October 1983, reviewed progress made by the various national programs since the ESTG third interim meeting (July 1982) and developed a table of requirements for processing samples for a geotechnical properties data base. Other items addressed were (1) potential methods of instrumenting penetrators to obtain in situ measurements, (2) procedures for evaluating and quantifying the disturbed zone created by an emplaced penetrator, (3) review and modification of the current draft version of the SWG Five-Year Plan, (4) review and extension of the ESTG detailed plan for penetrator tests, and (5) details of the penetrator tests scheduled for March 1984 in the Nares Abyssal Plain using the research vessel M/V TYRO. The review of the national programs indicated significant progress when measured against the integrated ESTG five-year plan which results in a joint evaluation of engineering feasibility of subseabed disposal based upon (1) a demonstration of an emplacement capability, (2) an evaluation of the zone of sediment disturbance created during emplacement, (3) the existence of acceptable emplacement models, and (4) an acceptable engineering data base. A table of geotechnical sample-processing requirements is being developed to provide guidance for the other task groups that may have the opportunity to furnish suitable geotechnical samples to the ESTG as well as to provide some measure of consistency within the ESTG for the development of the engineering data base for the SWG study areas

  1. 77 FR 55230 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-01; Compliance With...

    Science.gov (United States)

    2012-09-07

    ... COMMISSION Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-01; Compliance With...-Learned Project Directorate interim staff guidance; issuance. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing the Final Japan Lessons-Learned Project Directorate...

  2. 77 FR 71019 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-04; Guidance on...

    Science.gov (United States)

    2012-11-28

    ... COMMISSION Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-04; Guidance on...: Nuclear Regulatory Commission. ACTION: Japan Lessons-Learned Project Directorate Interim Staff Guidance issuance. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing the Final Japan...

  3. 78 FR 48201 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2013-01; Guidance for...

    Science.gov (United States)

    2013-08-07

    ... COMMISSION Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2013-01; Guidance for... Lessons-Learned Project Directorate Interim Staff Guidance (JLD-ISG), JLD-ISG-2013-01, ``Guidance for... to http://www.nrc.gov/reading-rm/doc-collections/isg/japan-lessons-learned.html and refer to...

  4. 75 FR 41726 - Interim Final Rules for Group Health Plans and Health Insurance Issuers Relating to Coverage of...

    Science.gov (United States)

    2010-07-19

    ... Internet search engines. No deletions, modifications, or redactions will be made to the comments received... April 14, 2010 (75 FR 19297). The second phase was interim final regulations implementing PHS Act... May 13, 2010 (75 FR 27122). The third phase was interim final regulations implementing section 1251...

  5. 75 FR 43329 - Interim Final Rules for Group Health Plans and Health Insurance Issuers Relating to Internal...

    Science.gov (United States)

    2010-07-23

    ... can be retrieved by most Internet search engines. No deletions, modifications, or redactions will be... Register on April 14, 2010 (75 FR 19297). The second phase was interim final regulations implementing PHS... Register on May 13, 2010 (75 FR 27122). The third phase was interim final regulations implementing...

  6. 33 CFR 96.350 - Interim Document of Compliance certificate: what is it and when can it be used?

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Interim Document of Compliance certificate: what is it and when can it be used? 96.350 Section 96.350 Navigation and Navigable Waters COAST...? § 96.350 Interim Document of Compliance certificate: what is it and when can it be used? (a) An...

  7. 76 FR 63676 - Final Division of Safety Systems Interim Staff Guidance DSS-ISG-2010-01: Staff Guidance Regarding...

    Science.gov (United States)

    2011-10-13

    ... COMMISSION Final Division of Safety Systems Interim Staff Guidance DSS-ISG- 2010-01: Staff Guidance Regarding... final Division of Safety Systems Interim Staff Guidance, (DSS-ISG) DSS- ISG-2010-01, ``Staff Guidance... guidance to the NRC staff reviewer to address the increased complexity of recent spent fuel pool...

  8. 78 FR 53183 - Request for Public Comments Regarding the Interim Environmental Review of the Trans-Pacific...

    Science.gov (United States)

    2013-08-28

    ... interim environmental review of the proposed Trans-Pacific Partnership Agreement (TPP). The interim... with Executive Order 13141-Environmental Review of Trade Agreements (64 FR 63,169, Nov. 18, 1999) and its implementing guidelines (65 FR 79,442, Dec. 19, 2000) and report on such reviews to the...

  9. 40 CFR 262.212 - Making the hazardous waste determination at an on-site interim status or permitted treatment...

    Science.gov (United States)

    2010-07-01

    ....212 Making the hazardous waste determination at an on-site interim status or permitted treatment... hazardous waste permit or interim status as soon as it arrives in the on-site treatment, storage or disposal... permitted treatment, storage or disposal facility. (e) If the unwanted material is a hazardous waste,...

  10. Immobilized High Level Waste (HLW) Interim Storage Alternative Generation and analysis and Decision Report 2nd Generation Implementing Architecture

    Energy Technology Data Exchange (ETDEWEB)

    CALMUS, R.B.

    2000-09-14

    Two alternative approaches were previously identified to provide second-generation interim storage of Immobilized High-Level Waste (IHLW). One approach was retrofit modification of the Fuel and Materials Examination Facility (FMEF) to accommodate IHLW. The results of the evaluation of the FMEF as the second-generation IHLW interim storage facility and subsequent decision process are provided in this document.

  11. 75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

    Science.gov (United States)

    2010-01-07

    ... the National Oil and Hazardous Substances Pollution Contingency Plan (NCP) (40 CFR 300.430(e)(2)(i... AGENCY RIN 2050-ZA05 Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA...) developed in the Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at...

  12. Environmental assessment for 881 Hillside (High Priority Sites) interim remedial action

    International Nuclear Information System (INIS)

    This Environmental Assessment evaluates the impact of an interim remedial action proposed for the High Priority Sites (881 Hillside Area) at the Rocky Flats Plant (RFP). This interim action is to be conducted to minimize the release of hazardous substances from the 881 Hillside Area that pose a potential long-term threat to public health and the environment. This document integrates current site characterization data and environmental analyses required by the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) or ''Superfund'' process, into an environmental assessment pursuant to the National Environmental Policy Act (NEPA). Characterization of the 881 Hillside Area is continuing. Consequently, a final remedial action has not yet been proposed. Environmental impacts associated with the proposed interim remedial action and reasonable alternatives designed to remove organic and inorganic contaminants, including radionuclides, from alluvial groundwater in the 881 Hillside Area are addressed. 24 refs., 5 figs., 23 tabs

  13. Process evaluation of the Bonneville Power Administration Interim Residential Weatherization Program

    Energy Technology Data Exchange (ETDEWEB)

    Lerman, D.I.; Bronfman, B.H.

    1984-08-01

    A process evaluation of the Bonneville Power Administration (BPA) Interim Residential Weatherization Program was conducted between December of 1983 and March of 1984. For this evaluation seven of the utility participants were visited, as were the four BPA area offices serving those utilities. Interviews were also conducted with key staff members at BPA headquarters in Portland. This report describes the Interim Program and the elements of the BPA organizational structure involved in management of the program. It deals also with the implementation process at the seven utilities involved in the evaluation; perceptions of the key actors as to the strengths and weaknesses of the program; the adequacy of the BPA reimbursement for utility administrative expenses; and finally lessons for the Long-Term Program, the BPA residential program which followed the Interim Program in October 1983.

  14. THE IMPORTANCE OF FINANCIAL INTERIM REPORTING FOR THE POSITION OF COMPANIES

    Directory of Open Access Journals (Sweden)

    Claudia‐Elena\tGRIGORAȘ‐ICHIM

    2015-12-01

    Full Text Available The importance that each company must grant to the strategic sources of information generates our concern for analysis of the interim financial reporting. In every enterprise, there are doubts on the usefulness of interim financial reports, given the following elements: the necessary time for their preparation (relatively long, their restricted character and the resources necessary to establish them. Finding a common solution to these problems and, implicitly, increasing the interest for interim financial reporting, can help to increase the economic performance of the company, either by reducing the unnecessary costs related to time, or by increasing communication and transparency with third parties. An appropriate management can act early in the direction of counteracting the negative effects in their company or prevention of any commercial or production failures, the overall economic trends in that field and increasing productivity. Starting from these premises, we propose a research in order to capture the main aspects related to the mentioned issues.

  15. Development of Accident Scenario for Interim Spent Fuel Storage Facility Based on Fukushima Accident

    International Nuclear Information System (INIS)

    700 MTU of spent nuclear fuel is discharged from nuclear fleet every year and spent fuel storage is currently 70.9% full. The on-site wet type spent fuel storage pool of each NPP(nuclear power plants) in Korea will shortly exceed its storage limit. Backdrop, the Korean government has rolled out a plan to construct an interim spent fuel storage facility by 2024. However, the type of interim spent fuel storage facility has not been decided yet in detail. The Fukushima accident has resulted in more stringent requirements for nuclear facilities in case of beyond design basis accidents. Therefore, there has been growing demand for developing scenario on interim storage facility to prepare for beyond design basis accidents and conducting dose assessment based on the scenario to verify the safety of each type of storage

  16. Measuring $\

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Jessica Sarah [Univ. of Cambridge (United Kingdom)

    2011-01-01

    The MINOS Experiment consists of two steel-scintillator calorimeters, sampling the long baseline NuMI muon neutrino beam. It was designed to make a precise measurement of the ‘atmospheric’ neutrino mixing parameters, Δm2 atm. and sin2 (2 atm.). The Near Detector measures the initial spectrum of the neutrino beam 1km from the production target, and the Far Detector, at a distance of 735 km, measures the impact of oscillations in the neutrino energy spectrum. Work performed to validate the quality of the data collected by the Near Detector is presented as part of this thesis. This thesis primarily details the results of a vμ disappearance analysis, and presents a new sophisticated fitting software framework, which employs a maximum likelihood method to extract the best fit oscillation parameters. The software is entirely decoupled from the extrapolation procedure between the detectors, and is capable of fitting multiple event samples (defined by the selections applied) in parallel, and any combination of energy dependent and independent sources of systematic error. Two techniques to improve the sensitivity of the oscillation measurement were also developed. The inclusion of information on the energy resolution of the neutrino events results in a significant improvement in the allowed region for the oscillation parameters. The degree to which sin2 (2θ )= 1.0 could be disfavoured with the exposure of the current dataset if the true mixing angle was non-maximal, was also investigated, with an improved neutrino energy reconstruction for very low energy events. The best fit oscillation parameters, obtained by the fitting software and incorporating resolution information were: | Δm2| = 2.32+0.12 -0.08×10-3 eV2 and sin2 (2θ ) > 0.90(90% C.L.). The analysis provides the current world best measurement of the atmospheric neutrino mass

  17. 1987 Federal interim storage fee study: A technical and economic analysis

    International Nuclear Information System (INIS)

    This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs

  18. Dynamics of Flexible Rotor Systems with an Interim Mass Unbalanced Disk Using a Spectral Element Model

    OpenAIRE

    Sangkyu Choi; Usik Lee

    2014-01-01

    A frequency domain spectral element model is developed for a rotor system that consists of two spinning shafts and an interim disk or blade system. In this study, the shafts are represented by spinning Timoshenko beam models, and the interim disk system is represented by a uniform thick rigid disk with an unbalanced mass. In our derivation of the governing equations of motion of the disk system, the disk is considered to be wobbling about the geometric center of the disk at which the spinning...

  19. Retrieval of plutonium-contaminated waste materials from interim storage

    International Nuclear Information System (INIS)

    Plutonium-contaminated solid waste materials (PCM) (contact-handled transuranic waste) originating from the early UK defence program were placed for interim storage in existing structures at Drigg, a site some 6km (4 miles) from Sellafield (formerly known as Windscale), the UK reprocessing and plutonium production site. The waste was contained within steel drums of up to 205 liters (55 US gallons) capacity or was contained in larger timber and plastic cuboid containment, known as 'crates'. The paper will describe the typical constituents of the drummed waste and of the crated waste, a proportion of which consists of redundant glove box facilities from the early production lines themselves. British Nuclear Fuels pie (BNFL) became responsible for the Drigg site and waste stored on it at Company formation in 1971. In the mid-1970s, a commitment was given that PCM would be removed from the Drigg site leaving it to fulfil its role as the principal site in the UK for the disposal of solid low level radioactive waste from Sellafield and from elsewhere. Following a program of design and procurement of necessary facilities, retrieval of drummed PCM began in 1976. A team of operators, not full-time on this task, removed all drummed PCM from the existing storage structures, known as magazines, by 1986. This work is briefly reviewed in the paper. Five of the magazines contain about 200 non-drummed packages which remain to be removed. Facilities to permit the retrieval of that waste have been designed and are now being procured and installed so that first retrieval can begin during this year. The project team has addressed all aspects of safety and has needed to obtain necessary consents and authorizations from Her Majesty's Inspectorate of Pollution, so far as the safety of the environment and of members of the public is concerned, from Her Majesty's Nuclear Installations Inspectorate, so far as the safety of the workforce is concerned, and from the Department of Transport, so

  20. Plutonium Immobilization Form Development Interim and Final Data Report Summaries

    Energy Technology Data Exchange (ETDEWEB)

    VanKonynenburg, R.; Ebbinghaus, B.

    2000-06-01

    Contained within this report are summaries of the available interim and final data summary reports provided by ANSTO, ANL, LLNL, and WSRC in support of work in the Form Development activity in the Plutonium Immobilization Development and Testing Program. Milestone reports and technical papers prepared for journals or conference proceedings are not included in this list. This document covers work from about 1997 to the present. All of the following reports are available from the Plutonium Immobilization Program Document Control Center (DCC) at LLNL. In most cases, the documents can also be obtained from the libraries the originating site or from the document's authors. All samples of the various formulations discussed in the following summaries were prepared by one of four processes: Wet-milling, dry-milling, an alkoxide-nitrate process, or attritor milling. The fabrication processes differ primarily in the mixing steps. The wet milling process is the one most commonly used. It is a simple ball milling process where water is added that provides intimate mixing of the materials. The dry milling process is a worst case dry mixing process. The alkoxide-nitrate process provides for very intimate mixing and is used when equilibrium samples are desired. The attritor milling process simulates the process being developed for the Plutonium Immobilization Plant. After mixing, the subsequent calcination and consolidation steps are generally the same. Most samples were consolidated by cold pressing and sintering although some of the earlier samples or Some of the single-phase samples were prepared by hot pressing. The sample identification numbers (ID's) that are referenced in the summaries (e.g. A-0, B3-13, etc.) are described in the Sample Test Matrix (PIP-99-012 and PIP-00-016). Samples which contain both plutonium and uranium are given the designation Hf-Pu-U samples. When Ce was used as a surrogate for Pu, the designation is Hf-Ce-U. When Th was used as a

  1. Hazelwood Interim Storage Site annual site environmental report: Calendar year 1986

    International Nuclear Information System (INIS)

    During 1986, the environmental monitoring program was continued at the Hazelwood Interim Storage Site (HISS), a US Department of Energy (DOE) facility located in the City of Hazelwood, Missouri. Originally known as the Cotter Corporation site on Latty Avenue in Hazelwood, the HISS is presently used for the storage of soils contaminated with residual radioactive material. As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action and environmental monitoring program are being conducted at the site and at vicinity properties by Bechtel National, Inc., Project Management Contractor for FUSRAP. The monitoring program at the HISS measures radon gas concentrations in air; external gamma radiation levels; and uranium, radium, and thorium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the scenario described in this report, the maximally exposed individual at the HISS would receive an annual external exposure approximately equivalent to 2% of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than the exposure a person would receive during a round-trip flight from New York to Los Angeles. The cumulative dose to the population within an 80-km (50-mi) radius of the HISS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the HISS is in compliance with the DOE radiation protection standard. 11 refs., 6 figs., 10 tabs

  2. Colonie Interim Storage Site annual environmental report for calendar year 1991, Colonie, New York

    International Nuclear Information System (INIS)

    This document describes the environmental monitoring program at the Colonie Interim Storage Site (CISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring at CISS began in 1984 when Congress added the site to the US Department of Energy's Formerly Utilized Sites Remedial Action Program. CISS property and surrounding areas were radioactively contaminated by operations conducted by National Lead Industries, which manufactured various components from uranium and thorium from 1958 to 1984. The environmental monitoring program at CISS includes sampling networks for external gamma radiation exposure and for radium-226, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in groundwater. In 1992 the program will also include sampling networks for radioactive and chemical contaminants in stormwater to meet permit application requirements under the Clean Water Act. Monitoring results are compared with applicable Environmental Protection Agency (EPA) standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE.orders. Environmental standards are established to protect public health and the environment. Results of environmental monitoring during 1991 indicate that average concentrations of radioactive contaminants of concern were well below applicable standards and DCGS. Concentrations of some chemical contaminants in groundwater were above-the New York State Department of Environmental Conservation (Class GA) and EPA guidelines for drinking water. The potential annual radiation exposure (excluding background) calculated for a hypothetical maximally exposed individual is 0.23 mrem (milliroentgen equivalent man), which is less than an individual would receive while traveling in an airplane at 12,000 meters (39,000 feet) for one hour

  3. 78 FR 76160 - Public Housing Assessment System (PHAS) Capital Fund Interim Scoring Notice: Reinstitution of...

    Science.gov (United States)

    2013-12-16

    ... by an interim rule published on February 23, 2011, at 76 FR 10136. The Capital Fund Program Indicator... Scoring Notice, also published on February 23, 2011, at 76 FR 10053. Under this indicator, PHAs can... occupancy ] rate is accounted for under another indicator, the management operations indicator, at 24...

  4. 76 FR 57657 - Tetrachlorvinphos; Extension of Time-Limited Interim Pesticide Tolerances

    Science.gov (United States)

    2011-09-16

    ... residues in whole milk and of which no more than 0.05 ppm is tetrachlorvinphos per se) at 0.05 ppm; poultry..., except kidney and liver.. 1.0 March 18, 2013. Milk, fat (reflecting negligible residues in 0.05 March 18... AGENCY 40 CFR Part 180 Tetrachlorvinphos; Extension of Time-Limited Interim Pesticide Tolerances...

  5. 40 CFR 57.302 - Performance level of interim constant controls.

    Science.gov (United States)

    2010-07-01

    ... exceed the following: (i) For sulfuric acid plants on copper smelters, 12-hour running average; (ii) For... smelters, 2-hour running average; (iv) For dimethylaniline (DMA) scrubbing units on copper smelters, 2-hour... 40 Protection of Environment 5 2010-07-01 2010-07-01 false Performance level of interim...

  6. 76 FR 40777 - Interim Enforcement Policy for Certain Fire Protection Issues

    Science.gov (United States)

    2011-07-12

    ... Register notice Date Brief description 69 FR 33684 June 16, 2004 Describes the initial interim Enforcement Policy on fire protection. 70 FR 2662 January 14, 2005 Revises the submittal date for licensees to receive enforcement discretion for existing identified fire protection program noncompliant issues. 71...

  7. Interim Policy Options for Commercialization of Solar Heating and Cooling Systems.

    Science.gov (United States)

    Bezdek, Roger

    This interim report reviews the major incentive policy options available to accelerate market penetration of solar heating and cooling (SHAC) systems. Feasible policy options designed to overcome existing barriers to commercial acceptance and market penetration are identified and evaluated. The report is divided into seven sections, each dealing…

  8. 46 CFR 8.570 - Interim approval of prototype SIP company or vessel plans.

    Science.gov (United States)

    2010-10-01

    ... of 46 CFR part 2, subpart 2.01 of this chapter. ... 46 Shipping 1 2010-10-01 2010-10-01 false Interim approval of prototype SIP company or vessel... of prototype SIP company or vessel plans. (a) A company operating under an approved prototype...

  9. Interim-status groundwater monitoring plan for the 216-B-63 trench

    Energy Technology Data Exchange (ETDEWEB)

    Sweeney, M.D.

    1995-02-09

    This document outlines the groundwater monitoring plan, under RCRA regulations in 40 CFR 265 Subpart F and WAC173-300-400, for the 216-B-63 Trench. This interim status facility is being sampled under detection monitoring criteria and this plan provides current program conditions and requirements.

  10. Study of New Youth Initiatives in Apprenticeship. Interim Report. Volume 2: Site Visit Reports.

    Science.gov (United States)

    CSR, Inc., Washington, DC.

    This second volume of the interim report provides detailed case study reports on each of the eight Youth Apprenticeship Projects. (Volume 1, an overview of data from the site visits, is available separately as CE 032 791.) Discussion areas covered in each site visit report are local context/operational environment, administrative information,…

  11. Engineering Task Plan for Hose In Hose Transfer Lines for the Interim Stabilization Program

    Energy Technology Data Exchange (ETDEWEB)

    TORRES, T.D.

    2000-08-16

    The document is the Engineering Task Plan for the engineering, design services, planning, project integration and management support for the design, modification, installation and testing of an over ground transfer (OGT) system to support the interim stabilization of S/SX and U Tank Farms.

  12. Engineering Task Plan for Hose In Hose Transfer Lines for the Interim Stabilization Program

    Energy Technology Data Exchange (ETDEWEB)

    RUNG, M.P.

    2000-06-20

    This document is the Engineering Task Plan for the engineering, design services, planning, project integration and management support for the design, modification, installation and testing of an over ground transfer (OGT) system to support the interim stabilization of nine tanks in the 241-S/SX Tank Farms.

  13. 40 CFR 80.156 - Liability for violations of the interim detergent program controls and prohibitions.

    Science.gov (United States)

    2010-07-01

    ... gasoline non-conformity violations caused solely by the addition of misadditized ethanol or other PRC to... Detergent Gasoline § 80.156 Liability for violations of the interim detergent program controls and prohibitions. (a) Persons liable—(1) Gasoline non-conformity. Where gasoline contained in any storage tank...

  14. 76 FR 9381 - Notice of Availability of Interim Staff Guidance Documents for Spent Fuel Storage Casks

    Science.gov (United States)

    2011-02-17

    ... COMMISSION Notice of Availability of Interim Staff Guidance Documents for Spent Fuel Storage Casks AGENCY... Gordon, Structural Mechanics and Materials Branch, Division of Spent Fuel Storage and Transportation... performing technical reviews of spent fuel storage and transportation packaging licensing actions.'' This...

  15. Educative Accountability Policies for Tasmania's Locally Managed Schools: Interim Policy Research Findings.

    Science.gov (United States)

    Macpherson, R. J. S.

    1996-01-01

    Summarizes interim findings of a policy research project in Tasmania, Australia, aimed at producing educative accountability options for identifying processes and criteria to improve learning, teaching, and leadership. Identifies preferred accountability criteria and processes in Tasmania's locally managed school district, maps patterns of…

  16. 77 FR 65366 - Interim Procedures for Considering Requests From the Public for Textile and Apparel Safeguard...

    Science.gov (United States)

    2012-10-26

    .... 8818, 77 FR 29519 (May 18, 2012). Background Title III, Subtitle B, Section 321 through Section 328 of... IMPLEMENTATION OF TEXTILE AGREEMENTS [Docket :121018560-2560-01; OMB Control :0625-0271 (Expiration: 10/31/2015)] RIN 0625-XC003 Interim Procedures for Considering Requests From the Public for Textile and...

  17. 77 FR 15997 - Interim Procedures for Considering Requests From the Public for Textile and Apparel Safeguard...

    Science.gov (United States)

    2012-03-19

    ... force. In Presidential Proclamation 8783 (77 FR 14265, March 9, 2012), the President delegated to the... Apparel Safeguard Actions on Imports from Peru'', 76 FR 9556 (February 18, 2011). A request will only be... IMPLEMENTATION OF TEXTILE AGREEMENTS Interim Procedures for Considering Requests From the Public for Textile...

  18. 78 FR 31886 - Interim Procedures for Considering Requests From the Public for Textile and Apparel Safeguard...

    Science.gov (United States)

    2013-05-28

    ... 321 through Section 328 of the Implementation Act and Proclamation No. 8894, 77 FR 66507 (November 5... IMPLEMENTATION OF TEXTILE AGREEMENTS [Docket : 130430427-3427-01; OMB Control : 0625-0274 (Expiration: 04/30/2016)] RIN 0625-XC006 Interim Procedures for Considering Requests From the Public for Textile and...

  19. 76 FR 52996 - Public Company Accounting Oversight Board; Order Approving Proposed Temporary Rule for an Interim...

    Science.gov (United States)

    2011-08-24

    .... 34-64814 (Jul. 6, 2011) [76 FR 40961 (Jul. 12, 2011)]. II. Discussion Section 982 of the Dodd-Frank... COMMISSION Public Company Accounting Oversight Board; Order Approving Proposed Temporary Rule for an Interim..., 2011, the Public Company Accounting Oversight Board (the ``Board'' or the ``PCAOB'') filed with...

  20. THE INTERIM EXPERTS’ COUNCIL RESOLUTION ON THE EMPA-REG OUTCOME TRIAL ISSUES

    Directory of Open Access Journals (Sweden)

    M. V. Shestakova

    2016-05-01

    Full Text Available The interdisciplinary interim experts’ council on March 3, 2016 in Moscow have considered the EMPA-REG OUTCOME trial results and suggested a number of propositions and recommendations on further empagliflozin’s cardiovascular effects investigation and its clinical application in patients with type 2 diabetes at high cardiovascular risk.

  1. THE INTERIM EXPERTS’ COUNCIL RESOLUTION ON THE EMPA-REG OUTCOME TRIAL ISSUES

    OpenAIRE

    M V Shestakova; S. A. Boytsov; O. M. Drapkina; T Yu Demidova; Drexel, H.; M B Antsiferov; N A Petunina; I. A. Chernikova; V. Yu. Kalashnikov; T P Bardymova; V. K. Protasov; A. Yu. Babenko; L. A. Ruyatkina; V V Klimontov; V. V. Salukhov

    2016-01-01

    The interdisciplinary interim experts’ council on March 3, 2016 in Moscow have considered the EMPA-REG OUTCOME trial results and suggested a number of propositions and recommendations on further empagliflozin’s cardiovascular effects investigation and its clinical application in patients with type 2 diabetes at high cardiovascular risk.

  2. Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2A. GSFLS visit findings (appendix). Interim report

    International Nuclear Information System (INIS)

    This appendix is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This appendix provides the legal/regulatory reference material, supportive of Volume 2 - GSFLS Visit Finding and Evaluations; and certain background material on British Nuclear Fuel Limited

  3. A Reading Program for Mexican-American Children. Second Interim Report.

    Science.gov (United States)

    Amsden, Constance

    A second interim report on a reading program for Mexican-American children in an East Los Angeles elementary school notes that reading ability in the primary grades has improved. In January, 1967, the average first grade reading score on the Stanford Reading Test was at the third percentile, whereas in January, 1968, the score was at the eighth…

  4. A Reading Program for Mexican-American Children, Third Interim Report. Final Report.

    Science.gov (United States)

    Amsden, Constance

    The third and final interim report is devoted to analysis of research data relating to a 3-year experimental reading program for Mexican American children at the Malabar Street School in Los Angeles. The program utilized language development methods, individualized instruction, and parental assistance to improve the children's competencies. Using…

  5. Safety evaluation for the interim stabilization of Tank 241-C-103

    Energy Technology Data Exchange (ETDEWEB)

    Geschke, G.R.

    1995-03-01

    This document provides the basis for interim stabilization of tank 241-C-103. The document covers the removal of the organic liquid layer and the aqueous supernatant from tank 241-C-103. Hazards are identified, consequences are calculated and controls to mitigate or prevent potential accidents are developed.

  6. 78 FR 56752 - Interim Staff Guidance Specific Environmental Guidance for Integral Pressurized Water Reactors...

    Science.gov (United States)

    2013-09-13

    ... COMMISSION Interim Staff Guidance Specific Environmental Guidance for Integral Pressurized Water Reactors... and operate integral pressurized water reactors (iPWR). This guidance applies to environmental reviews... Environmental Guidance for iPWR Reviews.'' The purpose of this ISG is to clarify the NRC guidance...

  7. 77 FR 74512 - Interim Policy Leasing for Renewable Energy Data Collection Facility on the Outer Continental...

    Science.gov (United States)

    2012-12-14

    ... testing facilities on the OCS (72 FR 62673). An applicant has submitted a lease proposal to BOEM pursuant... the Federal Register (72 FR 62673), BOEM announced that it had established an interim policy under... renewable energy activities and initiatives (73 FR 21152). BOEM also took into consideration the...

  8. 14 CFR 60.21 - Interim qualification of FSTDs for new aircraft types or models.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Interim qualification of FSTDs for new aircraft types or models. 60.21 Section 60.21 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION... aircraft, even though the aircraft manufacturer's aircraft data package is preliminary, if the...

  9. Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2A. GSFLS visit findings (appendix). Interim report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-31

    This appendix is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This appendix provides the legal/regulatory reference material, supportive of Volume 2 - GSFLS Visit Finding and Evaluations; and certain background material on British Nuclear Fuel Limited (BNFL).

  10. Evaluation of Hose in Hose Transfer Line Service Life for Hanford's Interim Stabilization Program

    International Nuclear Information System (INIS)

    RPP-6153, Engineering Task Plan for Hose-in-Hose Transfer System for the Interim Stabilization Program, defines the programmatic goals, functional requirements, and technical criteria for the development and subsequent installation of transfer line equipment to support Hanford's Interim Stabilization Program. RPP-6028, Specification for Hose in Hose Transfer Lines for Hanford's Interim Stabilization Program, has been issued to define the specific requirements for the design, manufacture, and verification of transfer line assemblies for specific waste transfer applications. Included in RPP-6028 are tables defining the chemical constituents of concern to which transfer lines will be exposed. Current Interim Stabilization Program planning forecasts that the at-grade transfer lines will be required to convey pumpable waste for as much as three years after commissioning. Prudent engineering dictates that the equipment placed in service have a working life in excess of this forecasted time period, with some margin to allow for future adjustments to the planned schedule. This document evaluates the effective service life of the Hose-in-Hose Transfer Lines, based on information submitted by the manufacturer and published literature. The effective service life of transfer line assemblies is a function of several factors. Foremost among these are process fluid characteristics, ambient environmental conditions, and the manufacturer's stated shelf life. This evaluation examines the manufacturer's certification of shelf life, the manufacturer's certifications of chemical compatibility with waste, and published literature on the effects of exposure to ionizing radiation on the mechanical properties of elastomeric materials to evaluate transfer line service life

  11. 78 FR 67442 - Congestion Mitigation and Air Quality Improvement Program Interim Guidance

    Science.gov (United States)

    2013-11-12

    ... scope of CMAQ eligibility for electric vehicle charging stations and natural gas vehicle refueling... focus on construction equipment and vehicles, and summarizes the interim approach to calculating the PM... types of rail service in a January 16, 2002, Federal Register notice (67 FR 2278), and in a March...

  12. 77 FR 4758 - Foreign-Trade Zone 59-Lincoln, Nebraska, Application for Temporary/Interim Manufacturing...

    Science.gov (United States)

    2012-01-31

    ... Manufacturing Authority, Novartis Consumer Health, Inc. (Pharmaceutical Product Manufacturing), Lincoln, NE An... Lincoln Foreign-Trade Zone, Inc., grantee of FTZ 59, requesting temporary/interim manufacturing (T/ IM... request to the FTZ Board for FTZ manufacturing authority beyond a two-year period, which may...

  13. Experience collecting interim data on mortality: an example from the RALES study

    Directory of Open Access Journals (Sweden)

    Kulbertus Henri

    2001-02-01

    Full Text Available Abstract Introduction The Randomized Aldactone Evaluation Study (RALES randomized 822 patients to receive 25 mg spironolactone daily and 841 to receive placebo. The primary endpoint was death from all causes. Randomization began on March 24, 1995; recruitment was completed on December 31, 1996; follow-up was scheduled to continue through December 31, 1999. Evidence of a sizeable benefit on mortality emerged early in the RALES. The RALES data safety monitoring board (DSMB, which met semiannually throughout the trial, used a prespecified statistical guideline to recommend stopping for efficacy. At the DSMB's request, its meetings were preceded by an 'endpoint sweep', that is, a census of all participants to confirm their vital status. Methods We used computer simulation to evaluate the effect of the sweeps. Results The sweeps led to an estimated 5 to 8% increase in the number of reported deaths at the fourth and fifth interim analyses. The data crossed the statistical boundary at the fifth interim analysis. If investigators had reported all deaths within the protocol-required 24-h window, the DSMB might have recommended stopping after the fourth interim analysis. Discussion Although endpoint sweeps can cause practical problems at the clinical centers, sweeps are very useful if the intervals between patient visits or contact are long or if endpoints require adjudication by committee, reading center, or central laboratory. Conclusion We recommend that trials with interim analyses institute active reporting of the primary endpoints and endpoint sweeps.

  14. 78 FR 72897 - Draft Guidance for Industry on Interim Product Reporting for Human Drug Compounding Outsourcing...

    Science.gov (United States)

    2013-12-04

    ... Human Drug Compounding Outsourcing Facilities Under Section 503B of the Federal Food, Drug, and Cosmetic... entitled ``Interim Product Reporting for Human Drug Compounding Outsourcing Facilities Under Section 503B... register as outsourcing facilities (outsourcing facilities). DATES: Although you can comment on...

  15. 40 CFR 265.352 - Interim status incinerators burning particular hazardous wastes.

    Science.gov (United States)

    2010-07-01

    ... HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES Incinerators § 265.352 Interim status incinerators burning particular hazardous wastes. (a) Owners or operators of incinerators subject to this... particular hazardous wastes. 265.352 Section 265.352 Protection of Environment ENVIRONMENTAL...

  16. Neutron spectrometry at the interim storage facility for spent nuclear fuel

    CERN Document Server

    Králik, M; Studeny, J

    2002-01-01

    Dosimetric characteristics of neutron and photon components of mixed fields around casks for spent nuclear fuel have been determined at various places at the dry interim storage facility. The results obtained with metrological grade instruments were compared with data provided by usual survey meters for both neutrons and photons.

  17. Wendell Flinchum to serve as interim chief of Virginia Tech Police

    OpenAIRE

    Owczarski, Mark

    2006-01-01

    Lt. Wendell Flinchum, a 21-year veteran of the Virginia Tech Police Department, has been named the department's interim chief of police effective July 1. Flinchum's appointment follows the resignation of Chief Debra Duncan, who will leave the university to become police chief for the City of Monroe, N.C.

  18. Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 & 2

    Energy Technology Data Exchange (ETDEWEB)

    CARRELL, R D

    2002-07-16

    The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft{sup 2} and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available.

  19. Thermal-hydraulic experiment and analysis for interim dry storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    The experimental and numerical studies of interim storages for nuclear spent fuels have been performed to investigate thermal-hydraulic characteristics of the dry storage systems and to propose new methodologies for the analysis and the design. Three separate researches have been performed in the present study: (a) Development of a scaling methodology and thermal-hydraulic experiment of a single spent fuel assembly simulating a dry storage cask: (b) Full-scope simulation of a dry storage cask by the use of Computational Fluid Dynamics (CFD) code: (c) Thermal-hydraulic design of a tunnel-type interim storage facility. In the first study, a scaling methodology has been developed to design a scaled-down canister. The scaling was performed in two steps. For the first step, the height of a spent fuel assembly was reduced from full height to half height. In order to consider the effect of height reduction on the natural convection, the scaling law of Ishii and Kataoka (1984) was employed. For the second step, the quantity of spent fuel assemblies was reduced from multiple assemblies to a single assembly. The scaling methodology was validated through the comparison with the experiment of the TN24P cask. The Peak Cladding Temperature (PCT), temperature gradients, and the axial and radial temperature distribution in the nondimensional forms were in good agreement with the experimental data. Based on the developed methodology, we have performed a single assembly experiment which was designed to simulate the full scale of the TN24P cask. The experimental data was compared with the CFD calculations. It turns out that their PCTs were less than the maximum allowable temperature for the fuel cladding and that the differences of their PCTs were agreed within 3 .deg. C, which was less than measurement uncertainty. In the second study, the full-scope simulations of the TN24P cask were performed by FLUENT. In order to investigate the sensitivity of the numerical and physical

  20. The CARISMA project for measurement of fracture-mechanical characteristics on pre-exposed samples for the German PWR reactor lines. Status and interim report; Das Projekt CARISMA zur Ermittlung von Bruchmechanikkennwerten an vorbestrahlten Proben fuer die deutsche DWR-Baulinien. Status und Zwischenbericht

    Energy Technology Data Exchange (ETDEWEB)

    Hein, H.; Keim, E.; Schnabel, H. [AREVA NP GmbH, Erlangen (Germany)

    2006-07-01

    In 1983 and 1985, samples of original pressure vessel material of German PWR reactors were exposed to radiation in the VAK reactor in order to ensure pressure vessel integrity in the context of future design changes and possible life-prolonging measures. In the CARISMA project (Crack initiation and ARrest of Irradiated Steel Materials), some of the test pieces were analyzed by mechanical-technological materials tests and the data were used for the further development of new safety concepts. One major goal of the project, which will run until 2007, is the provision of an extensive experimental data base for irradiated and non-irradiated materials from all four types of PWR reactors in operation in Germany. Irradiations were carried out in the VAK reactor in a fluency range of 6.10{sup 18} ro 4.10{sup 19}. The data base is applied to the two concepts of RT{sub NDT} and Master Curve, and fracture toughness characteristics are determinted both for crack initiation and crack arrest. (orig.)

  1. Age of stratospheric air in the ERA-Interim

    Science.gov (United States)

    Diallo, M.; Legras, B.; Chedin, A.

    2012-07-01

    The age of stratospheric air is calculated over 22 yr of the ERA-Interim reanalysis using an off-line Lagrangian transport model and heating rates. At low and mid-latitudes, the mean age of air is in good agreement with observed ages from aircraft flights, high altitude balloons and satellite observations of CO2 and SF6. The mid-latitude age spectrum in the lower stratosphere exhibits a long tail with a peak at 0.5 yr, which is maximum at the end of the winter, and a secondary flat maximum between 4 and 5 yr due to the combination of fast and slow branches of the Brewer-Dobson circulation and the reinforced barrier effect of the jet. At higher altitudes, the age spectrum exhibits the footprint of the annual modulation of the deep Brewer-Dobson circulation. The variability of the mean age is analysed through a decomposition in terms of annual cycle, QBO, ENSO and trend. The annual modulation is the dominating signal in the lower stratosphere and in the tropical pipe with amplitude up to one year. The phase of the oscillation is opposite in both hemisphere beyond 20° and is also reversed below and above 25 km with maximun arising in mid-March in the Northern Hemisphere and in mid-September in the Southern Hemisphere. The tropical pipe signal is in phase with the lower southern stratosphere and the mid northern stratosphere. The maximum amplitude of the QBO modulation is of about 0.5 yr and is mostly concentrated within the tropics between 25 and 35 km. It lags the QBO wind at 30 hPa by about 8 months. The ENSO signal is small and limited to the lower northen stratosphere. The trend is significant and negative, of the order of -0.3 to -0.5 yr dec-1, within the lower stratosphere in the Southern Hemisphere and under 40° N in the Northern Hemisphere below 25 km. It is positive (of the order of 0.3 yr dec-1) in the mid stratosphere but there is no region of consistent significance. This suggests that the shallow and deep Brewer-Dobson circulations may evolve in

  2. Does the radiation from the interim storage in Gorleben affect the sex ratio of newborn children?; Beeinflusst die Strahlung aus dem Zwischenlager in Gorleben das Geschlechterverhaeltnis von Neugeborenen?

    Energy Technology Data Exchange (ETDEWEB)

    Engelmann, H.W.; Schulze, H.; Wede, S. [GNS Gesellschaft fuer Nuklear-Service mbH, Gorleben (Germany); Mueller, S. [Studsvik GmbH, Pforzheim (Germany)

    2015-07-01

    In the professional world but especially in public, the question is discussed whether ionizing radiation from nuclear facilities has a significant impact on the secondary sex ratio of newborn children in the vicinity of the plants. This issue is of exceptional importance in the region around Gorleben, where the opposition to nuclear facilities and activities for decades is particularly strong. At the site borders of the interim storage facility (TBL-G) of GNS the effective individual dose is about 0.2 mSv per year, mainly caused by neutron irradiation from 108 casks with high-level radioactive waste from reprocessing. In the surrounding villages there is no radiation measurable. Statistical studies allegedly have shown evidence that in some villages in the area and during certain periods, proportionately fewer girls were born in comparison to the average for the Federal Republic of Germany. Based on these purely statistical results henceforward was also alleged that neutron-induced secondary effects such as activation or secondary gamma radiation would be responsible for it. Monte Carlo calculations and special measurements yielded values of the dose at the plant border for activation products less than E-04 mSv/a and for secondary gamma radiation of about E-03 mSv/a. These results indicate that the ionizing radiation from the Gorleben interim storage facility cannot be held accountable for shifts of the secondary sex ratio.

  3. T Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring FY09 Report

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Z. F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

    2010-01-01

    DOE’s Office of River Protection constructed a temporary surface barrier over a portion of the T Tank Farm as part of the T Farm Interim Surface Barrier Demonstration Project. As part of the demonstration effort, vadose zone moisture is being monitored to assess the effectiveness of the barrier at reducing soil moisture. A solar-powered system was installed to continuously monitor soil water conditions at four locations (i.e., instrument Nests A, B, C, and D) beneath the barrier and outside the barrier footprint as well as site meteorological conditions. Nest A is placed in the area outside the barrier footprint and serves as a control, providing subsurface conditions outside the influence of the surface barrier. Nest B provides subsurface measurements to assess surface-barrier edge effects. Nests C and D are used to assess changes in soil-moisture conditions beneath the interim surface barrier. Each instrument nest is composed of a capacitance probe (CP) with multiple sensors, multiple heat-dissipation units (HDUs), and a neutron probe (NP) access tube. The monitoring results in FY09 are summarized below. The solar panels functioned normally and could provide sufficient power to the instruments. The CP in Nest C after September 20, 2009, was not functional. The CP sensors in Nest B after July 13 and the 0.9-m CP sensor in Nest D before June 10 gave noisy data. Other CPs were functional normally. All the HDUs were functional normally but some pressure-head values measured by HDUs were greater than the upper measurement-limit. The higher-than-upper-limit values might be due to the very wet soil condition and/or measurement error but do not imply the malfunction of the sensors. Similar to FY07 and FY08, in FY09, the soil under natural conditions (Nest A) was generally recharged during the winter period (October-March) and discharged during the summer period (April-September). Soil water conditions above about 1.5-m to 2-m depth from all three types of measurements

  4. Observations of precipitable water vapour over complex topography of Ethiopia from ground-based GPS, FTIR, radiosonde and ERA-Interim reanalysis

    Science.gov (United States)

    Mengistu Tsidu, G.; Blumenstock, T.; Hase, F.

    2015-08-01

    Water vapour is one of the most important greenhouse gases. Long-term changes in the amount of water vapour in the atmosphere need to be monitored not only for its direct role as a greenhouse gas but also because of its role in amplifying other feedbacks such as clouds and albedo. In recent decades, monitoring of water vapour on a regular and continuous basis has become possible as a result of the steady increase in the number of deployed global positioning satellite (GPS) ground-based receivers. However, the Horn of Africa remained a data-void region in this regard until recently, when some GPS ground-receiver stations were deployed to monitor tectonic movements in the Great Rift Valley. This study seizes this opportunity and the installation of a Fourier transform infrared spectrometer (FTIR) at Addis Ababa to assess the quality and comparability of precipitable water vapour (PWV) from GPS, FTIR, radiosonde and interim ECMWF Re-Analysis (ERA-Interim) over Ethiopia. The PWV from the three instruments and the reanalysis show good correlation, with correlation coefficients in the range from 0.83 to 0.92. On average, GPS shows the highest PWV followed by FTIR and radiosonde observations. ERA-Interim is higher than all measurements with a bias of 4.6 mm compared to GPS. The intercomparison between GPS and ERA-Interim was extended to seven other GPS stations in the country. Only four out of eight GPS stations included simultaneous surface pressure observations. Uncertainty in the model surface pressure of 1 hPa can cause up to 0.35 mm error in GPS PWV. The gain obtained from using observed surface pressure in terms of reducing bias and strengthening correlation is significant but shows some variations among the GPS sites. The comparison between GPS and ERA-Interim PWV over the seven other GPS stations shows differences in the magnitude and sign of bias of ERA-Interim with respect to GPS PWV from station to station. This feature is also prevalent in diurnal and seasonal

  5. Unpublished Interim Digital Geologic Map of Hot Springs National Park and Vicinity, Arkansas (NPS, GRD, GRI, HOSP, HOSP digital map) adapted from the interim Arkansas Geological Survey DGM-HSR-003 by Johnson and Hanson (2011)

    Data.gov (United States)

    National Park Service, Department of the Interior — The Unpublished Interim Digital Geologic Map of Hot Springs National Park and Vicinity, Arkansas is composed of GIS data layers complete with ArcMap 9.3 layer...

  6. 78 FR 59726 - Interim Final Appendix D of OMB Circular No. A-123, “Management's Responsibility for Internal...

    Science.gov (United States)

    2013-09-27

    ... Internal Control,'' defines management's responsibility for internal control in Federal agencies. OMB... From the Federal Register Online via the Government Publishing Office OFFICE OF MANAGEMENT AND BUDGET Interim Final Appendix D of OMB Circular No. A-123, ``Management's Responsibility for...

  7. 77 FR 24857 - Interim Final Determination To Stay and Defer Sanctions, San Joaquin Valley Unified Air Pollution...

    Science.gov (United States)

    2012-04-26

    ... Air Pollution Control District AGENCY: Environmental Protection Agency (EPA). ACTION: Interim final... Joaquin Valley Unified Air Pollution Control District (SJVUAPCD) portion of the California State... Part 52 Environmental protection, Air pollution control, Intergovernmental regulations,...

  8. Dedicated-site, interim storage of high-level nuclear waste as part of the management system.

    Science.gov (United States)

    Zen, E A

    1980-11-01

    Dedicated-site interim storage of high-level reprocessed nuclear waste and of spent fuel rods is proposed as a long-term integral part of the systems approach of the national nuclear waste isolation program. Separation of interim sites for retrievable storage from permanent-disposal repositories should enhance ensurance of the performance of the latter; maintenance of retrievability at separate sites also has many advantages in both safety and possible use of waste as resources. Interim storage sites probably will not be needed beyond about 100 years from now, so the institutional and technical considerations involved in their choice should be much less stringent than those for the selection of permanent sites. Development of interim sites must be concurrent with unabated effort to identify and to develop permanent repositories.

  9. Detailed Rules for the Implementing the Interim Regulations of the People's Republic of China on Value-added Tax

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    @@ Article 1 The Detailed Rules are formulated according to the provisions of the Interim Regulations of the People's Republic of Chi-na on Value-added Tax (hereinafter referred to as the Regulations).

  10. John Burton named interim director for distance learning and summer sessions; Learning Technologies formally partners with undergraduate education

    OpenAIRE

    Owczarski, Mark

    2010-01-01

    John K. Burton, professor of learning sciences and technology in the School of Education in the College of Liberal Arts and Human Sciences at Virginia Tech, has been named the university's interim director for distance learning and summer sessions.

  11. Caustic-Side Solvent-Extraction Modeling for Hanford Interim Pretreatment System

    Energy Technology Data Exchange (ETDEWEB)

    Moyer, B.A.; Birdwell, J.F.; Delmau, L. H.; McFarlane, J.

    2008-06-01

    The purpose of this work is to examine the applicability of the Caustic-Side Solvent Extraction (CSSX) process for the removal of cesium from Hanford tank-waste supernatant solutions in support of the Hanford Interim Pretreatment System (IPS). The Hanford waste types are more challenging than those at the Savannah River Site (SRS) in that they contain significantly higher levels of potassium, the chief competing ion in the extraction of cesium. It was confirmed by use of the CSSX model that the higher levels of potassium depress the cesium distribution ratio (DCs), as validated by measurement of DCs values for four of eight specified Hanford waste-simulant compositions. The model predictions were good to an apparent standard error of ±11%. It is concluded from batch distribution experiments, physical-property measurements, equilibrium modeling, flowsheet calculations, and contactor sizing that the CSSX process as currently employed for cesium removal from alkaline salt waste at the SRS is capable of treating similar Hanford tank feeds. For the most challenging waste composition, 41 stages would be required to provide a cesium decontamination factor (DF) of 5000 and a concentration factor (CF) of 5. Commercial contacting equipment with rotor diameters of 10 in. for extraction and 5 in. for stripping should have the capacity to meet throughput requirements, but testing will be required to confirm that the needed efficiency and hydraulic performance are actually obtainable. Markedly improved flowsheet performance was calculated for a new solvent formulation employing the more soluble cesium extractant BEHBCalixC6 used with alternative scrub and strip solutions, respectively 0.1 M NaOH and 10 mM boric acid. The improved system can meet minimum requirements (DF = 5000 and CF = 5) with 17 stages or more ambitious goals (DF = 40,000 and CF = 15) with 19 stages. Potential benefits of further research and development are identified that would lead to reduced costs, greater

  12. Caustic-Side Solvent-Extraction Modeling for Hanford Interim Pretreatment System

    International Nuclear Information System (INIS)

    The purpose of this work is to examine the applicability of the Caustic-Side Solvent Extraction (CSSX) process for the removal of cesium from Hanford tank-waste supernatant solutions in support of the Hanford Interim Pretreatment System (IPS). The Hanford waste types are more challenging than those at the Savannah River Site (SRS) in that they contain significantly higher levels of potassium, the chief competing ion in the extraction of cesium. It was confirmed by use of the CSSX model that the higher levels of potassium depress the cesium distribution ratio (DCs), as validated by measurement of DCs values for four of eight specified Hanford waste-simulant compositions. The model predictions were good to an apparent standard error of ±11%. It is concluded from batch distribution experiments, physical-property measurements, equilibrium modeling, flowsheet calculations, and contactor sizing that the CSSX process as currently employed for cesium removal from alkaline salt waste at the SRS is capable of treating similar Hanford tank feeds. For the most challenging waste composition, 41 stages would be required to provide a cesium decontamination factor (DF) of 5000 and a concentration factor (CF) of 5. Commercial contacting equipment with rotor diameters of 10 in. for extraction and 5 in. for stripping should have the capacity to meet throughput requirements, but testing will be required to confirm that the needed efficiency and hydraulic performance are actually obtainable. Markedly improved flowsheet performance was calculated for a new solvent formulation employing the more soluble cesium extractant BEHBCalixC6 used with alternative scrub and strip solutions, respectively 0.1 M NaOH and 10 mM boric acid. The improved system can meet minimum requirements (DF = 5000 and CF = 5) with 17 stages or more ambitious goals (DF = 40,000 and CF = 15) with 19 stages. Potential benefits of further research and development are identified that would lead to reduced costs, greater

  13. 78 FR 78819 - National Conference on Weights and Measures 99th Interim Meeting

    Science.gov (United States)

    2013-12-27

    ... receipts provide important information for consumers (e.g., seller identity, date, product identity, and... found their way into direct sale applications, some manufacturers are now requesting a change to the... product identity adjacent to stationary devices in retail outlets. In addition, the...

  14. 78 FR 290 - National Conference on Weights and Measures 98th Interim Meeting

    Science.gov (United States)

    2013-01-03

    .... Item 232-6: Packaged Printer Ink and Toner Cartridges This proposal was originally intended to... 2012 NCWM Annual Meeting a newly formed Printer Ink and Toner Cartridge Gravimetric Package Testing... Testing of Printer Ink and Toner Cartridges for more information. Retail Sale of Electricity for...

  15. 76 FR 540 - National Conference on Weights and Measures 2011 Interim Meeting

    Science.gov (United States)

    2011-01-05

    ... Method of Sale Regulation for Packages of Printer Ink and Toner Cartridges--The L&R Committee will... products so value comparisons can be made. Special Meeting Announcements The Task Group on Printer Ink...

  16. Spent fuel test-climax: technical measurements interim report, FY 1980

    International Nuclear Information System (INIS)

    The Spent Fuel Test--Climax (SFT-C), a test of the retrievable geologic storage of spent fuel assemblies from an operating commercial power reactor, is under way at the Nevada Test Site of the US Department of Energy. Although the main thrust of the project is a demonstration of the feasibility of packaging, handling, storing, and retrieving the highly radioactive fuel assemblies, over 800 data channels have been installed to monitor the response of the rock to the heat and radiation produced by the fuel assemblies and to distinguish in that response the effect due to heat alone. Temperatures in the test array are tracking well with thermal modeling calculations performed before the test was started. The fuel assemblies have been in place since May 1980. The canisters have passed through skin temperature maxima of about 1450C and are currently declining in temperature. Evidence is emerging that the thermomechanical response of the rock surrounding the SFT-C is strongly affected by fractures and other discontinuities inthe rock. Most of the effort to date has been in project construction, design, and installation of the instrumentation. Although the data are available in raw form for verification purposes, the data are not as yet in a suitable form for detailed analyses. Work continues on the data management aspects of the project and in continued monitoring of the test

  17. 76 FR 81477 - National Conference on Weights and Measures 97th Interim Meeting

    Science.gov (United States)

    2011-12-28

    ... value of livestock, meat, and poultry. The impact of calibration, machine, and formula errors is unknown... vehicles. The first proposal would add the most recent version of SAE International's Standard...

  18. A Comparative Study of ERA-40 and ERA-Interim Reanalyses: Uncertainties in Estimating Wave Forcing in Northern Winter

    Science.gov (United States)

    Lu, Hua; Bracegirdle, Thomas; Phillips, Tony Tony; Turner, John

    2014-05-01

    The eddy heat flux is a fundamental quantity for understanding stratospheric variability. At 100 hPa it is a direct measure of the wave activity that propagates from the troposphere into the stratosphere. In the Northern winter it is dominated by the contribution from stationary waves and forms a significant component of the vertical Eliassen-Palm (E-P) flux. Based on the transformed Eulerian mean (TEM) equation, the divergence of the E-P flux acts as a body force on the mean flow and causes temperature variations in the stratosphere. Thus the accuracy and homogeneity of the heat flux and the associated E-P flux divergence are vital for studying stratospheric dynamics. The objective of this study is to detect possible errors in these wave forcing parameters estimated from the widely used ERA-40 and ERA-Interim reanalysis data sets produced by the European Centre for Medium-range Weather Forecasts (ECMWF). We focus on the December to February mean, during which the magnitude and variation of the wave forcing are largest. We examine two types of discrepancies. The first is based on the simple composite difference between the two data sets across their common period of the 1979/1980-2001/2002 winters. The second is to detect a discontinuity, or a sudden change of mean in each data set. We find four regions where significant discrepancies of zonal mean E-P flux divergence exist. They are: 1) polarward of 20° N in the upper stratosphere where the discrepancies are found to be associated with both the eddy heat flux v'T'and the eddy momentum flux u'v'; 2) poleward of 45° N in the middle to lower stratosphere where the discrepancies are primarily associated with the eddy heat flux v'T'; 3) the tropical to subtropical upper troposphere where the discrepancies are mainly caused by the difference in vertical eddy flux w'u'; and 4) the middle latitude upper troposphere where a large cancellation of error is detected between the vertical eddy flux w'u' and eddy heat flux v

  19. South Philadelphia Passive Sampler and Sensor Study - Interim Report

    Science.gov (United States)

    Starting in the June 2013, the U.S. EPA and the City of Philadelphia Air Measurements Services (AMS) began a collaborative research project to investigate how sensor-based, stand-alone air measurements (SAMs) and passive samplers (PSs) can help improve information on air pollutan...

  20. South Philadelphia Passive Sampler and Sensor Study: Interim Report

    Science.gov (United States)

    Starting in June 2013, the United States Environmental Protection Agency (U.S. EPA) and the City of Philadelphia Air Measurements Services began collaborative research on the use of passive samplers (PSs) and stand-alone air measurement (SAM) systems to improve information on the...

  1. Functions and requirements document for interim store solidified high-level and transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    Smith-Fewell, M.A., Westinghouse Hanford

    1996-05-17

    The functions, requirements, interfaces, and architectures contained within the Functions and Requirements (F{ampersand}R) Document are based on the information currently contained within the TWRS Functions and Requirements database. The database also documents the set of technically defensible functions and requirements associated with the solidified waste interim storage mission.The F{ampersand}R Document provides a snapshot in time of the technical baseline for the project. The F{ampersand}R document is the product of functional analysis, requirements allocation and architectural structure definition. The technical baseline described in this document is traceable to the TWRS function 4.2.4.1, Interim Store Solidified Waste, and its related requirements, architecture, and interfaces.

  2. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    Energy Technology Data Exchange (ETDEWEB)

    Pickett, W.W.

    1997-12-30

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

  3. Criticality safety evaluation for long term storage of FFTF fuel in interim storage casks

    International Nuclear Information System (INIS)

    It has been postulated that a degradation phenomenon, referred to as ''hot cell rot'', may affect irradiated FFTF mixed plutonium-uranium oxide (MOX) fuel during dry interim storage. ''Hot cell rot'' refers to a variety of phenomena that degrade fuel pin cladding during exposure to air and inert gas environments. It is thought to be a form of caustic stress corrosion cracking or environmentally assisted cracking. Here, a criticality safety analysis was performed to address the effect of the ''hot cell rot'' phenomenon on the long term storage of irradiated FFTF fuel in core component containers. The results show that seven FFTF fuel assemblies or six Ident-69 pin containers stored in core component containers within interim storage casks will remain safely subcritical

  4. Interim storage for spent fuel elements. Bavarian Higher Administrative Court, judgement of February 7, 1985

    International Nuclear Information System (INIS)

    Spent fuel, which can be reprocessed under the conditions of sec. 9 a (1) Atomic Energy Act, is not classified as radioactive waste but as radioactive residues. Their interim storage is not subject to the provisions for waste disposal of sec. 9 a et seq. Atomic Energy Act, but to those of sec. 5 et seq. Atomic Energy Act. The construction and operation of a compact fuel storage in a cooling pond for the purpose of interim storage of irradiated fuel is subject to a licence pursuant to sec. 7 (1) Atomic Energy Act. External effects on a compact storage due to an incident 'plane crash' are to be attributed to the scope of residual risk because of the special precautions already considered within the design criteria and because of the comparatively favourable site of the plant Isar 1 at Ohu. (orig./HSCH)

  5. Safety features of proposed concepts for spent fuel dry interim storage

    International Nuclear Information System (INIS)

    Whichever solution is selected for the back-end of the fuel cycle, increasing quantities of spent fuel have often to be stored interim for rather long periods of time. Public acceptance of the corresponding storage facilities becomes more and more an important concern for all involved utilities in various countries. The fact that several governments have already issued sets of storage criteria which show significant differences with each other constitutes a weakness for all of them in front of their own population which no longer knows whom to believe. Therefore the need of an international consensus on basic rules and criteria for the safe interim storage of spent fuel has now become really urgent. The paper gives a brief view on this problem. (author)

  6. Dynamics of Flexible Rotor Systems with an Interim Mass Unbalanced Disk Using a Spectral Element Model

    Directory of Open Access Journals (Sweden)

    Sangkyu Choi

    2014-01-01

    Full Text Available A frequency domain spectral element model is developed for a rotor system that consists of two spinning shafts and an interim disk or blade system. In this study, the shafts are represented by spinning Timoshenko beam models, and the interim disk system is represented by a uniform thick rigid disk with an unbalanced mass. In our derivation of the governing equations of motion of the disk system, the disk is considered to be wobbling about the geometric center of the disk at which the spinning shafts are attached. The high accuracy of the proposed spectral element model is evaluated by comparison with the natural frequencies obtained using the conventional finite element method (FEM. The spectral element model is then used to investigate the effects of the unbalanced mass on the natural frequencies and dynamic responses of an example rotor system.

  7. The Time Needed to Implement the Blue Ribbon Commission Recommendation on Interim Storage - 13124

    International Nuclear Information System (INIS)

    The report of the Blue Ribbon Commission on America's Nuclear Future [1] makes a number of important recommendations to be considered if Congress elects to redirect U.S. high-level radioactive waste disposal policy. Setting aside for the purposes of this discussion any issues related to political forces leading to stopping progress on the Yucca Mountain project and driving the creation of the Commission, an important recommendation of the Commission was to institute prompt efforts to develop one or more consolidated storage facilities. The Blue Ribbon Commission noted that this recommended strategy for future storage and disposal facilities and operations should be implemented regardless of what happens with Yucca Mountain. It is too easy, however, to focus on interim storage as an alternative to geologic disposal. The Blue Ribbon Commission report does not go far enough in addressing the magnitude of the contentious problems associated with reopening the issues of relative authorities of the states and federal government with which Congress wrestled in crafting the Nuclear Waste Policy Act [2]. The Blue Ribbon Commission recommendation for prompt adoption of an interim storage program does not appear to be fully informed about the actions that must be taken, the relative cost of the effort, or the realistic time line that would be involved. In essence, the recommendation leaves to others the details of the systems engineering analyses needed to understand the nature and details of all the operations required to reach an operational interim storage facility without derailing forever the true end goal of geologic disposal. The material presented identifies a number of impediments that must be overcome before the country could develop a centralized federal interim storage facility. In summary, and in the order presented, they are: 1. Change the law, HJR 87, PL 107-200, designating Yucca Mountain for the development of a repository. 2. Bring new nuclear waste

  8. FedEx Gasoline Hybrid Electric Delivery Truck Evaluation: 6-Month Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Barnitt, R.

    2010-05-01

    This interim report presents partial (six months) results for a technology evaluation of gasoline hybrid electric parcel delivery trucks operated by FedEx in and around Los Angeles, CA. A 12 month in-use technology evaluation comparing in-use fuel economy and maintenance costs of GHEVs and comparative diesel parcel delivery trucks was started in April 2009. Comparison data was collected and analyzed for in-use fuel economy and fuel costs, maintenance costs, total operating costs, and vehicle uptime. In addition, this interim report presents results of parcel delivery drive cycle collection and analysis activities as well as emissions and fuel economy results of chassis dynamometer testing of a gHEV and a comparative diesel truck at the National Renewable Energy Laboratory's (NREL) ReFUEL laboratory. A final report will be issued when 12 months of in-use data have been collected and analyzed.

  9. Financial compensation for municipalities hosting interim or final disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    Brazilian Law No. 10308 issued November 20, 2001, establishes in its 34th article that 'those municipalities hosting interim or final disposal facilities for radioactive waste are eligible to receive a monthly payment as compensation'. The values of due payments depend on parameters such as volume of wastes and activity and half-lives of the radionuclides. The method to calculating those values was established by the National Commission on Nuclear Energy, the Brazilian regulatory authority, by Resolution No. 10, issued in the August 18, 2003. In this paper we report the application of that method to a low- and intermediate-level radioactive waste interim storage facility at the Nuclear Energy Research Institute. (author)

  10. 400-MWe Consolidated Nuclear Steam System (CNSS). 1200-MWt Phase 2A interim studies. [PWR

    Energy Technology Data Exchange (ETDEWEB)

    1978-09-01

    The Phase 2A interim studies of the Consolidated Nuclear Steam System (CNSS) consisted of a number of separate task studies addressing the design concepts developed during the Phase 1 study reported in BAW--1445. The purpose of the interim studies was to better establish overall concept feasibility from both a hardware and economic standpoint, to make modification and additions to the design where appropriate, and to understand and reduce the technical risks in critical areas of the design. The work on these task studies included input from Barberton, Mt. Vernon, and the Alliance Research Center as well as United Engineers and Constructors (UE and C). The UE and C work was carried out under a separate DOE contract.

  11. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    International Nuclear Information System (INIS)

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations

  12. 200 Area stack contamination. Interim report, August 2, 1948--October 11, 1948

    Energy Technology Data Exchange (ETDEWEB)

    Lapple, C.E.

    1948-10-11

    In connection with the problem of eliminating contamination of the atmosphere by the exhaust from the 221 Building ventilation air stacks, sand filters were previously recommended. Construction of a sand filter in West Area is about completed and construction of a filter in East Area is well underway. This report summarizes the status, technical findings, and comments and suggestions since the writer`s last Interim Report, dated August 6, 1948, was issued.

  13. Evaluation of ERA-interim and MERRA Cloudiness in the Southern Oceans

    Science.gov (United States)

    Naud, Catherine M.; Booth, James F.; Del Genio, Anthony D.

    2014-01-01

    The Southern Ocean cloud cover modeled by the Interim ECMWF Re-Analysis (ERA-Interim) and Modern- Era Retrospective Analysis for Research and Applications (MERRA) reanalyses are compared against Moderate Resolution Imaging Spectroradiometer (MODIS) and Multiangle Imaging Spectroradiometer (MISR) observations. ERA-Interim monthly mean cloud amounts match the observations within 5%, while MERRA significantly underestimates the cloud amount. For a compositing analysis of clouds in warm season extratropical cyclones, both reanalyses show a low bias in cloud cover. They display a larger bias to the west of the cyclones in the region of subsidence behind the cold fronts. This low bias is larger for MERRA than for ERA-Interim. Both MODIS and MISR retrievals indicate that the clouds in this sector are at a low altitude, often composed of liquid, and of a broken nature. The combined CloudSat-Cloud-Aerosol Lidar and Infrared Pathfinder Satellite Observations (CALIPSO) cloud profiles confirm these passive observations, but they also reveal that low-level clouds in other parts of the cyclones are also not properly represented in the reanalyses. The two reanalyses are in fairly good agreement for the dynamic and thermodynamic characteristics of the cyclones, suggesting that the cloud, convection, or boundary layer schemes are the problem instead. An examination of the lower-tropospheric stability distribution in the cyclones from both reanalyses suggests that the parameterization of shallow cumulus clouds may contribute in a large part to the problem. However, the differences in the cloud schemes and in particular in the precipitation processes, which may also contribute, cannot be excluded.

  14. Comprehensive Medical Management of Rosacea: An Interim Study Report and Literature Review

    OpenAIRE

    Del Rosso, James Q.; Baum, Eric W.

    2008-01-01

    Rosacea is a common inflammatory facial dermatosis seen in adults that exhibits considerable variety in clinical presentation. Multiple medical therapeutic options are available including topical and oral treatments. Optimal medical management of rosacea includes assessment of subtype and disease severity and use of appropriate skin care to reduce epidermal barrier dysfunction. This article provides an overall discussion of the medical management of rosacea and reviews interim results from a ...

  15. Record of Decision Colorado River Interim Surplus Guidelines Final Environmental Impact Statement

    OpenAIRE

    Secretary of the Department of the Interior

    2001-01-01

    This document constitutes the Record of Decision (ROD) of the Department of the Interior, regarding the preferred alternative for Colorado River Interim Surplus Guidelines (Guidelines). The Secretary of the Interior (Secretary) is vested with the responsibility of managing the mainstream waters of the lower Colorado River pursuant to federal law. This responsibility is carried out consistent with applicable federal law. Reclamation, as the agency that is designated to act on the Secretary’s b...

  16. Interim sanitary landfill groundwater monitoring report. First and second quarters 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site. These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 and as part of the SRS Groundwater Monitoring Program. This document contains the analytical groundwater sampling data for these eight wells for the first two quarters of 1996.

  17. An Evaluation of the Individual Training Account/Eligible Training Provider Demonstration. Final Interim Report.

    OpenAIRE

    Ronald D'Amico; Alexandria Martinez; Jeffrey Salzman; Robin Wagner

    2001-01-01

    Presents interim findings from an evaluation of 13 grantees' efforts to deliver training services through the use of Individual Training Accounts, which participants can use to procure the training of their choice, as long as it is state-approved. Describes policies and practices at about the midpoint of the grant period. Discusses how eligible programs were selected and reviews the information available to participants for use in making training choices.

  18. Report on interim storage of spent nuclear fuel. Midwestern high-level radioactive waste transportation project

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    The report on interim storage of spent nuclear fuel discusses the technical, regulatory, and economic aspects of spent-fuel storage at nuclear reactors. The report is intended to provide legislators state officials and citizens in the Midwest with information on spent-fuel inventories, current and projected additional storage requirements, licensing, storage technologies, and actions taken by various utilities in the Midwest to augment their capacity to store spent nuclear fuel on site.

  19. Development of a novel interim bulk fuel storage facility for the PBMR / W.F. Fuls

    OpenAIRE

    Fuls, Wilhelm Franz

    2004-01-01

    The PBMR is the first High Temperature Reactor being designed for commercial power generation in South Africa. It makes use of spherical fuel elements, containing coated uranium oxide particles encapsulated in a graphite matrix. The spent fuel generated from the reactor is stored in a storage system before final disposal. Such storage systems are called interim storage facilities, and normally make use of small transportable containers. The PBMR design makes use of bulk storage containers...

  20. Solid rocket technology advancement for Space Tug and IUS applications. [Interim Upper Stage

    Science.gov (United States)

    Ascher, W.; Bailey, R. L.; Behm, J. W.; Gin, W.

    1975-01-01

    Two-burn restartable solid propellant rocket motors for the kick stage (auxiliary stage) of the Shuttle Tug, or Interim Upper Stage, are described, with details on features and test results of the ignition and quench (thrust termination) systems and procedures, fabrication of propellant and insulation, explosion hazards of propellants, and comparative data on present and future motor design. These rocket motor systems are designed for upper stage augmentation of launch vehicles and possible service in Shuttle-launched outer planet spacecraft.

  1. Interim Storage of Spent Nuclear Fuel before Final Disposal in Germany - Regulator's view

    International Nuclear Information System (INIS)

    For spent nuclear fuel management in Germany the concept of dry interim storage in dual purpose casks before direct disposal is applied. The Federal Office for Radiation Protection (BfS) is the competent authority for licensing of interim storage facilities. The competent authority for surveillance of operation is the responsible authority of the respective federal state (Land). Currently operation licenses for storage facilities have been granted for a storage time of 40 years and are based on safety demonstrations for all safety issues as safe enclosure, shielding, sub-criticality and decay heat removal under consideration of operation conditions. In addition, transportability of the casks for the whole storage period has to be provided. Due to current delay in site selection and exploration of a disposal site, an extension of the storage time beyond 40 years could be needed. This will cause appropriate actions by the licensee and the competent authorities as well. A brief description of the regulatory base of licensing and surveillance of interim storage is given from the regulators view. Furthermore the current planning for final disposal of spent nuclear fuel and high level waste and its interconnections between storage and disposal concepts are shortly explained. Finally the relevant aspects for licensing of extended storage time beyond 40 years will be discussed. Current activities on this issue, which have been initiated by the Federal Government, will be addressed. On the regulatory side a review and amendment of the safety guideline for interim storage of spent fuel has been performed and the procedure of periodic safety review is being implemented. A guideline for implementing an ageing management programme is available in a draft version. Regarding safety of long term storage a study focussing on the identification and evaluation of long term effects as well as gaps of knowledge has been finished in 2010. A continuation and update is currently underway

  2. Interim action record of decision remedial alternative selection: TNX area groundwater operable unit

    International Nuclear Information System (INIS)

    This document presents the selected interim remedial action for the TNX Area Groundwater Operable Unit at the Savannah River Site (SRS), which was developed in accordance with CERCLA of 1980, as amended by the Superfund Amendments and Reauthorization Act (SARA) of 1986, and to the extent practicable, the National Oil and Hazardous Substances Pollution contingency Plan (NCP). This decision is based on the Administrative Record File for this specific CERCLA unit

  3. Operations and Maintenance Concept Plan for the Immobilized High-Level Waste (IHLW) Interim Storage Facility

    International Nuclear Information System (INIS)

    This OandM Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design

  4. Seismic Safety Margins Research Program. Phase I. Interim definition of terms

    International Nuclear Information System (INIS)

    This report documents interim definitions of terms in the Seismic Safety Margins Research Program (SSMRP). Intent is to establish a common-based terminology integral to the probabilistic methods that predict more realistically the behavior of nuclear power plants during an earthquake. These definitions are a response to a request by the Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards at its meeting held November 15-16, 1979

  5. Detailed Rules for Implementing the Interim Regulations of the People's Republic of China on Business Tax

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    @@ Article 1 The Detailed Rules are formulated in accordance with the Interim Regulations of the People's Republic of China on Busi-ness Tax (hereinafter referred to as the Regulations). Article 2 "Services" as mentioned in Article 1 of the Regulations refers to services within the scope of taxable items in the trans-portation, construction, finance and insurance, posts and tele-communications, culture and sports, entertainment and service industries (hereinafter referred to as taxable services).

  6. The British Society of Gastroenterology early gastric cancer/dysplasia survey: an interim report.

    OpenAIRE

    De Dombal, F T; Price, A. B.; Thompson, H; Williams, G. T.; Morgan, A G; Softley, A; Clamp, S E; Unwin, B J

    1990-01-01

    This presentation describes interim findings in a series of 319 patients referred from 41 hospitals on the basis of histopathological findings of 'early gastric cancer', 'dysplasia', or 'worrying mucosal appearances'. Data were recorded using a predefined proforma, and histopathological material circulated amongst a 'panel' of three further pathologists. After this process, 132 patients were classified as having early gastric cancer and 63 as dysplasia. There was good agreement between pathol...

  7. Democratic Republic of the Congo; Interim Poverty Reduction Strategy Paper Preparation Status Report

    OpenAIRE

    International Monetary Fund

    2004-01-01

    In this paper, the implementation of the activities under the interim poverty reduction strategy and progress toward the elaboration of poverty reduction strategy are described. Institutional framework is strengthened by the creation of the inter-ministerial committee on the implementation of the National Strategy for Poverty Reduction. The goal is to identify priorities and strategies at the community level, and their capacity to operationalize sectoral and thematic poverty reduction strateg...

  8. Wide-Field InfraRed Survey Telescope (WFIRST) Interim Report

    CERN Document Server

    Green, James; Baltay, Charles; Bean, Rachel; Bennett, David; Brown, Robert; Conselice, Christopher; Donahue, Megan; Gaudi, Scott; Lauer, Tod; Perlmutter, Saul; Rauscher, Bernard; Rhodes, Jason; Roellig, Thomas; Stern, Daniel; Sumi, Takahiro; Tanner, Angelle; Wang, Yun; Wright, Edward; Gehrels, Neil; Sambruna, Rita; Traub, Wesley

    2011-01-01

    In December 2010, NASA created a Science Definition Team (SDT) for WFIRST, the Wide Field Infra-Red Survey Telescope, recommended by the Astro 2010 Decadal Survey as the highest priority for a large space mission. The SDT was chartered to work with the WFIRST Project Office at GSFC and the Program Office at JPL to produce a Design Reference Mission (DRM) for WFIRST. This paper describes an Interim DRM. The DRM will be completed in 2012.

  9. The role of interim storage facilities in the nuclear waste management policy of Germany

    International Nuclear Information System (INIS)

    The article discusses the role of interim storage of spent fuel elements in the current nuclear waste management policy in Germany, and possible demand for additional interim storage facilities in the future, as a consequence of the shift in the radioactive waste disposal concept and the nuclear power opt-out policy of the Federal Government. Success or failure of the consensus on the nuclear power phase-out strategy, agreed between the Federal Government and the nuclear power industry on 14 June 2000, hinges not only but essentially on the availability of sufficient interim storage facilities for spent fuel elements accrued over the negotiated remaining operating periods of nuclear power plants. The NPP operators say the present radioactive waste management concept has to be put on a different basis and needs amending in response to the change in energy policy. For the electric utilities, the crucial test is whether the Federal Government will be able to fulfill their promise made during the consensus negotiations, namely that there will be no premature shutdowns of nuclear power plants because of a bottleneck in spent fuel storage capacity. (orig./CB)

  10. Safety of interim storage solutions of used nuclear fuel during extended term

    International Nuclear Information System (INIS)

    In 2013, the total amount of stored used nuclear fuel (UNF) in the world will reach 225,000 T HM. The UNF inventory in wet storage will take up over 80% of the available total spent fuel pool (SFP) capacity. Interim storage solutions are needed. They give flexibility to the nuclear operators and ensure that nuclear reactors continue to operate. However, we need to keep in mind that they are also an easy way to differ final decision and implementation of a UNF management approach (recycling or final disposal). In term of public perception, they can have a negative impact overtime as it may appear that nuclear industry may have significant issues to resolve. In countries lacking an integrated UNF management approach, the UNF are being discharged from the SFPs to interim storage (mostly to dry storage) at the same rate as UNF is being discharged from reactors, as the SFPs at the reactor sites are becoming full. This is now the case in USA, Taiwan, Switzerland, Spain, South Africa and Germany. For interim storage, AREVA has developed different solutions in order to allow the continued operation of reactors while meeting the current requirements of Safety Authorities: -) Dry storage canisters on pads, -) Dual-purpose casks (dry storage and transportation), -) Vault dry storage, and -) Centralized pool storage

  11. Lessons learned from the Siting Process of an Interim Storage Facility in Spain - 12024

    Energy Technology Data Exchange (ETDEWEB)

    Lamolla, Meritxell Martell [MERIENCE Strategic Thinking, 08734 Olerdola, Barcelona (Spain)

    2012-07-01

    On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision. Only in November 30, 2011, the new government elected on 20 November 2011 officially selected a non-nuclear municipality, Villar de Canas, for hosting this facility. This paper focuses on analysing the factors facilitating and hindering the siting of controversial facilities, in particular the interim storage facility in Spain. It demonstrates that involving all stakeholders in the decision-making process should not be underestimated. In the case of Spain, all regional governments where there were candidate municipalities willing to host the centralised interim storage facility, publicly opposed to the siting of the facility. (author)

  12. Remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 groundwater operable units' interim action

    International Nuclear Information System (INIS)

    This document is a combination remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 Operable Units (located on the Hanford Site in Richland, Washington) interim action. The interim actions described in this document represent the first of an ongoing program to address groundwater contamination in each operable unit. This document describes the design basis, provides a description of the interim action, and identifies how they will meet the requirements set forth in the interim action Record of Decision

  13. Surface Water Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, South Walnut Creek Basin, Operable Unit No. 2

    International Nuclear Information System (INIS)

    Volume 2 of this IM/IRA Plan contains OU 2 surface water, sediment, ground water and soil chemistry data, as well as the South Walnut Creek Basin Surface Water IM/IRA schedule and a tabulation of ARARs. (FL)

  14. Early interim {sup 18}F-FDG PET in Hodgkin's lymphoma: evaluation on 304 patients

    Energy Technology Data Exchange (ETDEWEB)

    Zinzani, Pier Luigi; Stefoni, Vittorio; Broccoli, Alessandro; Argnani, Lisa; Baccarani, Michele [University of Bologna, Institute of Hematology and Medical Oncology ' ' L. e A. Seragnoli' ' , Policlinico ' ' Sant' Orsola-Malpighi' ' , Bologna (Italy); Rigacci, Luigi; Puccini, Benedetta [Azienda Ospedaliero Universitaria ' ' Careggi' ' , Hematology Department, Florence (Italy); Castagnoli, Antonio [Ospedale ' ' Misericordia e Dolce' ' , Nuclear Medicine, Prato (Italy); Vaggelli, Luca [Azienda Ospedaliero Universitaria ' ' Careggi' ' , Nuclear Medicine, Florence (Italy); Zanoni, Lucia; Fanti, Stefano [Policlinico ' ' Sant' Orsola-Malpighi' ' , Department of Nuclear Medicine, Bologna (Italy)

    2012-01-15

    The use of early (interim) PET restaging during first-line therapy of Hodgkin's lymphoma (HL) in clinical practice has considerably increased because of its ability to provide early recognition of treatment failure allowing patients to be transferred to more intensive treatment regimens. Between June 1997 and June 2009, 304 patients with newly diagnosed HL (147 early stage and 157 advanced stage) were treated with the ABVD regimen at two Italian institutions. Patients underwent PET staging and restaging at baseline, after two cycles of therapy and at the end of the treatment. Of the 304 patients, 53 showed a positive interim PET scan and of these only 13 (24.5%) achieved continuous complete remission (CCR), whereas 251 patients showed a negative PET scan and of these 231 (92%) achieved CCR. Comparison between interim PET-positive and interim PET-negative patients indicated a significant association between PET findings and 9-year progression-free survival and 9-year overall survival, with a median follow-up of 31 months. Among the early-stage patients, 19 had a positive interim PET scan and only 4 (21%) achieved CCR; among the 128 patients with a negative interim PET scan, 122 (97.6%) achieved CCR. Among the advanced-stage patients, 34 showed a persistently positive PET scan with only 9 (26.4%) achieving CCR, whereas 123 showed a negative interim PET scan with 109 (88.6%) achieving CCR. Our results demonstrate the role of an early PET scan as a significant step forward in the management of patients with early-stage or advanced-stage HL. (orig.)

  15. Wayne Interim Storage Site environmental report for calendar year 1992, 868 Black Oak Ridge Road, Wayne, New Jersey

    International Nuclear Information System (INIS)

    This report describes the environmental surveillance program at the Wayne Interim Storage Site (WISS) and provides the results for 1992. The fenced, site, 32 km (20 mi) northwest of Newark, New Jersey, was used between 1948 and 1971 for commercial processing of monazite sand to separate natural radioisotopes - predominantly thorium. Environmental surveillance of WISS began in 1984 in accordance with Department of Energy (DOE) Order 5400.1 when Congress added the site to DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). The environmental surveillance program at WISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; radium-226, radium-228, thorium-230, thorium-232, total uranium, and several chemicals in surface water and sediment; and total uranium, radium-226, radium-228, thorium-230, thorium-232, and organic and inorganic chemicals in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. This monitoring program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results for environmental surveillance in 1992 show that the concentrations of all radioactive and most chemical contaminants were below applicable standards

  16. Maywood Interim Storage Site environmental report for calendar year 1992, 100 West Hunter Avenue, Maywood, New Jersey

    International Nuclear Information System (INIS)

    This report describes the environmental surveillance program at the Maywood Interim Storage Site (MISS) and provides the results for 1992. Environmental monitoring of MISS began in 1984, when the site was assigned to DOE by Congress through the Energy and Water Development Appropriations Act and was placed under DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. MISS is part of a National Priorities List (NPL) site. The environmental surveillance program at MISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium in surface water, sediment, and groundwater. Additionally, chemical analysis includes metals and organic compounds in surface water and groundwater and metals in sediments. This program assists in fulfilling the DOE objective of measuring and monitoring effluents from DOE activities and calculating hypothetical doses to members of the general public. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Environmental standards are established to protect public health and the environment. The radiological data for all media sampled support the conclusion that doses to the public are not distinguishable from natural background radiation

  17. A process of spent nuclear fuel treatment with the interim storage of TRU by use amidic extractants

    Energy Technology Data Exchange (ETDEWEB)

    Tachimori, Shoichi; Suzuki, Shinichi; Sasaki, Yuji [Japan Atomic Energy Research Inst., Tokyo (Japan)

    2001-12-01

    A new chemical process, ARTIST process, is proposed for the treatment of spent nuclear fuel. The main concept of the ARTIST process is to recover and stock separately all actinides, uranium and a mixture of transuranics, and to dispose fission products. The process composed of two main steps, a uranium exclusive isolation and a total recovery of transuranium elements (TRU); which copes with the nuclear non-proliferation measures, and additional processes. Both actinide products are solidified by calcination and allowed to the interim storage for future utilization. These separations are achieved by use of amidic extractants in accord with the CHON principle. The technical feasibility of the ARTIST process was explained by the experimental results of both the branched-alkyl monoamides in extracting uranium and suppressing the extraction of tetravalent actinides due to the steric effect and the diglycolic amide in thorough extraction of all TRU by tridentate coordination. When these TRU are requested to put into reactors, LWR or FBR, for power generation or the Accelerator-Driven System (ADS) for transmutation, lanthanides are to be removed from TRU by utilizing a soft nitrogen donor ligand. (author)

  18. Development of dual-purpose metal cask for interim storage of spent nuclear fuel (1). Outline of cask structure

    International Nuclear Information System (INIS)

    Spent fuels discharged from nuclear power plants in Japan are planed to be reprocessed at the nuclear fuel recycle plant under construction at Rokkasho-mura. Since the amount of the spent fuels exceeds that of recycled fuel, the spent fuels have to be properly stored and maintained as recycle fuel resource until the beginning of the reprocessing. For that sake, interim storage installations are being constructed outside the nuclear power plants by 2010. The storage dry casks have been practically used as the interim storage in the nuclear power plants. From this reason, the storage system using the storage dry casks is promising as the interim storage installations away form the reactors, which are under discussion. In the interim storage facilities, the storage using the dry cask of the storage metal cask with business showings, having the function of transportation is now under discussion. By employing transportation and storage dual-purpose cask, the repack equipments can be exhausted, and the reliability of the interim storage installations can be increased. Hitachi, Ltd. has been developing the high reliable and economical transportation and storage dry metal cask. In this report, the outline of our developing transportation and storage dry cask is described. (author)

  19. Diesel Emission Control -- Sulfur Effects (DECSE) Program; Phase I Interim Date Report No. 3: Diesel Fuel Sulfur Effects on Particulate Matter Emissions

    Energy Technology Data Exchange (ETDEWEB)

    DOE; ORNL; NREL; EMA; MECA

    1999-11-15

    The Diesel Emission Control-Sulfur Effects (DECSE) is a joint government/industry program to determine the impact of diesel fuel sulfur levels on emission control systems whose use could lower emissions of nitrogen oxides (NO{sub x}) and particulate matter (PM) from on-highway trucks in the 2002--2004 model years. Phase 1 of the program was developed with the following objectives in mind: (1) evaluate the effects of varying the level of sulfur content in the fuel on the emission reduction performance of four emission control technologies; and (2) measure and compare the effects of up to 250 hours of aging on selected devices for multiple levels of fuel sulfur content. This interim report covers the effects of diesel fuel sulfur level on particulate matter emissions for four technologies.

  20. Interim report of evaluation of research and development problems in 2002 FY. Research and development of collaboration with Russian Institutes for Russian weapon plutonium demolition

    International Nuclear Information System (INIS)

    The evaluation of above theme was carried out by data from JNC and discussion at the evaluation committee, which is composed by 14 members. The evaluation method, procedure, items, evaluation standard and results are stated. BFS-2 critical experiment was finished. Three bodies irradiation examination had been finished and the post-irradiation examination will be begun soon. Technical possibility of 1.3 ton weapon plutonium disposition by MOX reactor core was confirmed. Possibility of BN reactor core fuel design was discussed and confirmed by data of hybrid reactor core and fuel design obtained. Safety analysis of BN600 hybrid reactor core was carried out and compared with analytical results of Russia. The last design step of production line for equipment of RIAR facility was attained and a part of them began to be bought. The references consist of interim evaluation of R and D problem, measures of evaluation results, supplementary explanation data, explanation data of problem and OHP. (S.Y.)

  1. qPET - a quantitative extension of the Deauville scale to assess response in interim FDG-PET scans in lymphoma

    Energy Technology Data Exchange (ETDEWEB)

    Hasenclever, Dirk [University of Leipzig, Institute for Medical Informatics, Statistics and Epidemiology (IMISE), Leipzig (Germany); Kurch, Lars; Georgi, Thomas; Sabri, Osama; Kluge, Regine [University Hospital Leipzig, Department of Nuclear Medicine, Leipzig (Germany); Mauz-Koerholz, Christine; Koerholz, Dieter [University Hospital Halle, Department of Pediatrics, Halle (Germany); Elsner, Andreas [Hermes Medical Solutions AB, Stockholm (Sweden); Wallace, Hamish [Royal Hospital for Sick Children, Edinburgh, Scotland (United Kingdom); Landman-Parker, Judith [Hopital d' Enfants Armand Trousseau, Paris (France); Moryl-Bujakowska, Angelina [Jagiellonian University Medical College, Department of Pediatric Oncology and Hematology, Polish-American Institute of Pediatrics, Krakow (Poland); Cepelova, Michaela [Department of Pediatric Hematology and Oncology, Faculty Hospital Motol, Prague (Czech Republic); Karlen, Jonas [Karolinska University Hospital, Pediatric Cancer Unit, Astrid Lindgrens Childrens Hospital, Stockholm (Sweden); Alvarez Fernandez-Teijeiro, Ana [University Hospital Virgen Macarena Avda, Department of Pediatric Oncology and Hematology, Sevilla (Spain); Attarbaschi, Andishe [Medical University of Vienna, Department of Pediatric Hematology and Oncology, St. Anna Children' s Hospital, Vienna (Austria); Fossaa, Alexander [Department of Medical Oncology and Radiotherapy, Rikshospitalet - Radiumhospitalet HF, Oslo (Norway); Pears, Jane [Our Lady' s Children' s Hospital, Crumlin, Dublin (Ireland); Hraskova, Andrea [University Children' s Hospital, Clinic of Pediatric Oncology, Bratislava (Slovakia); Bergstraesser, Eva [University Children' s Hospital, Department Oncology, Zurich (Switzerland); Beishuizen, Auke [MC - Sophia Children' s Hospital, Department of Pediatric Oncology/Hematology, Rotterdam (Netherlands); Uyttebroeck, Anne [University Hospitals of Leuven, Department of Pediatric Hemato-Oncology, Leuven (Belgium); Schomerus, Eckhard [University of Odense (OUH), Department of Pediatric Oncology and Hematology, H. C. Andersen Children' s Hospital, Odense (Denmark)

    2014-07-15

    Interim FDG-PET is used for treatment tailoring in lymphoma. Deauville response criteria consist of five ordinal categories based on visual comparison of residual tumor uptake to physiological reference uptakes. However, PET-response is a continuum and visual assessments can be distorted by optical illusions. With a novel semi-automatic quantification tool we eliminate optical illusions and extend the Deauville score to a continuous scale. SUV{sub peak} of residual tumors and average uptake of the liver is measured with standardized volumes of interest. The qPET value is the quotient of these measurements. Deauville scores and qPET-values were determined in 898 pediatric Hodgkin's lymphoma patients after two OEPA chemotherapy cycles. Deauville categories translate to thresholds on the qPET scale: Categories 3, 4, 5 correspond to qPET values of 0.95, 1.3 and 2.0, respectively. The distribution of qPET values is unimodal with a peak representing metabolically normal responses and a tail of clearly abnormal outliers. In our patients, the peak is at qPET = 0.95 coinciding with the border between Deauville 2 and 3. qPET cut values of 1.3 or 2 (determined by fitting mixture models) select abnormal metabolic responses with high sensitivity, respectively, specificity. qPET methodology provides semi-automatic quantification for interim FDG-PET response in lymphoma extending ordinal Deauville scoring to a continuous scale. Deauville categories correspond to certain qPET cut values. Thresholds between normal and abnormal response can be derived from the qPET-distribution without need for follow-up data. In our patients, qPET < 1.3 excludes abnormal response with high sensitivity. (orig.)

  2. qPET - a quantitative extension of the Deauville scale to assess response in interim FDG-PET scans in lymphoma

    International Nuclear Information System (INIS)

    Interim FDG-PET is used for treatment tailoring in lymphoma. Deauville response criteria consist of five ordinal categories based on visual comparison of residual tumor uptake to physiological reference uptakes. However, PET-response is a continuum and visual assessments can be distorted by optical illusions. With a novel semi-automatic quantification tool we eliminate optical illusions and extend the Deauville score to a continuous scale. SUVpeak of residual tumors and average uptake of the liver is measured with standardized volumes of interest. The qPET value is the quotient of these measurements. Deauville scores and qPET-values were determined in 898 pediatric Hodgkin's lymphoma patients after two OEPA chemotherapy cycles. Deauville categories translate to thresholds on the qPET scale: Categories 3, 4, 5 correspond to qPET values of 0.95, 1.3 and 2.0, respectively. The distribution of qPET values is unimodal with a peak representing metabolically normal responses and a tail of clearly abnormal outliers. In our patients, the peak is at qPET = 0.95 coinciding with the border between Deauville 2 and 3. qPET cut values of 1.3 or 2 (determined by fitting mixture models) select abnormal metabolic responses with high sensitivity, respectively, specificity. qPET methodology provides semi-automatic quantification for interim FDG-PET response in lymphoma extending ordinal Deauville scoring to a continuous scale. Deauville categories correspond to certain qPET cut values. Thresholds between normal and abnormal response can be derived from the qPET-distribution without need for follow-up data. In our patients, qPET < 1.3 excludes abnormal response with high sensitivity. (orig.)

  3. Towards a sustainable electricity system for Ontario : interim report

    International Nuclear Information System (INIS)

    More changes have occurred in Ontario's electricity sector in the past 5 years than over the preceding 9 decades since the creation of Ontario Hydro Electric Power Commission in 1906. The province's nuclear generating facilities were taken out of service in 1997 for safety and maintenance overhauls. The existing nuclear facilities, which account for 28 per cent of the province's generating capacity, will reach the end of their operational lifetimes by 2018. The government of Ontario also announced the phasing out of Ontario Power Generation's coal-fired plants by 2007 due to the environmental health impacts of their operation. These changes have ignited debate over the province's future electricity needs and how they might be met. This study examined by how much electricity demand in Ontario could be reduced through the adoption of energy efficient technologies, fuel switching, cogeneration and demand response measures. It also examined how much future supply could be obtained from renewable energy sources such as wind, the upgrading of existing hydroelectric facilities, and the development of new solar, biomass and small-scale hydro facilities. It also examined how to accommodate the remaining grid demand and which public policies should be adopted to maximize efficiency and other demand side measures. The impacts of the policies were simulated using the Canadian Integrated Modelling System (CIMS) computer model developed by the Energy and Materials Research Group at Simon Fraser University. The CIMS simulations were conducted under the assumptions that barriers to cogeneration would be removed, financial incentives would be provided along with innovative financing programs. The study revealed that capital investments of $18.2 billion over the 2005-2020 period would be required to reduce peak demand of 12,300 MW relative to the business and usual forecast through efficiency, fuel switching and cogeneration. 13 refs., 8 tabs

  4. T-TY Tank Farm Interim Surface Barrier Demonstration—Vadose Zone Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Z. F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

    2010-09-27

    The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank of the 241-T Tank Farm in 1973. Five tanks are assumed to have leaked in the TY Farm. Many of the contaminants from those leaks still reside within the vadose zone within the T and TY Tank Farms. The Department of Energy’s Office of River Protection seeks to minimize the movement of these contaminant plumes by placing interim barriers on the ground surface. Such barriers are expected to prevent infiltrating water from reaching the plumes and moving them further. The soil water regime is monitored to determine the effectiveness of the interim surface barriers. Soil-water content and water pressure are monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. Four instrument nests were installed in the T Farm in fiscal year (FY) 2006 and FY2007; two nests were installed in the TY Farm in FY2010. Each instrument nest contains a neutron probe access tube, a capacitance probe, and four heat-dissipation units. A meteorological station has been installed at the north side of the fence of the T Farm. This document summarizes the monitoring methods, the instrument calibration and installation, and the vadose zone monitoring plan for interim barriers in T farm and TY Farm.

  5. Interim report on the accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company

    International Nuclear Information System (INIS)

    The Investigation Committee on the Accident at the Fukushima Nuclear Power Stations (the Investigation Committee) of Tokyo Electric Power Company (TEPCO) was established by the Cabinet decision on May 24, 2011. Its objectives are: to conduct investigation for finding out the causes of accidents at the Fukushima Dai-ichi Nuclear Power Station (Fukushima Dai-ichi NPS) and Fukushima Dai-ni Nuclear Power Station (Fukushima Dai-ni NPS) of TEPCO as well as the causes of accident damage; and to make policy recommendations for limiting the expansion of damage and preventing reoccurrence of similar accidents. The Investigation Committee has conducted its investigation and evaluation since its first meeting on June 7, 2011. Its activities included: site visits to the Fukushima Dai-ichi and Dai-ni NPSs, as well as to other facilities; hearing of heads of local governments around the Fukushima Dai-ichi NPS; and hearing of people concerned through interviews mainly arranged by the Secretariat. As of December 16, 2011, the number of interviewees reached 456. The investigation and evaluation by the Investigation Committee are still ongoing and the Interim Report does not cover every item that the Committee aims at investigating and evaluating. Fact-finding of even some of those items discussed in the Interim Report are not yet completed. The Investigation Committee continues to conduct its investigation and evaluation and will issue its Final Report in the summer of 2012. This brief executive summary covers mainly considerations and evaluation of the issues in Chapter VII of the Interim Report, with brief reference to Chapters I to VI. The Investigation Committee recommendations are printed in bold. (author)

  6. 40 CFR 86.1860-04 - How to comply with the Tier 2 and interim non-Tier 2 fleet average NOX standards.

    Science.gov (United States)

    2010-07-01

    ... interim non-Tier 2 fleet average NOX standards. 86.1860-04 Section 86.1860-04 Protection of Environment... § 86.1860-04 How to comply with the Tier 2 and interim non-Tier 2 fleet average NOX standards. (a) The fleet average standards referred to in this section are the corporate fleet average standards for...

  7. Early interim FDG PET/CT prediction of treatment response and prognosis in pediatric Hodgkin disease - added value of low-dose CT

    Energy Technology Data Exchange (ETDEWEB)

    Ilivitzki, Anat [Rambam Health Care Campus, Department of Diagnostic Imaging, Haifa (Israel); Rambam Health Care Campus, Department of Pediatric Radiology, Haifa (Israel); Radan, Lea; Israel, Ora [Rambam Health Care Campus, Department of Nuclear Medicine, Haifa (Israel); Ben-Arush, Miriam; Ben-Barak, Ayelet [Rambam Health Care Campus, Department of Pediatric Oncology, Haifa (Israel)

    2013-01-15

    Interim 18F-FDG PET helps predict outcome and tailor treatment in adults with Hodgkin disease (HD). The purpose of this study was to assess predictive values of interim 18F-FDG PET/CT in children with HD and to define the potential added value to interim PET of low-dose CT. Children were prospectively enrolled August 2002-April 2007. PET/low-dose CT was performed at staging, after 2 cycles, at the end of treatment and during follow-up (mean 45 months). Treatment was unchanged regardless of interim results. PET and low-dose CT were read independently. Of 34 enrolled children (ages 3-17 years), 27 achieved complete response, 4 had progressive disease and 3 had relapse. Interim PET alone had positive and negative predictive values of 67% and 89%, respectively. Interim low-dose CT alone had positive and negative predictive values of 35% and 100%, respectively. Interim PET/CT had positive and negative predictive values of 75% and 96%, respectively. Early interim PET/CT was a good predictor of outcome. Integrated PET and low-dose CT improved the predictive value in children with HD. (orig.)

  8. Interim storage of solidified fission products from fuel element reprocessing with utilization of obtaining post-decay heat

    International Nuclear Information System (INIS)

    It is noted that the out-lined interim store for HRW with industrial utilization of decay heat (production of saturated steam and hydrogen) does include a certain risk potential like any technical plant but that it does not represent a danger to the population living nearby. All internal and external impacts on the store result in safely triggering natural convection cooling. A further emergency cooling system is provided by the water irrigation facility so that obtaining after-heat can be safely removed under all circumstances. Therefore, there are no safety-technology arguments against any realization of the concept presented for interim storage of solidified high-level radio-active wastes. An interim store of this type may be built and operated even in densely populated regions and urban agglomerations. (orig./HP)

  9. 2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

    Energy Technology Data Exchange (ETDEWEB)

    D. Shanklin

    2006-07-19

    This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities fro the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003.

  10. IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-03-01

    Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D{sup +})-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m{sup 2}, 20 dpa/year for Fe) in a volume of 500 cm{sup 3} for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

  11. Nondestructive evaluation of creep-fatigue damage: an interim report. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Nickell, R.E.

    1977-02-01

    In view of the uncertainties involved in designing against creep-fatigue failure and the consequences of such failures in Class 1 nuclear components that operate at elevated temperature, the possibility of intermittent or even continuous non-destructive examination of these components has been considered. In this interim report some preliminary results on magnetic force and ultrasonic evaluation of creep-fatigue damage in an LMFBR steam generator material are presented. These results indicate that the non-destructive evaluation of pure creep damage will be extremely difficult. A set of biaxial creep-fatigue tests that are designed to discriminate between various failure theories is also described.

  12. Meet the Challenges of Spent Fuel Interim Storage by Using Intensive Innovation

    International Nuclear Information System (INIS)

    AREVA Logistics Business Unit, through its entities TN International in France, Transnuclear Inc. in the USA and Transnuclear Ltd. in Japan, has proposed for more than 2 decades the leading dry storage systems of spent fuel in use today. These systems have mainly been sold in Europe, in the US and in Japan. The PWR, BWR or VVER fuel characteristics may have various enrichment values up to 5%, various cooling time down to 2 years and various burnups up to 65,000 MWd/tU. Facing the current international trend towards expanding Spent Fuel Interim Storage capabilities and the unpredictable market prices of steel large forged components, AREVA Logistics Business Unit has launched an extensive innovation process to create the new generation of dry interim storage systems: i) the TN®DUO cask is an innovative and cost effective dual purpose cask; and ii) the TN®NOVA system is an innovative canister system based on the NUHOMS® cask system, the US industry leading spent fuel storage solution. These two innovative solutions can naturally be transported to the storage facilities as well as other sites such as reprocessing facilities or geological repositories depending of the national strategy for the back-end of the nuclear fuel cycle. In addition to these innovative dry interim storage systems and based on 40 years experience in design, licensing and fabrication of baskets for transportation cask, AREVA Logistics Business Unit has developed new innovative designs for Underwater Fuel Storage Racks which includes the use of Metal Matrix Composite (MMC) material as a neutron absorbing material. This kind of material allows proposing a cost efficient solution with a reduced rack weight and a significant improvement of the criticality performance. Furthermore, AREVA Logistics Business Unit Rack Design remains flexible and evolutionary linked to fuel characteristics evolution and it can include other neutron absorbing materials commonly used in the nuclear industry as borated

  13. Operable Unit 3: Proposed Plan/Environmental Assessment for interim remedial action

    International Nuclear Information System (INIS)

    This document presents a Proposed Plan and an Environmental Assessment for an interim remedial action to be undertaken by the US Department of Energy (DOE) within Operable Unit 3 (OU3) at the Fernald Environmental Management Project (FEMP). This proposed plan provides site background information, describes the remedial alternatives being considered, presents a comparative evaluation of the alternatives and a rationnale for the identification of DOE's preferred alternative, evaluates the potential environmental and public health effects associated with the alternatives, and outlines the public's role in helping DOE and the EPA to make the final decision on a remedy

  14. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear Regulation Authority (NRA: which controls the regulations for Spent Fuel Interim Storage Facilities). In 2012 fiscal year, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel under cask drop accidents, and preparation for PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be also carried out in 2013 fiscal year and after. (author)

  15. Emulytics for Cyber-Enabled Physical Attack Scenarios: Interim LDRD Report of Year One Results.

    Energy Technology Data Exchange (ETDEWEB)

    Clem, John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Urias, Vincent [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Atkins, William Dee [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Symonds, Christopher J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-08

    Sandia National Laboratories has funded the research and development of a new capability to interactively explore the effects of cyber exploits on the performance of physical protection systems. This informal, interim report of progress summarizes the project’s basis and year one (of two) accomplishments. It includes descriptions of confirmed cyber exploits against a representative testbed protection system and details the development of an emulytics capability to support live, virtual, and constructive experiments. This work will support stakeholders to better engineer, operate, and maintain reliable protection systems.

  16. IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

    International Nuclear Information System (INIS)

    Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D+)-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m2, 20 dpa/year for Fe) in a volume of 500 cm3 for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

  17. Interim obturator in an infant with Treacher Collins syndrome: Review and chairside modification in impression making

    Directory of Open Access Journals (Sweden)

    Sudhir Bhandari

    2011-01-01

    Full Text Available Treacher Collins syndrome has been described as a syndrome involving 1st and 2nd branchial arches, affecting various organs in the craniofacial region. Affected infants report with nasal regurgitation and minimal dietary intake due to cleft palate, consequently show delayed and retarded growth. The situation is further complicated when the repair of the palatal defect is postponed due to delayed milestones. At this juncture, it is of paramount importance to intervene prosthetically and close the defect with the aid of an interim obturator. Herein we describe a simple, yet successful, chairside approach to make an impression of an infant without the aid of any kind of anesthesia.

  18. Interim obturator in an infant with Treacher Collins syndrome: Review and chairside modification in impression making.

    Science.gov (United States)

    Bhandari, Sudhir; Aras, Meena; Bakshi, Sonika

    2011-10-01

    Treacher Collins syndrome has been described as a syndrome involving 1st and 2nd branchial arches, affecting various organs in the craniofacial region. Affected infants report with nasal regurgitation and minimal dietary intake due to cleft palate, consequently show delayed and retarded growth. The situation is further complicated when the repair of the palatal defect is postponed due to delayed milestones. At this juncture, it is of paramount importance to intervene prosthetically and close the defect with the aid of an interim obturator. Herein we describe a simple, yet successful, chairside approach to make an impression of an infant without the aid of any kind of anesthesia.

  19. Reliability Centered Maintenance for Savannah River Site's interim waste management facilities

    International Nuclear Information System (INIS)

    The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC)

  20. Interim structural evaluation of pool swell loads on suppression chamber of Peach Bottom Plant

    International Nuclear Information System (INIS)

    An interim structural evaluation has been conducted to establish the effects of pool swell loads on the suppression chamber system of a typical Mark I plant. The plant selected for the analyses was the Peach Bottom Atomic Power Station, Unit 3. In order to provide results in a timely manner, the geometry was adopted from an existing finite element model of a suppression chamber such that the model closely represented, though not identically, the Peach Bottom Plant. A brief summary of the results obtained from the various analyses is presented for the three main structural components of the suppression chamber, i.e., the support columns, the reinforcing ring, and the cylindrical shell

  1. Interim structural evaluation of pool swell loads on suppression chamber of Peach Bottom Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kontoudakis, J.; Higginbotham, A.B.

    1976-04-01

    An interim structural evaluation has been conducted to establish the effects of pool swell loads on the suppression chamber system of a typical Mark I plant. The plant selected for the analyses was the Peach Bottom Atomic Power Station, Unit 3. In order to provide results in a timely manner, the geometry was adopted from an existing finite element model of a suppression chamber such that the model closely represented, though not identically, the Peach Bottom Plant. A brief summary of the results obtained from the various analyses is presented for the three main structural components of the suppression chamber, i.e., the support columns, the reinforcing ring, and the cylindrical shell.

  2. Liivimaa ja Augsburgi Interim 1548. Lisandusi teadmistele reformatsiooni levikust Baltikumi / Juhan Kreem

    Index Scriptorium Estoniae

    Kreem, Juhan, 1971-

    2011-01-01

    Interim (15. mail Augsburgi riigipäevale kogunenutele esitatud usuküsimuste ajutine lahendus) oli viimane tõsine katse ületada usulõhe. Võib arvata, et Interimi tekst sai Liivimaal laiemalt teatavaks 1548. aasta novembri esimesel poolel. Saksa Ordu reageering sellele sisaldub 1548. aasta sügisel koostatud ordukapiitlil arutatavate küsimuste nimekirjas. Tegemist on Interimi luterliku eitamisega. Tallinlaste meelest polnud keiser üldse volitatud usuasjade üle otsustama. Tallinlaste soovitatav käitumine oli vaikiv vastupanu. Interimi-vastast suhtumist ei saa siiski pidada Liivimaa üksmeelseks väljenduseks

  3. Evaluation of Equivalent Dose Rate of Interim Dry Storage Casks Loaded with Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Equivalent dose rate calculations of the CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks were performed using SCALE 4.3 computer codes system. These casks are planned for an interim storage of spent nuclear fuel at Ignalina NPP. The dose rate calculations were made on the sidelong, upper and lower surface of the cask and at the certain distance. Results show that dose rate values on the surface of the cask are much less then permissible value 1000 μSv/h when average burnup of fuel assembly is 20 GWd/tU. (author)

  4. Environmental Impact Statement. March 2011. Interim storage, encapsulation and final disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    An Environmental Impact Statement (EIS) shall be prepared and submitted along with applications for permissibility and a licence under the Environmental Code and a licence under the Nuclear Activities Act for new nuclear facilities. This Environmental Impact Statement has been prepared by Svensk Kaernbraenslehantering AB (the Swedish Nuclear Fuel and Waste Management Co, SKB) to be included in the licence applications for continued operation of Clab (central interim storage facility for spent nuclear fuel) in Simpevarp in Oskarshamn Municipality and construction and operation of facilities for encapsulation (integrated with Clab) and final disposal of spent nuclear fuel in Forsmark in Oesthammar Municipality

  5. Conceptual design of the JT-60 neutral beam injection system (interim report)

    International Nuclear Information System (INIS)

    This is an interim report on conceptual design of the JT-60 neutral beam injection system. Requirements for the JT-60 neutral beam injector are injection of a 20 MW neutral hydrogen beam into the plasma in the vicinity of energy 75 keV as long as 10 sec, keeping thermal gas flow rate into the torus vacuum chamber below 15% the neutral beam flux. On the basis of these requirements and recent results of research and development of ion sources and beam line components, system conceptual design is now proceeding. Scale of the JT-60 neutral beam injection system is discussed, indicating also future problems. (auth.)

  6. Unit cell modeling in support of interim performance assessment for low level tank waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Kline, N.W., Westinghouse Hanford

    1996-08-01

    A unit cell model is used to simulate the base analysis case and related sensitivity cases for the interim performance assessment of low level tank waste disposal. Simulation case results are summarized in terms of fractional contaminant release rates to the vadose zone and to the water table at the unconfined aquifer. Results suggest that the crushed glass water conditioning layer at the top of the facility and the chemical retardation pad at the bottom of the facility can be important components of the facility. Results also suggest that the release rates to the water table are dominated by the release rate from the waste form.

  7. Republic of Congo; Joint Staff Advisory Note of the Interim Poverty Reduction Strategy Paper

    OpenAIRE

    International Monetary Fund

    2005-01-01

    This Joint Staff Advisory Note examines Congo’s Interim Poverty Reduction Strategy Paper (I-PRSP). The I-PRSP recognizes the lack of recent and good quality data on poverty, and recommends new surveys and studies to improve poverty assessment and analysis. On the basis of the sparsely available data, the I-PRSP estimates that at least 50 percent of the population is poor. The I-PRSP also links the high poverty incidence to a significant decline in per capita output and the deterioration of ...

  8. Environmental Impact Statement. March 2011. Interim storage, encapsulation and final disposal of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    An Environmental Impact Statement (EIS) shall be prepared and submitted along with applications for permissibility and a licence under the Environmental Code and a licence under the Nuclear Activities Act for new nuclear facilities. This Environmental Impact Statement has been prepared by Svensk Kaernbraenslehantering AB (the Swedish Nuclear Fuel and Waste Management Co, SKB) to be included in the licence applications for continued operation of Clab (central interim storage facility for spent nuclear fuel) in Simpevarp in Oskarshamn Municipality and construction and operation of facilities for encapsulation (integrated with Clab) and final disposal of spent nuclear fuel in Forsmark in Oesthammar Municipality

  9. Hydrogen combustion in an MCO during interim storage (fauske and associates report 99-14)

    Energy Technology Data Exchange (ETDEWEB)

    PLYS, M.G.

    1999-05-12

    Flammable conditions are not expected to develop in an MCO during interim storage. This report considers potential phenomena which, although not expected t o occur, could lead t o flammable conditions. For example, reactions of hydrogen w i t h fuel over decades a r e postulated t o lead t o flammable atmospheric mixtures. For the extreme cases considered in this report, the highest attainable post-combustion pressure is about 13 atmospheres absolute, almost a factor of two and a half below the MCO design pressure of 31 atmospheres.

  10. Subretinal Visual Implant Alpha IMS--Clinical trial interim report.

    Science.gov (United States)

    Stingl, Katarina; Bartz-Schmidt, Karl Ulrich; Besch, Dorothea; Chee, Caroline K; Cottriall, Charles L; Gekeler, Florian; Groppe, Markus; Jackson, Timothy L; MacLaren, Robert E; Koitschev, Assen; Kusnyerik, Akos; Neffendorf, James; Nemeth, Janos; Naeem, Mohamed Adheem Naser; Peters, Tobias; Ramsden, James D; Sachs, Helmut; Simpson, Andrew; Singh, Mandeep S; Wilhelm, Barbara; Wong, David; Zrenner, Eberhart

    2015-06-01

    A subretinal visual implant (Alpha IMS, Retina Implant AG, Reutlingen, Germany) was implanted in 29 blind participants with outer retinal degeneration in an international multicenter clinical trial. Primary efficacy endpoints of the study protocol were a significant improvement of activities of daily living and mobility to be assessed by activities of daily living tasks, recognition tasks, mobility, or a combination thereof. Secondary efficacy endpoints were a significant improvement of visual acuity/light perception and/or object recognition (clinicaltrials.gov, NCT01024803). During up to 12 months observation time twenty-one participants (72%) reached the primary endpoints, of which thirteen participants (45%) reported restoration of visual function which they use in daily life. Additionally, detection, localization, and identification of objects were significantly better with the implant power switched on in the first 3 months. Twenty-five participants (86%) reached the secondary endpoints. Measurable grating acuity was up to 3.3 cycles per degree, visual acuities using standardized Landolt C-rings were 20/2000, 20/2000, 20/606 and 20/546. Maximal correct motion perception ranged from 3 to 35 degrees per second. These results show that subretinal implants can restore very-low-vision or low vision in blind (light perception or less) patients with end-stage hereditary retinal degenerations. PMID:25812924

  11. Dobson, Brewer, ERA-40 and ERA-Interim original and merged total ozone data sets – evaluation of differences: a case study, Hradec Králové (Czech), 1961–2010

    OpenAIRE

    Vaníček, K.; L. Metelka; Skřivánková, P.; M. Staněk

    2012-01-01

    Homogenized data series of total ozone measurements taken by the regularly and well calibrated Dobson and Brewer spectrophotometers at Hradec Králové (Czech) and the data from the re-analyses ERA-40 and ERA-Interim were merged and compared to investigate differences between the particular data sets originated in Central Europe, the Northern Hemisphere (NH) mid-latitudes. The Dobson-to-Brewer transfer function and the algorithm for approximation of the data from the re-analyses were developed,...

  12. Dobson, Brewer, ERA-40 and ERA-Interim original and assimilated total ozone data sets – evaluation of differences: a case study, Hradec Králové (Czech), 1961–2010

    OpenAIRE

    Vaníček, K.; L. Metelka; Skřivánková, P.; M. Staněk

    2012-01-01

    Homogenized data series of total ozone measurements taken by the regularly and well calibrated Dobson and Brewer spectrophotometers at Hradec Králové (Czech) and the data from the re-analyses ERA-40 and ERA-Interim were assimilated and combined to investigate differences between the particular data sets over Central Europe, the NH mid-latitudes. The Dobson-to-Brewer transfer function and the algorithm for approximation of the data from the re-analyses were developed, tested and applied for cr...

  13. Hanford Tank Farm interim storage phase probabilistic risk assessment outline

    International Nuclear Information System (INIS)

    This report is the second in a series examining the risks for the high level waste (HLW) storage facilities at the Hanford Site. The first phase of the HTF PSA effort addressed risks from Tank 101-SY, only. Tank 101-SY was selected as the initial focus of the PSA because of its propensity to periodically release (burp) a mixture of flammable and toxic gases. This report expands the evaluation of Tank 101-SY to all 177 storage tanks. The 177 tanks are arranged into 18 farms and contain the HLW accumulated over 50 years of weapons material production work. A centerpiece of the remediation activity is the effort toward developing a permanent method for disposing of the HLW tank's highly radioactive contents. One approach to risk based prioritization is to perform a PSA for the whole HLW tank farm complex to identify the highest risk tanks so that remediation planners and managers will have a more rational basis for allocating limited funds to the more critical areas. Section 3 presents the qualitative identification of generic initiators that could threaten to produce releases from one or more tanks. In section 4 a detailed accident sequence model is developed for each initiating event group. Section 5 defines the release categories to which the scenarios are assigned in the accident sequence model and presents analyses of the airborne and liquid source terms resulting from different release scenarios. The conditional consequences measured by worker or public exposure to radionuclides or hazardous chemicals and economic costs of cleanup and repair are analyzed in section 6. The results from all the previous sections are integrated to produce unconditional risk curves in frequency of exceedance format

  14. Progress and future direction for the interim safe storage and disposal of Hanford high level waste (HLW)

    International Nuclear Information System (INIS)

    This paper describes the progress made at the largest environmental cleanup program in the United States. Substantial advances in methods to start interim safe storage of Hanford Site high-level wastes, waste characterization to support both safety- and disposal-related information needs, and proceeding with cost-effective disposal by the US DOE and its Hanford Site contractors, have been realized. Challenges facing the Tank Waste Remediation System Program, which is charged with the dual and parallel missions of interim safe storage and disposal of the high-level tank waste stored at the Hanford Site, are described

  15. Cna 1 spent fuel element interim dry storage system thermal analysis

    International Nuclear Information System (INIS)

    At the moment, the Atucha I Nuclear Power Plant (Cnea-I) located in the city of Lima, has enough room to store its spent fuel (Sf) in their two pools spent fuel until about 2015.In case of life extension a spend fuel element interim dry storage system is needed.Nucleolectrica Argentina S.A. (N A-S A) and the Comision Nacional de Energia Atomica (Cnea), have proposed different interim dry storage systems.These systems have to be evaluated in order to choose one of them.The present work's objective is the thermal analysis of one dry storage alternative for the Sf element of Cna 1.In this work a simple model was developed and used to perform the thermal calculations corresponding to the system proposed by Cnea.This system considers the store of sealed containers with 37 spent fuels in concrete modules.Each one of the containers is filled in the pool houses and transported to the module in a transference cask with lead walls.Fulfill the maximum cladding temperature requirement (<200 degrade C) for a total 2140 W thermal power

  16. Project management plan for the 105-C Reactor interim safe storage project. Revision 1

    International Nuclear Information System (INIS)

    In 1942, the Hanford Site was commissioned by the US Government to produce plutonium. Between 1942 and 1955, eight water-cooled, graphite-moderated reactors were constructed along the Columbia River at the Hanford Site to support the production of plutonium. The reactors were deactivated from 1964 to 1971 and declared surplus. The Surplus Production Reactor Decommissioning Project (BHI 1994b) will decommission these reactors and has selected the 105-C Reactor to be used as a demonstration project for interim safe storage at the present location and final disposition of the entire reactor core in the 200 West Area. This project will result in lower costs, accelerated schedules, reduced worker exposure, and provide direct benefit to the US Department of Energy for decommissioning projects complex wide. This project sets forth plans, organizational responsibilities, control systems, and procedures to manage the execution of the Project Management Plan for the 105-C Reactor Interim Safe Storage Project (Project Management Plan) activities to meet programmatic requirements within authorized funding and approved schedules. The Project Management Plan is organized following the guidelines provided by US Department of Energy Order 4700.1, Project Management System and the Richland Environmental Restoration Project Plan (DOE-RL 1992b)

  17. INTERIM STORAGE AND LONG TERM DISPOSAL OF RESEARCH REACTOR SPENT FUEL

    Energy Technology Data Exchange (ETDEWEB)

    Vinson, D

    2006-08-22

    Aluminum clad research reactor spent nuclear fuel (SNF) is currently being consolidated in wet storage basins (pools). Approximately 20 metric tons (heavy metal) of aluminum-based spent nuclear fuel (Al-SNF) is being consolidated for treatment, packaging, interim storage, and preparation for ultimate disposal in a geologic repository. The storage and disposal of Al-SNF are subject to requirements that provide for safety and acceptable radionuclide release. The options studied for interim storage of SNF include wet storage and dry storage. Two options have also been studied to develop the technical basis for the qualification and repository disposal of aluminum spent fuel. The two options studied include Direct Disposal and Melt-Dilute treatment. The implementation of these options present relative benefits and challenges. Both the Direct Disposal and the Melt-Dilute treatment options have been developed and their technical viability assessed. Adaptation of the melt-dilute technology for the treatment of spent fuel offers the benefits of converting the spent fuel into a proliferation resistant form and/or significantly reducing the volume of the spent fuel. A Mobile Melt-Dilute system concept has emerged to realize these benefits and a prototype system developed. The application of the melt-dilute technology for the treatment of legacy nuclear materials has been evaluated and also offers the promise for the safe disposal of these materials.

  18. CERCLA interim action at the Par Pond unit: A case study

    International Nuclear Information System (INIS)

    The Par Pond unit designated under CERCLA consists of sediments within a Savannah River Site (SRS) cooling water reservoir. The sediments are contaminated with radionuclides and nonradioactive constituents from nuclear production reactor operations. The mercury in Par Pond is believed to have originated from the Savannah River. Because of Par Pond Dam safety Issues, the water level of the reservoir was drawn down, exposing more than 1300 acres of contaminated sediments and triggering the need for CERCLA interim remedial action. This paper presents the interim action approach taken with Par Pond as a case study. The approach considered the complexity of the Par Pond ecosystem, the large size of Par Pond, the volume of contaminated sediments, and the institutional controls existing at SRS. The Environmental Protection Agency (EPA) considers units with large volumes of low-concentration wastes, as is the case with Par Pond, to be open-quotes special sites.close quotes Accordingly, EPA guidance establishes that the range of alternatives developed focus primarily on containment options and other remedial approaches that mitigate potential risks associated with the open-quotes special site.close quotes The remedial alternatives, according to EPA, are not to be prohibitively expensive or difficult to implement. This case study also is representative of the types of issues that will need to be addressed within the Department of Energy (DOE) complex as nuclear facilities are transitioned to inactive status and corrective/remedial actions are warranted

  19. INTERIM BARRIER AT HANFORDS TY FARM TO PROTECT GROUNDWATER AT THE HANFORD SITE WASHINGTON USA

    Energy Technology Data Exchange (ETDEWEB)

    PARKER DL; HOLM MJ; HENDERSON JC; LOBER RW

    2011-01-13

    An innovative interim surface barrier was constructed as a demonstration project at the Hanford Site's TY Tank Farm. The purpose of the demonstration barrier is to stop rainwater and snowmelt from entering the soils within the tank farm and driving contamination from past leaks and spills toward the ground water. The interim barrier was constructed using a modified asphalt material with very low permeability developed by MatCon{reg_sign}. Approximately 2,400 cubic yards of fill material were added to the tank farm to create a sloped surface that will gravity drain precipitation to collection points where it will be routed through buried drain lines to an evapotranspiration basin adjacent to the farm. The evapotranspiration basin is a lined basin with a network of perforated drain lines covered with soil and planted with native grasses. The evapotranspiration concept was selected because it prevents the runoff from percolating into the soil column and also avoids potential monitoring and maintenance issues associated with standing water in a traditional evaporation pond. Because of issues associated with using standard excavation and earth moving equipment in the farm a number of alternate construction approaches were utilized to perform excavations and prepare the site for the modified asphalt.

  20. Czech interim spent fuel storage facility: operation experience, inspections and future plans

    International Nuclear Information System (INIS)

    The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

  1. Modified Interim Mandibular Advancement (MIMA) Appliance for Symptomatic Correction of Obstructive Sleep Apnea.

    Science.gov (United States)

    Maurya, Rajkumar; Singh, Harpreet; Mishra, Harsh Ashok; Gupta, Ankur

    2016-08-01

    Obstructive Sleep Apnea (OSA) is a chronic, progressive, multifactorial, life-threatening disorder that causes significant impact on patient's life. Patients with OSA [Apnea/Hypopnea Index (AHI)>30] who cannot tolerate Continuous Positive Airway Pressure (CPAP) therapy or are not surgical candidates may benefit from oral appliances. This paper describes interim appliance devised from existing Hawley's retainer in patients with OSA. A 38-year-old man of athletic built with history of orthodontic treatment six months back due to esthetic concerns and wearing upper Hawley's retainer, reported with chief complaint of frequent nocturnal awakening along with excessive daytime somnolence. Based on diagnostic aids, he was diagnosed with Class II Division 1 malocclusion with severe mandibular retrusion. Sleep test revealed AHI score of 34, suggestive of severe OSA. With ENT and Oral surgeon concurrence, mandibular advancement of 7mm with Bilateral Sagital Split Osteotomy (BSSO) with distraction was contemplated as a viable functional and curative stable treatment plan. Because of non-adherence and non-compliance with CPAP therapy and on request of patient, an interim anterior positioning appliance was devised to facilitate comfortable sound sleep till the time surgery is impending. After three months of wearing this customized appliance, improved quality of sleep was discernible; both subjectively as reported by patient and objectively using sleep test (AHI=9.8). PMID:27656589

  2. Physical protection of a nuclear waste interim storage against interference by third parties

    International Nuclear Information System (INIS)

    Full text: The nuclear power plant (NPP) Lubmin/Greifswald was shut down in 1990. As there exists no final storage for radioactive waste in Germany it is necessary to store the spent nuclear fuel elements and the radioactive waste of the decommissioning on the NPP site. Therefore the Interim Storage North (ISN) was erected. The spent fuel elements are dry stored in massive iron casks from type CASTOR-440/84. The physical protection of the ISN is determined by the storage of spent nuclear fuel. It must realize the prevention of danger to life and health due to release of a substantial amount of radioactive material and of stealing nuclear fuels in such amounts that critical accumulations can be produced. The concept of physical protection against interference by third parties consists of three barriers. The first is the CASTOR cask itself, the second is the storage building and the third the fence around the storage site. In the paper the systems of physical protection of the Interim Storage North are presented. (author)

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

    International Nuclear Information System (INIS)

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

  4. Energy policy act transportation study: Interim report on natural gas flows and rates

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-17

    This report, Energy Policy Act Transportation Study: Interim Report on Natural Gas Flows and Rates, is the second in a series mandated by Title XIII, Section 1340, ``Establishment of Data Base and Study of Transportation Rates,`` of the Energy Policy Act of 1992 (P.L. 102--486). The first report Energy Policy Act Transportation Study: Availability of Data and Studies, was submitted to Congress in October 1993; it summarized data and studies that could be used to address the impact of legislative and regulatory actions on natural gas transportation rates and flow patterns. The current report presents an interim analysis of natural gas transportation rates and distribution patterns for the period from 1988 through 1994. A third and final report addressing the transportation rates and flows through 1997 is due to Congress in October 2000. This analysis relies on currently available data; no new data collection effort was undertaken. The need for the collection of additional data on transportation rates will be further addressed after this report, in consultation with the Congress, industry representatives, and in other public forums.

  5. Identifying Potential Areas for Siting Interim Nuclear Waste Facilities Using Map Algebra and Optimization Approaches

    Energy Technology Data Exchange (ETDEWEB)

    Omitaomu, Olufemi A [ORNL; Liu, Cheng [ORNL; Cetiner, Sacit M [ORNL; Belles, Randy [ORNL; Mays, Gary T [ORNL; Tuttle, Mark A [ORNL

    2013-01-01

    The renewed interest in siting new nuclear power plants in the United States has brought to the center stage, the need to site interim facilities for long-term management of spent nuclear fuel (SNF). In this paper, a two-stage approach for identifying potential areas for siting interim SNF facilities is presented. In the first stage, the land area is discretized into grids of uniform size (e.g., 100m x 100m grids). For the continental United States, this process resulted in a data matrix of about 700 million cells. Each cell of the matrix is then characterized as a binary decision variable to indicate whether an exclusion criterion is satisfied or not. A binary data matrix is created for each of the 25 siting criteria considered in this study. Using map algebra approach, cells that satisfy all criteria are clustered and regarded as potential siting areas. In the second stage, an optimization problem is formulated as a p-median problem on a rail network such that the sum of the shortest distance between nuclear power plants with SNF and the potential storage sites from the first stage is minimized. The implications of obtained results for energy policies are presented and discussed.

  6. Technologies for integrating wind farms to the grid. (Interim Report)

    Energy Technology Data Exchange (ETDEWEB)

    Chondrogiannis, Stamatios; Barnes, Mike [Univ. of Manchester, Manchester (United Kingdom); Aten, M [AREVA T and D Technology Centre, Paris, (France)

    2006-02-28

    -through, reactive power and voltage control capability. In the case of a DC connection to shore, the performance of the wind farm as seen at the PoC depends mostly on the inherent technical capabilities of the employed DC technology. Doubly-Fed Induction Generators (DFIGs) have been extensively researched and the capability of DFIGs to comply with the requirements for power quality is well documented. In cases where the electrical distance between the wind farm and the PoC is large, the use of a static and/or dynamic reactive compensation device may be necessary in order that the required reactive power capability of the farm is satisfied, as measured at the PoC. System frequency control has been demonstrated in the Horns Rev wind farm by appropriate blade pitch angle control of the individual wind turbines. Fault ride through capability is starting to be demonstrated in the public domain through simulations and site tests. However, there is a lack of information on the impact of a wind farm comprising DFIG wind turbines on the existing network under transient and fault conditions. A wind farm comprised of Fixed Speed Induction Generators (FSIGs) and connected to the grid with an AC connection without dynamic VAr compensation, cannot meet the new requirements of the Grid Code. Particular issues are voltage control and the supply of reactive power to the network during faults, and here the use of a dynamic reactive compensation device can significantly enhance the wind farm's technical capabilities. Frequency control can be provided by a wind farm with FSIG wind turbines when they possess blade angle controllers. For transient stability, recent research shows that a combination of improved machine design and supplementary controls during faults can aid fault ride through capability but this must be coordinated with Grid Code requirements for post-fault real power output recovery. Still, further work is needed for an assessment of the impact of a STATCOM's rating and

  7. Maywood Interim Storage Site: Annual site environmental report, Maywood, New Jersey, Calendar year 1986: Formerly Utilized Sites Remedial Action Program

    International Nuclear Information System (INIS)

    During 1986, the environmental monitoring program was continued at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. The MISS is presently used for the storage of low-level radioactively contaminated soils. The MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action and environmental monitoring programs are being conducted at this site and at vicinity properties by Bechtel National, Inc., Project Management Contractor for FUSRAP. The monitoring program at the MISS measures thoron and radon gas concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/y) and to assess the potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, the maximally exposed individual would receive an annual external exposure approximately equivalent to 1% of the DOE radiation protection standard of 100 mrem/y. This exposure is less than the exposure a person would receive during a round-trip flight from New York to Los Angeles (due to greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of the MISS that would result from radioactive materials present at the site would be indistinguishable from the dose the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the MISS is in compliance with the DOE radiation protection standard. 16 refs., 8 figs., 15 tabs

  8. Development and implementation of a NATO-wide state-of-the-art interim geospatial intelligence support tool

    Science.gov (United States)

    Teufert, John F.

    2004-09-01

    In order to enhance operational planning capabilities of the NATO Force Headquarters (KFOR, SFOR, ISAF), the NC3A Geo Team has developed a web-based interim geospatial intelligence support tool (IGEOSIT). The NC3A IGEOSIT displays geospatial data, such as digital topographic maps and satellite/air photo imagery, together with selectable overlay objects retrieved from distributed operational databases (DBs), for example minefields, bridges, culverts and military units. The NC3A IGEOSIT is a state-of-the-art web-based and Java-based multi-tier solution consisting of applications distributed over multiple servers within each Force HQ. The IGEOSIT provides advanced GIS terrain analysis capabilities based on the available Geo-data, including line-of-sight, 3-D perspective views, terrain profiles, and the definition of go/no-go areas. The system also performs vector-based route analysis and enhances the real-time tracking capabilities of mobile vehicles and troops. The IGEOSIT analyzes overlay data sets according to their attributes and dependencies in order to highlight otherwise hidden spatial relations that may be critical for mission planning. After performing geospatial analysis, the system compiles maps automatically to provide the user with immediate hard copy results, according to NATO standards, if necessary. The successful implementation of the IGEOSIT currently provides all NATO FORCE HQ staff members with a common operational picture of the theatre. This ensures that a common set of recently-updated information overlays forms the basis for all operational decisions. This paper describes the architecture, technology, performance tests (including test environment, analysis and measurement tools, hardware, selected test scenarios and results) and the lessons learned implementing advanced network and Java-based multi-tier solutions within the NATO Force Headquarters.

  9. 77 FR 46127 - Interim Staff Guidance on Changes to the Generic Aging Lessons Learned (GALL) Report Revision 2...

    Science.gov (United States)

    2012-08-02

    ... COMMISSION Interim Staff Guidance on Changes to the Generic Aging Lessons Learned (GALL) Report Revision 2... Learned (GALL) Report,'' and the NRC staff's aging management review procedure and acceptance criteria... learned and to address emergent issues not covered in license renewal guidance documents. In this way,...

  10. 75 FR 70114 - Amendment to the Interim Final Rules for Group Health Plans and Health Insurance Coverage...

    Science.gov (United States)

    2010-11-17

    ... most Internet search engines. Comments may be submitted anonymously. Department of Labor. Comments to... were published in the Federal Register on June 17, 2010 (75 FR 34538). Additionally, on September 20... FR 34538). Paragraph (a)(1)(ii) of the interim final regulations provides that if a group health...

  11. 33 CFR 96.360 - Interim Safety Management Certificate: what is it and when can it be used?

    Science.gov (United States)

    2010-07-01

    ... Certificate: what is it and when can it be used? 96.360 Section 96.360 Navigation and Navigable Waters COAST...? § 96.360 Interim Safety Management Certificate: what is it and when can it be used? (a) A responsible... 6 months. It may be issued to a U.S. vessel which meets the conditions of paragraph (a) of...

  12. Television as a Socialization Factor: Interim Results of a Study Concerning the Effects of Television Violence on Viewers' Behaviour

    Science.gov (United States)

    Kellner, Hella

    1978-01-01

    The results of the initial study suggested that the question of effects of television violence could be answered meaningfully only in the same context as the question of the social effect of television. Interim results reported here support this hypothesis. (Author)

  13. 78 FR 3039 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-06; Performing a...

    Science.gov (United States)

    2013-01-15

    ... guidance prior to its issuance formally for public comment. On October 26, 2012 (77 FR 65417), the NRC... COMMISSION Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-06; Performing a Tsunami, Surge, or Seiche Hazard Assessment AGENCY: Nuclear Regulatory Commission. ACTION: Japan...

  14. 25 CFR 39.1100 - Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously...

    Science.gov (United States)

    2010-04-01

    ... pre-kindergarten programs previously funded by the Bureau. 39.1100 Section 39.1100 Indians BUREAU OF...-kindergarten Programs § 39.1100 Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously funded by the Bureau. Those schools having pre-kindergarten programs funded fully or...

  15. 75 FR 53353 - Notice of Availability of Final Interim Staff Guidance Document No. 25 “Pressure and Helium...

    Science.gov (United States)

    2010-08-31

    ... COMMISSION Notice of Availability of Final Interim Staff Guidance Document No. 25 ``Pressure and Helium... Guidance Document No. 25 (ISG-25) ``Pressure and Helium Leakage Testing of the Confinement Boundary of... helium leakage testing and ASME Code required pressure (hydrostatic/pneumatic) testing that is...

  16. 75 FR 26981 - Notice of Establishment of Interim Final Supplementary Rules for Public Lands Managed by the...

    Science.gov (United States)

    2010-05-13

    ..., protect natural and cultural resources, improve recreational opportunities, and protect public health. All... safety concerns and resource protection needs within the management area. All of the interim final... Managed by the Mother Lode Field Office, California AGENCY: Bureau of Land Management, Interior....

  17. 77 FR 4492 - Endangered and Threatened Wildlife and Plants; Reissuance of Interim Special Rule for the Polar Bear

    Science.gov (United States)

    2012-01-30

    ... Wildlife Service the December 16, 2008, final special rule for the polar bear (73 FR 76249). The Court..., 2008 (73 FR 28306), shall remain in effect until superseded by the new special rule for the polar bear... the polar bear (73 FR 76249), the Court further ordered that, in its place, the interim final...

  18. 75 FR 8412 - Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of...

    Science.gov (United States)

    2010-02-24

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of... Sections 2.4.12 and 2.4.13 regarding the assessment of ground water flow and transport of...

  19. 76 FR 17159 - Office of New Reactors; Final Interim Staff Guidance on Standard Review Plan, Section 17.4...

    Science.gov (United States)

    2011-03-28

    .... SUMMARY: The NRC staff is issuing its Final Interim Staff Guidance (ISG) DC/COL-ISG-018 (Agencywide... of ] the design certification (DC) and combined license (COL) applications. The NRC staff issues DC/COL-ISGs to facilitate timely implementation of current staff guidance and to facilitate...

  20. 75 FR 16202 - Office of New Reactors; Interim Staff Guidance on Ensuring Hazard-Consistent Seismic Input for...

    Science.gov (United States)

    2010-03-31

    ...) DC/COL-ISG-017 titled ``Ensuring Hazard-Consistent Seismic Input for Site Response and Soil Structure..., and DC/COL-ISG-01, ``Interim Staff Guidance on Seismic Issues Associated with High Frequency Ground... No. ML081400293). The NRC staff issues DC/COL-ISGs to facilitate timely implementation of...

  1. Leading Curriculum Innovation in Primary Schools Project: An Interim Report on School Leaders' Roles in Curriculum Development in England

    Science.gov (United States)

    Brundrett, Mark; Duncan, Diane; Rhodes, Christopher

    2010-01-01

    This article provides an interim report on a two-phase study of curriculum innovation in primary schools in England during one of the most significant periods of change for the last two decades. More specifically, the study addresses the challenges to school leaders created by the Rose Review of the primary curriculum. This article presents and…

  2. 75 FR 8411 - Office of New Reactors: Interim Staff Guidance on Assessing the Consequences of an Accidental...

    Science.gov (United States)

    2010-02-24

    ... Gallagher at 301-492-3668; e-mail at Carol.Gallagher@nrc.gov . Mail comments to: Michael T. Lesar, Chief... on May 4, 2009 (74 FR 20510), on its Proposed Interim Staff Guidance (ISG) DC/ COL-ISG-013...

  3. 75 FR 13484 - Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA...

    Science.gov (United States)

    2010-03-22

    ... authorized by FTZ Board Orders 1347 (69 FR 52857, 8/30/04) and 1480 (71 FR 55422, 9/22/06), including notice in the Federal Register inviting public comment (75 FR 4344, January 27, 2010). The FTZ staff... Foreign-Trade Zones Board Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG...

  4. 76 FR 72006 - Draft Interim Staff Guidance: Evaluations of Uranium Recovery Facility Surveys of Radon and Radon...

    Science.gov (United States)

    2011-11-21

    ... COMMISSION Draft Interim Staff Guidance: Evaluations of Uranium Recovery Facility Surveys of Radon and Radon... Recovery Facility Surveys of Radon and Radon Progeny in Air and Demonstrations of Compliance with 10 CFR 20... that existing guidance does not sufficiently detail how the NRC staff reviews surveys of radon...

  5. 78 FR 33120 - Final Interim Staff Guidance LR-ISG-2011-04; Updated Aging Management Criteria for Reactor Vessel...

    Science.gov (United States)

    2013-06-03

    ... Internal Components for Pressurized Water Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Interim... Reactor Vessel Internal Components for Pressurized Water Reactors.'' This final LR-ISG revises the... components exposed to reactor coolant environments. ADDRESSES: Please refer to Docket ID NRC-2012-0070...

  6. Prognostic value of interim 18F-FDG PET/CT in diffuse large B-cell lymphoma

    Institute of Scientific and Technical Information of China (English)

    Zhitao Ying; Xuejuan Wang; Yuqin Song; Wen Zheng; Xiaopei Wang; Yan Xie; Ningjing Lin

    2013-01-01

    Diffuse large B-cell lymphoma (DLBCL) is a heterogeneous disease.The prognostic factor currently used is not accurate enough to predict the outcomes of patients with DLBCL.The prognostic significance of interim PET/CT in DLBCL remains controversial.The aim of this study is to determine the predictive value of interim 18F-FDG PET/CT after first-line treatment in patients with DLBCL.Methods:Thirty-two patients with DLBCL underwent baseline,interim and post-treatment 18F-FDG PET/CT scans.Imaging results were analyzed for the survival of patients via software SPSS 13.0,retrospectively.Results:Thirty-one of the 32 patients were treated with R-CHOP regimen,and interim 18F-FDG PET/CT of 24 patients was performed after 2 cycles of treatment.After a median follow-up period of 16.7 months,the 2-year progression-free survival (PFS) rates were significandy different between the groups above and below SUVmax cut-off value of 2.5 (P=0.039).No significant differences were found in the 2-year PFS rates if SUVmax cut-offvalues were set as 2.0 and 3.0,respectively (P=0.360; P=0.113).Conclusions:Interim PET/CT could predict the prognosis of DLBCL patients with the SUVmax cut-off value of 2.5,but more clinical data should be concluded to confirm this conclusion.

  7. Exemption of radiation sources and practices from regulatory control: Interim report

    International Nuclear Information System (INIS)

    This document is an interim report on progress at the IAEA on exemption principles and their application to low-level radioactive waste disposal. In the first part of the document the general principles for the exemption of radiation sources and practices from regulatory control are described. The exempt quantities of low-level radioactive wastes for disposal to municipal landfill or by incineration including methods for their derivation and generic values are contained in the second part of the document. In the appendices the individual effective dose equivalents and committed effective dose equivalents by pathway for waste concentrations of 1 Bq.g-1 and some quoted limits from the literature on dust concentrations at the outlet of municipal waste incinerators are estimated

  8. PROJECT W-551 SUMMARY INFORMATION FOR EARLY LAW INTERIM PRETREATMENT SYSTEM SELECTION

    Energy Technology Data Exchange (ETDEWEB)

    AR, TEDESCHI

    2008-08-11

    This report provides summary data for use by the decision board to assess and select the final technology for project W-551, Interim Pretreatment System. This project will provide early pretreated low activity waste feed to the Waste Treatment Plant to allow Waste Treatment Plan Low Activity Waste facility operation prior to construction completion of the Pretreatment and High Level Waste facilities. The candidate solids separations technologies are rotary microfiltration and crossflow filtration, and the candidate cesium separation technologies are fractional crystallization, caustic-side solvent extraction, and ion-exchange using spherical resorcinol-fonnaldebyde resin. This document provides a summary of comparative data against prior weighted criteria to support technology selection. Supporting details and background for this summary are documented in the separate report, RPP-RPT-37741.

  9. Interim-status groundwater monitoring plan for the 216-B-63 trench. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Sweeney, M.D.

    1995-06-13

    This document outlines the groundwater monitoring plan for interim-status detection-level monitoring of the 216-B-63 Trench. This is a revision of the initial groundwater monitoring plan prepared for Westinghouse Hanford Company (WHC) by Bjornstad and Dudziak (1989). The 216-B-63 Trench, located at the Hanford Site in south-central Washington State, is an open, unlined, earthern trench approximately 1.2 m (4 ft) wide at the bottom, 427 m (1400 ft) long, and 3 m (10 ft) deep that received wastewater containing hazardous waste and radioactive materials from B Plant, located in the 200 East Area. Liquid effluent discharge to the 216-B-63 Trench began in March 1970 and ceased in February 1992. The trench is now managed by Waste Tank Operations.

  10. Cost of implementing AECB interim criteria for the closeout of uranium tailings sites

    International Nuclear Information System (INIS)

    The main purpose of this study was to arrive at a gross approximation of the costs to the Canadian uranium mining industry of meeting the proposed closeout criteria established by the Atomic Energy Control Board for tailings deposits. Two options have been investigated: on-land disposal and underlake disposal. Given the budget allocated to the study, the estimates must be understood as approximations. Overall cost figures for the Canadian uranium mining industry are linear extensions from a hypothetical base case. The results of a conference held in Ottawa on February 25 and 26 to discuss the proposed AECB interim criteria for the closeout of uranium tailings sites are also included. Representatives from mining firms, provincial regulatory authorities, universities and the Atomic Energy Control board attended the conference

  11. PROJECT W-551 DETERMINATION DATA FOR EARLY LAW INTERIM PRETREATMENT SYSTEM SELECTION

    Energy Technology Data Exchange (ETDEWEB)

    TEDESCHI AR

    2008-08-11

    This report provides the detailed assessment forms and data for selection of the solids separation and cesium separation technology for project W-551, Interim Pretreatment System. This project will provide early pretreated low activity waste feed to the Waste Treatment Plant to allow Waste Treatment Plan Low Activity Waste facility operation prior to construction completion of the Pretreatment and High Level Waste facilities. The candidate solids separations technologies are rotary microfiltration and crossflow filtration, and the candidate cesium separation technologies are fractional crystallization, caustic-side solvent extraction, and ion-exchange using spherical resorcinol-formaldehyde resin. This data was used to prepare a cross-cutting technology summary, reported in RPP-RPT-37740.

  12. Manipulation of natural subsurface processes: Field research and validation. Interim report

    International Nuclear Information System (INIS)

    Often the only alternative for treating deep subsurface contamination is in situ manipulation of natural processes to change the mobility or form of contaminants. However, the complex interactions of natural subsurface physical, chemical, and microbial processes limit the predictability of the system-wide impact of manipulation based on current knowledge. This report is a summary of research conducted to examine the feasibility of controlling the oxidation-reduction (redox) potential of the unconfined aquifer at the Hanford Site in southeastern Washington State by introducing chemical reagents and microbial nutrients. The experiment would allow the testing of concepts and hypotheses developed from fundamental research in the US Department of Energy's (DOE's) Subsurface Science Program. Furthermore, the achievement of such control is expected to have implications for in situ remediation of dispersed aqueous contaminants in the subsurface environment at DOE sites nationwide, and particularly at the Hanford Site. This interim report summarizes initial research that was conducted between July 1990 and October 1991

  13. 40 CFR 265 interim-status ground-water monitoring plan for the 2101-M pond

    International Nuclear Information System (INIS)

    This report outlines a ground-water monitoring plan for the 2101-M pond, located in the southwestern part of the 200-East Area on the Hanford Site in south-central Washington State. It has been determined that hazardous materials may have been discharged to the pond. Installation of an interim-status ground-water monitoring system is required under the Resource Conservation and Recovery Act to determine if hazardous chemicals are moving out of the pond. This plan describes the location of new wells for the monitoring system, how the wells are to be completed, the data to be collected, and how those data can be used to determine the source and extent of any ground-water contamination from the 2101-M pond. Four new wells are planned, one upgradient and three downgradient. 35 refs., 12 figs., 9 tabs

  14. Electric car design. Interim summary report, Phase I: deliverable item 9

    Energy Technology Data Exchange (ETDEWEB)

    1977-05-09

    The work included in this Interim Summary Report is part of the Electric Car Program, the goal of which is to develop by 1979 a totally new electric car with substantially improved performance over those electric cars available in 1976. The rationale used in designing a four-passenger electric car for use in an urban environment is presented. The approach taken was to design an electric car utilizing current technology. On the basis of tradeoff analyses, upgrading improvements were identified which would permit the electric car to more nearly meet all of the ERDA near-term goals. The electric car design, including the chassis, drive train, major components, and the control are summarized. The Phase I electric car design will meet many of the ERDA near-term goals. Upgrading development programs are identified which, when incorporated in Phase II vehicle development, will result in upgraded performance, which essentially meets ERDA's near-term goals.

  15. Interim report on updated microarray probes for the LLNL Burkholderia pseudomallei SNP array

    Energy Technology Data Exchange (ETDEWEB)

    Gardner, S; Jaing, C

    2012-03-27

    The overall goal of this project is to forensically characterize 100 unknown Burkholderia isolates in the US-Australia collaboration. We will identify genome-wide single nucleotide polymorphisms (SNPs) from B. pseudomallei and near neighbor species including B. mallei, B. thailandensis and B. oklahomensis. We will design microarray probes to detect these SNP markers and analyze 100 Burkholderia genomic DNAs extracted from environmental, clinical and near neighbor isolates from Australian collaborators on the Burkholderia SNP microarray. We will analyze the microarray genotyping results to characterize the genetic diversity of these new isolates and triage the samples for whole genome sequencing. In this interim report, we described the SNP analysis and the microarray probe design for the Burkholderia SNP microarray.

  16. Adjustable Autonomy and Human-Agent Teamwork in Practice: An Interim Report on Space Applications

    Science.gov (United States)

    Bradshaw, Jeffrey M.; Feltovich, Paul; Hoffman, Robert; Jeffers, Renia; Suri, Niranhan; Uszok, Andrzej; VanHoof, Ron; Acquisti, Alessandro; Prescott, Debbie

    2003-01-01

    We give a preliminary perspective on the basic principles and pitfalls of adjustable autonomy and human-centered teamwork. We then summarize the interim results of our study on the problem of work practice modeling and human-agent collaboration in space applications, the development of a broad model of human-agent teamwork grounded in practice, and the integration of the Brahms, KAoS, and NOMADS agent frameworks. We hope our work will benefit those who plan and participate in work activities in a wide variety of space applications, as well as those who are interested in design and execution tools for teams of robots that can function as effective assistants to humans.

  17. 40 CFR 265 interim-status ground-water monitoring plan for the 2101-M pond

    Energy Technology Data Exchange (ETDEWEB)

    Chamness, M.A.; Luttrell, S.P.; Dudziak, S.

    1989-03-01

    This report outlines a ground-water monitoring plan for the 2101-M pond, located in the southwestern part of the 200-East Area on the Hanford Site in south-central Washington State. It has been determined that hazardous materials may have been discharged to the pond. Installation of an interim-status ground-water monitoring system is required under the Resource Conservation and Recovery Act to determine if hazardous chemicals are moving out of the pond. This plan describes the location of new wells for the monitoring system, how the wells are to be completed, the data to be collected, and how those data can be used to determine the source and extent of any ground-water contamination from the 2101-M pond. Four new wells are planned, one upgradient and three downgradient. 35 refs., 12 figs., 9 tabs.

  18. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear and Industrial Safety Agency (NISA: which prepares necessary regulations for Spent Fuel Interim Storage Facilities). In 2010 fiscal year, JNES completed technical evaluation of the standard (prepared by Atomic Energy Society of Japan) used for the storage facility (dual purpose cask system) being constructed in Mutsu-City and R and D for UT test of welded canister lids which is required for concrete cask storage facilities. And also, JNES is preparing dynamic test of spent fuel to examine the integrity of spent fuel at cask drop accidents and PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. The results of these tests will be reported in 2011 and 2012 fiscal year. (author)

  19. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear and Industrial Safety Agency (NISA: which prepares necessary regulations for Spent Fuel Interim Storage Facilities). In 2011 fiscal year, JNES carried out R and D for UT test of welded canister lids which is required for concrete cask storage facilities. And also, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel at cask drop accidents and PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be carried out in 2012 fiscal year and after. (author)

  20. Guidelines on interim performance constraints for radioactive waste disposal in crystalline rock

    International Nuclear Information System (INIS)

    Interim performance constraints have been developed for preliminary design analyses of a radioactive waste repository in crystalline rock. The approach taken in defining these constraints was to consider the thermal, thermomechanical, and thermochemical beavior for three regions of the repository (very-near field, near field, and far field) during three time periods (operational, containment, and isolation). Physical, thermal, and mechanical limits are proposed. These may be required to support the repository performance objectives defined by the US Nuclear Regulatory Commission in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, in particular those related to barrier performance after permanent closure (10 CFR 60.113). The performance constraints represent the informed judgment of a Working Group whose members are knowledgeable in matters relating to design of a repository in crystalline rock. The constraints are intended for use in early design studies and will be revised as analytical and experimental information to support revision becomes available

  1. Update: Interim Guidance for Prevention of Sexual Transmission of Zika Virus--United States, 2016.

    Science.gov (United States)

    Oster, Alexandra M; Russell, Kate; Stryker, Jo Ellen; Friedman, Allison; Kachur, Rachel E; Petersen, Emily E; Jamieson, Denise J; Cohn, Amanda C; Brooks, John T

    2016-04-01

    CDC issued interim guidance for the prevention of sexual transmission of Zika virus on February 5, 2016. The following recommendations apply to men who have traveled to or reside in areas with active Zika virus transmission and their female or male sex partners. These recommendations replace the previously issued recommendations and are updated to include time intervals after travel to areas with active Zika virus transmission or after Zika virus infection for taking precautions to reduce the risk for sexual transmission. This guidance defines potential sexual exposure to Zika virus as any person who has had sex (i.e., vaginal intercourse, anal intercourse, or fellatio) without a condom with a man who has traveled to or resides in an area with active Zika virus transmission. This guidance will be updated as more information becomes available.

  2. Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2. GSFLS visit findings and evaluations. Interim report

    International Nuclear Information System (INIS)

    This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This report describes a global framework that evaluates spent fuel disposition requirements, influencing factors and strategies. A broad sampling of foreign governmental officials, electric utility spokesmen and nuclear power industry officials responsible for GSFLS policies, plans and programs were surveyed as to their views with respect to national and international GSFLS related considerations. The results of these GSFLS visit findings are presented herein. These findings were then evaluated in terms of technical, institutional and legal/regulatory implications. The GSFLS evaluations, in conjunction with perceived US spent fuel objectives, formed the basis for selecting a set of GSFLS strategies which are reported herein

  3. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 3

    International Nuclear Information System (INIS)

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second such assessment was completed in 1984 and is documented in the Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1-4. This, the third volume of the report, summarizes the pre-closure environmental and safety assessments completed by Ontario Hydro for Atomic Energy of Canada Limited. The preliminary results and their sigificance are discussed. 85 refs

  4. Deep Vadose Zone Treatability Test for the Hanford Central Plateau: Interim Post-Desiccation Monitoring Results

    Energy Technology Data Exchange (ETDEWEB)

    Truex, Michael J.; Oostrom, Martinus; Strickland, Christopher E.; Johnson, Timothy C.; Johnson, Christian D.; Clayton, Ray E.; Chronister, Glen B.

    2013-09-01

    A field test of desiccation is being conducted as an element of the deep vadose zone treatability test program. Desiccation technology relies on removal of water from a portion of the subsurface such that the resultant low moisture conditions inhibit downward movement of water and dissolved contaminants. Previously, a field test report (Truex et al. 2012a) was prepared describing the active desiccation portion of the test and initial post-desiccation monitoring data. Additional monitoring data have been collected at the field test site during the post-desiccation period and is reported herein along with interpretation with respect to desiccation performance. This is an interim report including about 2 years of post-desiccation monitoring data.

  5. The interim storage facility with dry storage casks and its safeguards activity

    International Nuclear Information System (INIS)

    Recyclable-Fuel Storage Company (RFS) is constructing an interim storage facility of spent fuel at Recyclable-Fuel Storage Center (RFSC) in Aomori Prefecture. Metallic dry casks are employed to contain the spent fuel from nuclear power plants and to serve for about 50 years in RFSC. Metallic dry casks have already been used for dry cask storage facility at Tokai No.2 power station of Japan Atomic Power Company. But, RFSC is not exactly the same as the dry cask storage facility at Tokai No.2 power station, for example, cask transportation between facilities and no hot cells. Therefore, additional safeguards activities are necessary. The outline of the design and handling of metallic dry casks at RFSC and the currently developing status of safeguards activity such as containment and surveillance for the cask receipt and storage at RFSC, etc are described. (author)

  6. The dry storage cask in interim storage facility and safeguards activity

    International Nuclear Information System (INIS)

    The Japan Atomic Power Company (JAPC) is preparing for interim storage of spent fuel at Recyclable-Fuel Storage Center (RFSC) in Aomori Prefecture. Metallic dry casks are employed to contain the spent fuel and to serve for about 50 years in RFSC. Metallic dry casks have already been used for spent fuel dry storage at Tokai No.2 power station. But, RFSC is not exactly the same as the dry storage facility in Tokai No.2 power station, for example, casks are transported out side of the reactor site and RFSC has no fuel handling system. Therefore, additional implementation of safeguards is necessary. This report introduces the design and handling of metallic dry casks for RFSC and the currently developing status of the safeguards activity such as containment and surveillance for the fuel loading at the power station, the cask receipt and storage at RFSC, etc. (author)

  7. Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Klett, R.D.

    1997-06-01

    The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs.

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

    International Nuclear Information System (INIS)

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

  9. Update: Interim Guidance for Prevention of Sexual Transmission of Zika Virus--United States, 2016.

    Science.gov (United States)

    Oster, Alexandra M; Russell, Kate; Stryker, Jo Ellen; Friedman, Allison; Kachur, Rachel E; Petersen, Emily E; Jamieson, Denise J; Cohn, Amanda C; Brooks, John T

    2016-01-01

    CDC issued interim guidance for the prevention of sexual transmission of Zika virus on February 5, 2016. The following recommendations apply to men who have traveled to or reside in areas with active Zika virus transmission and their female or male sex partners. These recommendations replace the previously issued recommendations and are updated to include time intervals after travel to areas with active Zika virus transmission or after Zika virus infection for taking precautions to reduce the risk for sexual transmission. This guidance defines potential sexual exposure to Zika virus as any person who has had sex (i.e., vaginal intercourse, anal intercourse, or fellatio) without a condom with a man who has traveled to or resides in an area with active Zika virus transmission. This guidance will be updated as more information becomes available. PMID:27032078

  10. Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2. GSFLS visit findings and evaluations. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-31

    This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This report describes a global framework that evaluates spent fuel disposition requirements, influencing factors and strategies. A broad sampling of foreign governmental officials, electric utility spokesmen and nuclear power industry officials responsible for GSFLS policies, plans and programs were surveyed as to their views with respect to national and international GSFLS related considerations. The results of these GSFLS visit findings are presented herein. These findings were then evaluated in terms of technical, institutional and legal/regulatory implications. The GSFLS evaluations, in conjunction with perceived US spent fuel objectives, formed the basis for selecting a set of GSFLS strategies which are reported herein.

  11. Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996

    Energy Technology Data Exchange (ETDEWEB)

    None

    1997-05-06

    OAK A271 Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996. The Rockwell International Hot Laboratory (RIHL) is one of a number of former nuclear facilities undergoing decontamination and decommissioning (D&D) at the Santa Susana Field Laboratory (SSFL). The RIHL facility is in the later stages of dismantlement, with the final objective of returning the site location to its original natural state. This report documents the decontamination and dismantlement activities performed at the facility over the time period 1988 through 1996. At this time, the support buildings, all equipment associated with the facility, and the entire above-ground structure of the primary facility building (Building 020) have been removed. The basement portion of this building and the outside yard areas (primarily asphalt and soil) are scheduled for D&D activities beginning in 1997.

  12. Interim Status Closure Plan Open Burning Treatment Unit Technical Area 16-399 Burn Tray

    Energy Technology Data Exchange (ETDEWEB)

    Vigil-Holterman, Luciana R. [Los Alamos National Laboratory

    2012-05-07

    This closure plan describes the activities necessary to close one of the interim status hazardous waste open burning treatment units at Technical Area (TA) 16 at the Los Alamos National Laboratory (LANL or the Facility), hereinafter referred to as the 'TA-16-399 Burn Tray' or 'the unit'. The information provided in this closure plan addresses the closure requirements specified in the Code of Federal Regulations (CFR), Title 40, Part 265, Subparts G and P for the thermal treatment units operated at the Facility under the Resource Conservation and Recovery Act (RCRA) and the New Mexico Hazardous Waste Act. Closure of the open burning treatment unit will be completed in accordance with Section 4.1 of this closure plan.

  13. Variability of Iberian upwelling implied by ERA-40 and ERA-Interim reanalyses

    Directory of Open Access Journals (Sweden)

    José M. R. Alves

    2013-05-01

    Full Text Available The Regional Ocean Modeling System ocean model is used to simulate the decadal evolution of the regional waters in offshore Iberia in response to atmospheric fields given by ECMWF ERA-40 (1961–2001 and ERA-Interim (1989–2008 reanalyses. The simulated sea surface temperature (SST fields are verified against satellite AVHRR SST, and they are analysed to characterise the variability and trends of coastal upwelling in the region. Opposing trends in upwelling frequency are found at the northern limit, where upwelling has been decreasing in recent decades, and at its southern edge, where there is some evidence of increased upwelling. These results confirm previous observational studies and, more importantly, indicate that observed SST trends are not only due to changes in radiative or atmospheric heat fluxes alone but also due to changes in upwelling dynamics, suggesting that such a process may be relevant in climate change scenarios.

  14. Ultrasonic Characterization of Cast Austenitic Stainless Steel Microstructure: Discrimination between Equiaxed- and Columnar-Grain Material – An Interim Study

    Energy Technology Data Exchange (ETDEWEB)

    Ramuhalli, Pradeep; Good, Morris S.; Diaz, Aaron A.; Anderson, Michael T.; Watson, Bruce E.; Peters, Timothy J.; Dixit, Mukul; Bond, Leonard J.

    2009-10-27

    Ultrasonic nondestructive evaluation (NDE) and inspection of cast austenitic stainless steel (CASS) components used in the nuclear power industry is neither as effective nor reliable as is needed due to detrimental effects upon the interrogating ultrasonic beam and interference from ultrasonic backscatter. The root cause is the coarse-grain microstructure inherent to this class of materials. Some ultrasonic techniques perform better for particular microstructural classifications and this has led to the hypothesis that an ultrasonic inspection can be optimized for a particular microstructural class, if a technique exists to reliably classify the microstructure for feedback to the inspection. This document summarizes scoping experiments of in-situ ultrasonic methods for classification and/or characterization of the material microstructures in CASS components from the outside surface of a pipe. The focus of this study was to evaluate ultrasonic methods and provide an interim report that documents results and technical progress. An initial set of experiments were performed to test the hypothesis that in-service characterization of cast austenitic stainless steel (CASS) is feasible, and that, if reliably performed, such data would provide real-time feedback to optimize in-service inspections in the field. With this objective in mind, measurements for the experiment were restricted to techniques that should be robust if carried forward to eventual field implementation. Two parameters were investigated for their ability to discriminate between different microstructures in CASS components. The first parameter was a time-of-flight ratio of a normal incidence shear wave to that of a normal incidence longitudinal wave (TOFRSL). The ratio removed dependency on component thickness which may not be accurately reported in the field. The second parameter was longitudinal wave attenuation. The selected CASS specimens provided five equiaxed-grain material samples and five columnar

  15. Activities Related to Safety Regulations of Spent Fuel Interim Storage at Japan Nuclear Energy Safety Organization

    International Nuclear Information System (INIS)

    Major research activities in safety regulation of spent fuel interim storage at JNES are presented. In Japan, the first license application was approved by the government in May 2010 and the design and construction method will be submitted to the regulatory authority NISA soon. A commencement of its operation is expected at December 2012. In its plan, dual purpose metal casks for storage and transport will be stored in a concrete building for about 50 years, and then they will be transported to a spent fuel reprocessing facility. When they will be shipped out after the storage, no visual inspection for cask internals will be scheduled. Major reason of no visual inspection is to avoid any radiation exposure from contingent incident during opening the casks lid. JNES as TSO has conducted research activities to support NISA. Before the license application, those activities focused on three areas. The first area was to investigate fundamental safety function of the cask, that is, confinement, shielding, heat removal and subcriticality. Especially, a long term performance of the safety function was key issues. The second one was to confirm integrity of spent fuel cladding during the storage. The third one was to improves and verify the computer codes and/or methods for safety evaluation of the spent fuel interim storage facilities. In usual safety review process in Japan, NISA sometimes asks JNES to perform independent analysis and check the adequacy of the safety analysis conducted by licensees. After the approval of the license application, the applicant should have approvals of “design and construction method”, the welding inspection of the cask and the pre-service inspection. JNES is now supporting to prepare the criteria of the design and construction method. (author)

  16. Interim data monitoring to enroll higher-risk participants in HIV prevention trials

    Directory of Open Access Journals (Sweden)

    Umo-Otong John

    2009-06-01

    Full Text Available Abstract Background Lower-than-expected incidence of HIV undermines sample size calculations and compromises the power of a HIV prevention trial. We evaluated the effectiveness of interim monitoring of HIV infection rates and on-going modification of recruitment strategies to enroll women at higher risk of HIV in the Cellulose Sulfate Phase III study in Nigeria. Methods We analyzed prevalence and incidence of HIV and other sexually transmitted infections, demographic and sexual behavior characteristics aggregated over the treatment groups on a quarterly basis. The site investigators were advised on their recruitment strategies based on the findings of the interim analyses. Results A total of 3619 women were screened and 1644 enrolled at the Ikeja and Apapa clinics in Lagos, and at the Central and Peripheral clinics in Port Harcourt. Twelve months after study initiation, the overall incidence of HIV was less than one-third of the pre-study assumption, with rates of HIV that varied substantially between clinics. Due to the low prevalence and incidence rates of HIV, it was decided to close the Ikeja clinic in Lagos and to find new catchment areas in Port Harcourt. This strategy was associated with an almost two-fold increase in observed HIV incidence during the second year of the study. Conclusion Given the difficulties in estimating HIV incidence, a close monitoring of HIV prevalence and incidence rates during a trial is warranted. The on-going modification of recruitment strategies based on the regular analysis of HIV rates appeared to be an efficient method for targeting populations at greatest risk of HIV infection and increasing study power in the Nigeria trial. Trial Registration The trial was registered with the ClinicalTrials.gov registry under #NCT00120770 http://clinicaltrials.gov/ct2/show/NCT00120770

  17. Administrative simplification: adoption of operating rules for health care electronic funds transfers (EFT) and remittance advice transactions. Interim final rule with comment period.

    Science.gov (United States)

    2012-08-10

    This interim final rule with comment period implements parts of section 1104 of the Affordable Care Act which requires the adoption of operating rules for the health care electronic funds transfers (EFT) and remittance advice transaction. PMID:22888504

  18. Technical Note: A simple procedure for removing temporal discontinuities in ERA-Interim upper stratospheric temperatures for use in nudged chemistry-climate model simulations

    OpenAIRE

    McLandress, C.; D. A. Plummer; Shepherd, T. G.

    2013-01-01

    This note describes a simple procedure for removing unphysical temporal discontinuities in ERA-Interim upper stratospheric temperatures in March 1985 and August 1998 that have arisen due to changes in satellite radiance data used in the assimilation. The derived adjustments (offsets) to the global mean temperatures are suitable for use in chemistry-climate models that are nudged to ERA-Interim winds and temperatures. Simulations using a nudged version of the Canadian Middle Atmosphere ...

  19. Wabash River Basin comprehensive study covering reservoir sites on Embarrass River, Illinois and Clifty Creek and Patoka River, Indiana. Volume index. Volume I. Report. Interim report No. 2

    Energy Technology Data Exchange (ETDEWEB)

    1964-01-01

    The purpose of this interim report is to present comprehensive plans of development for reservoir sites on the Embarrass River, Clifty Creek and Patoka River for one or more of the following needs: flood control, water supply, water quality control and low flow augmentation, water recreation and general conservation of water and related resources. The projects presented in this interim report are compatible with comprehensive development of the water and related land resources of the Wabash River Basin currently being developed.

  20. Colonie Interim Storage Site environmental report for calendar year 1992, 1130 Central Avenue, Colonie, New York. Formerly Utilized Sites Remedial Action Program (FUSRAP)

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    This report describes the environmental surveillance program at the Colonie Interim Storage Site (CISS) and provides the results for 1992. The site is located in eastern New York State, approximately 6.4 km (4.0 mi) northwest of downtown Albany. From 1958 to 1984, National Lead (NL) Industries used the facility to manufacture various components from depleted and enriched uranium natural thorium. Environmental monitoring of CISS began in 1984 when Congress added, the site to the US Department of Energy`s (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental surveillance program at CISS includes sampling networks for external gamma radiation exposure and for thorium-232 and total uranium concentrations in surface water, sediment, and groundwater. Several chemical parameters are also measured in groundwater, including total metals, volatile organics, and water quality parameters. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements.