WorldWideScience

Sample records for 94-4 interim measures

  1. Burn site groundwater interim measures work plan.

    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.

    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. Radon measurements in schools: an interim report

    The report provides school officials, groups such as Parent-Teacher Associations, and other interested person with interim information on how to measure radon in schools and what to do if elevated levels are found. The first sections of the document contain facts about radon and the health risks associated with radon exposure. The next sections summarize what is known about radon in schools and provide guidance for conducting radon measurements. The last sections describe how to interpret the measurement results and suggest techniques that can be used to reduce radon concentrations if elevated levels are found

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

    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.

  5. 78 FR 290 - National Conference on Weights and Measures 98th Interim Meeting

    2013-01-03

    ... National Institute of Standards and Technology National Conference on Weights and Measures 98th Interim Meeting AGENCY: National Institute of Standards and Technology, Commerce. ACTION: Notice. SUMMARY: The 2013 Interim Meeting of the National Conference on Weights and Measures (NCWM) will be held January...

  6. 76 FR 81477 - National Conference on Weights and Measures 97th Interim Meeting

    2011-12-28

    ... National Institute of Standards and Technology National Conference on Weights and Measures 97th Interim Meeting AGENCY: National Institute of Standards and Technology, Commerce. ACTION: Notice. SUMMARY: The Interim Meeting of the 97th National Conference on Weights and Measures (NCWM) will be held January 22...

  7. 76 FR 540 - National Conference on Weights and Measures 2011 Interim Meeting

    2011-01-05

    ... National Institute of Standards and Technology National Conference on Weights and Measures 2011 Interim Meeting AGENCY: National Institute of Standards and Technology, Commerce. ACTION: Notice. SUMMARY: The National Conference on Weights and Measures (NCWM) 2011 Interim Meeting will be held January 23 to 26,...

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

    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

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

    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.

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

    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

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

    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

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

    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.

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

    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

  14. E-Area Performance Assessment Interim Measures Assessment FY2005

    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.

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

    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.

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

    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

  17. Interim remedial measures proposed plan for the 200-ZP-1 Operable Unit, Hanford Site, Washington

    The purpose of this interim remedial measures (IRM) proposed plan is to present and solicit public comments on the IRM planned for the 200-ZP-1 Operable Unit at the Hanford Site in Washington state. The 200-ZP-1 is one of two operable units that envelop the groundwater beneath the 200 West Area of the Hanford Site

  18. Interim indoor radon and radon decay-product measurement protocols

    The report provides EPA's procedures for measuring radon concentrations in houses with continuous radon monitors, charcoal canisters, alpha-track detectors, and grab radon techniques. It also provides procedures for measuring radon decay-product concentrations with a continuous-working-level monitor, a radon-progeny integrating sampling unit (RPISU), and grab radon decay-product methods. Specifications for the location of the measurement, the house conditions during the measurement, and minimum requirements for quality control are included in each procedure

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

    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

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

    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

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

    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.

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

    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

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

    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.

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

    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.

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

    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

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

    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.

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

    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

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

    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

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

    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.

  10. 9 CFR 94.4 - Cured or cooked meat from regions where rinderpest or foot-and-mouth disease exists.

    2010-01-01

    ... regulations in 9 CFR 327.2; must meet all other applicable requirements of the Federal Meat Inspection Act and regulations thereunder (9 CFR Chapter III); and must have been approved by the Administrator in accordance... where rinderpest or foot-and-mouth disease exists. 94.4 Section 94.4 Animals and Animal Products...

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

    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

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

    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.

  13. CMM Interim Check (U)

    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.

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

    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...

  15. Measurement techniques and instruments suitable for life-prediction testing of photovoltaic arrays. Interim report

    Noel, G.T.; Sliemers, F.A.; Deringer, G.C.; Wood, V.E.; Wilkes, K.E.; Gaines, G.B.; Carmichael, D.C.

    1978-01-15

    The validation of a service life of 20 years for low-cost photovoltaic arrays must be accomplished through accelerated life-prediction tests. A methodology for such tests has been developed in a preceding study. The results discussed consist of the initial identification and assessment of all known measurement techniques and instruments that might be used in these life-prediction tests. Array failure modes, relevant materials property changes, and primary degradation mechanisms are discussed as a prerequisite to identifying suitable measurement techniques and instruments. Candidate techniques and instruments are identified on the basis of extensive reviews of published and unpublished information. These methods are organized in six measurement categories--chemical, electrical, optical, thermal, mechanical, and ''other physicals''. Using specified evaluation criteria, the most promising techniques and instruments for use in life-prediction tests of arrays are then selected. These recommended techniques and their characteristics are described. Recommendations are made regarding establishment of the adequacy, particularly with respect to precision, of the more fully developed techniques for this application, and regarding the experimental evaluation of promising developmental techniques. Measurement needs not satisfied by presently available techniques/instruments are also identified.

  16. Iodine partition coefficient measurements at simulated PWR steam generator conditions: Interim data report

    Iodine partition coefficients (defined as the ratio of the concentration of iodine species in the aqueous solution to the iodine concentration in the vapor phase) were measured at simulated PWR steam generator conditions (2850C and 6.9 MPa), using carrier-free radioactive 131I in the form of sodium iodide. The iodine tracer concentration was maintained at ∼6 x 10-11 mol/L; boric acid concentration was varied from 0 to 0.4 mol/L; and the solution pH (measured at 250C) was adjusted from 4 to 9 by the addition of lithium hydroxide. Iodine partition coefficients decrease with increasing boric acid concentration; however, the iodine volatility is essentially independent of the solution pH for a given boric acid concentration. Sparging the solutions with air at room temperature increases the iodine volatility by an order of magnitude, compared to that achieved with argon sparging. Iodine partition coefficient measurements ranged from a low of 200 (in 0.2 M boric acid sparged with air) to 400,000 (in purified water sparged with argon)

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

    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.

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

    Patrick, W.C.; Ballou, L.B.; Butkovich, T.R.

    1982-04-30

    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.

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

    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

  20. 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

    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

  1. Interim report

    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.

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

    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.

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

    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).

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

    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.

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

    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.

  6. CMM Interim Check Design of Experiments (U)

    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.

  7. 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)

    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)

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

    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

  9. Noble gas isotope measurements for spent nuclear fuel reprocessing. IAEA Task 90/0A211 interim report

    The nuclear fission of actinides in reactor fuel produces large quantities of Kr and Xe as fission products. Because of the high levels of fission Kr and Xe, sample collection and analysis of noble gases for spent fuel diagnostic measurements is a simple, straight-forward technique. In modern reprocessing plants with continuous dissolvers, it will not be possible to use traditional methods for isolating input batches of fuel. This study investigates the feasibility of using noble gas isotope abundance measurements (isotope correlation techniques - ICT) to solve safeguards requirements. Noble gas measurements might be able to provide an independent analysis of Pu contained within dissolves fuel, on an individual fuel assembly basis. The isotopic composition of Kr and Xe in spent fuel reflects both the composition (isotope abundance ratios) of the fission products and the effects of neutron capture on those fission products. We have reviewed the available literature for noble gas analyses of spent reactor fuel. While references are made to noble gas isotope correlations over the last 20 years, we have found little if any detailed analysis of large data sets. The literature search did find several useful reports. Of these papers, one is particularly useful for evaluating noble gas isotopic compositions. The ''Benchmark-paper'' (1) contains 54 Kr and 56 Xe isotopic composition analyses for 4 different reactors with a variety of fuel enrichment factors. Burnup ranges from 8000 to 37000 MWd/tU. Besides the noble gas measurements, a variety of other measurements are reported (actinides and fission products)

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

    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.

  11. Interim Storage Facility decommissioning. Final report

    Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

  12. Interim storage study report

    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.

  13. ETF interim design review

    A three-day ETF Interim Design Review was conducted on July 23-25, 1980, at the Sheraton Potomac Inn in Rockville, Maryland. The intent of the review was to provide a forum for an in-depth assessment and critique of all facets of the ETF design by members of the fusion community. The review began with an opening plenary session at which an overview of the ETF design was presented by D. Steiner, manager of the ETF Design Center, complemented by a physics overview by P.H. Rutherford, chairman of the ETF/INTOR Physics Committee. This was followed by six concurrent review sessions over the next day and a half. The review closed with a plenary session at which the Design Review Board presented its findings. This document consists of the viewgraphs for the opening plenary session and an edited version of the presentations made by Steiner and Rutherford

  14. 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

    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

  15. Interim Design Report

    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...

  16. Effects of Interim Assessments on the Achievement Gap: Evidence from an Experiment

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

    2015-01-01

    Motivated by the passage of the No Child Left Behind (NCLB) Act, all states operate accountability systems that measure and report school and student performance annually. The purpose of this study is to examine the effects of interim assessments on the achievement gap. The authors examine the impact of interim assessments throughout the…

  17. Ontario interim market

    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

  18. An Interim President Sets the Stage

    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…

  19. 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

    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.

  20. ITER Conceptual design: Interim report

    This interim report describes the results of the International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activities after the first year of design following the selection of the ITER concept in the autumn of 1988. Using the concept definition as the basis for conceptual design, the Design Phase has been underway since October 1988, and will be completed at the end of 1990, at which time a final report will be issued. This interim report includes an executive summary of ITER activities, a description of the ITER device and facility, an operation and research program summary, and a description of the physics and engineering design bases. Included are preliminary cost estimates and schedule for completion of the project

  1. Spent Fuel Behaviour During Interim Storage

    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

  2. Interim emergency preparedness and response plans

    One of the key components of Ontario Hydro's Dam Safety Program is the Emergency Preparedness and Response Plans (EPRP). Preparing such a plan is time consuming and costly. This paper presents a simplified approach to prepare preliminary or interim EPRPs. The interim EPRPs consist of only the most critical components namely notification plans, action plans and interim inundation maps. The interim inundation maps are developed using simplified methods, assumptions and techniques. They provide a conservative but realistic estimate of the flooding that could occur as a result of a dam breach. Interim EPRPs can be produced in a fraction of the time of full EPRPs and can therefore be implemented quickly. The process described in this paper represents a major saving in time over the production of full EPRP, yet it results in effective interim plans that can act as final plans for small dam owners who do not have the the resources to prepare a comprehensive plan. 5 refs., 4 figs

  3. SFAT geometry verification measurements at the TVO KPA-STORE. Interim report on Task FIN A563 of the Finnish Support Programme to IAEA Safeguards

    Experiments made for the confirmation of the measurement geometry of the Spent Fuel Attribute Tester (SFAT), performed in December 1992, are reported and analysed. The measurement geometry to be chosen for a commercial prototype can be confirmed to be close enough to the optimum and to give a satisfactory signal-to-noise ratio. The problems encountered during the determination of the signal-to-noise ratio of Cs137 peaks rise to recommendation of developing new algorithms for processing NaI(Tl) detector spectra. (orig.) (7 refs., 11 figs., 5 tabs.)

  4. Assessment of Methane and VOC Emissions on Select Upstream Oil and Gas Production Operations Using Remote Measurements, Interim Report on Recent Survey Studies

    Environmentally responsible development of oil and gas assets in the United States is facilitated by advancement of sector-specific air pollution emission measurement and modeling tools. Emissions from upstream oil and gas production are complex in nature due to the variety of e...

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

    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...

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

    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.

  7. Urgent recommendation. Interim report

    The Investigation Committee for Critical Accident at Uranium Processing Plant was founded immediately after the accident to investigate the cause of the accident and to establish measures to prevent the similar accident. On September 30, 1999 around 10:35, the Japan's first criticality accident occurred at JCO Co. Ltd. Uranium processing plant (auxiliary conversion plant) located at Tokai-mura Ibaraki-ken. The criticality continued on and off for approximately 20 hours after the first instantaneous criticality. The accident led the recommendation of tentative evacuation and sheltering indoors for residents living in the neighborhood. The serious exposure to neutrons happened to three workers. The dominant effect is dose due to neutrons and gamma rays from the precipitation tank. When the accident took place, three workers dissolved sequentially about 2.4 kg uranium powder with 18.8 % enrichment in the 10-litter bucket with nitric acid. The procedure of homogenization of uranium nitrate was supposed to be controlled using the shape-limited narrow storage column. Actually, however, the thick and large precipitation tank was used. As a result, about 16.6 kg of uranium was fed into the tank, which presumably caused criticality. The first notification by JCO was delayed and the following communication was not smooth. This led to the delay of correct understanding of the situation and made the initial proper response difficult, then followed by insufficient communication between the nation, prefecture, and local authority. Urgent recommendations were made on the following items; (1) Safety measures to be taken at the accident site, (2) health cares for residents and others, (3) Comprehensive safety securing at nuclear operators such as Establishment of the effective audit system, Safety education for employees and Qualification and licensing system, Safety related documents, etc. (4) Reconstruction of the government's safety regulations such as How safety regulation

  8. Urgent recommendation. Interim report

    Nakano, Masayuki [International Affairs and Safeguards Division, Atomic Energy Bureau, Science and Technology Agency, Tokyo (Japan)

    2000-12-01

    The Investigation Committee for Critical Accident at Uranium Processing Plant was founded immediately after the accident to investigate the cause of the accident and to establish measures to prevent the similar accident. On September 30, 1999 around 10:35, the Japan's first criticality accident occurred at JCO Co. Ltd. Uranium processing plant (auxiliary conversion plant) located at Tokai-mura Ibaraki-ken. The criticality continued on and off for approximately 20 hours after the first instantaneous criticality. The accident led the recommendation of tentative evacuation and sheltering indoors for residents living in the neighborhood. The serious exposure to neutrons happened to three workers. The dominant effect is dose due to neutrons and gamma rays from the precipitation tank. When the accident took place, three workers dissolved sequentially about 2.4 kg uranium powder with 18.8 % enrichment in the 10-litter bucket with nitric acid. The procedure of homogenization of uranium nitrate was supposed to be controlled using the shape-limited narrow storage column. Actually, however, the thick and large precipitation tank was used. As a result, about 16.6 kg of uranium was fed into the tank, which presumably caused criticality. The first notification by JCO was delayed and the following communication was not smooth. This led to the delay of correct understanding of the situation and made the initial proper response difficult, then followed by insufficient communication between the nation, prefecture, and local authority. Urgent recommendations were made on the following items; (1) Safety measures to be taken at the accident site, (2) health cares for residents and others, (3) Comprehensive safety securing at nuclear operators such as Establishment of the effective audit system, Safety education for employees and Qualification and licensing system, Safety related documents, etc. (4) Reconstruction of the government's safety regulations such as How safety

  9. Fusion Breeder Program interim report

    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

  10. Fusion Breeder Program interim report

    Moir, R.; Lee, J.D.; Neef, W.

    1982-06-11

    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.

  11. Addendum to IFMIF-CDA interim report

    During the second IFMIF-CDA Design Integration Workshop, the conceptual design and contents of 'IFMIF-CDA Interim Report' were examined and discussed at both general and group meetings. Based on these discussion, the final IFMIF-CDA Report will be modified from the 'Interim Report'. This report describes the outline of these modification. (author)

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

    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…

  13. 15 CFR 904.322 - Interim action.

    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...

  14. 7 CFR 1738.21 - Interim financing.

    2010-01-01

    ... followed: (1) Interim construction shall be conducted in accordance with RUS Bulletin 1738-2 and 7 CFR part... be covered by an Environmental Report prepared in accordance with 7 CFR part 1794 and approved by RUS... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1738.21 Section...

  15. Solid waste burial grounds interim safety analysis

    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

  16. Solid waste burial grounds interim safety analysis

    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.

  17. Something not written in Hatamura Investigation Committee interim report

    Hatamura Investigation Committee on the accident at Fukushima Daiichi Nuclear Power Station issued interim report. This article reviewed section 4-6 of interim report; problems of response to the accident, problems of hazard control measures and inappropriate precautionary measures against tsunami and severe accidents, and referred to something not written in the report; (1) whether core meltdown could be prevented by appropriate response to the accident?, (2) scope of evacuation area at the accident was too much underestimated and almost impossible to establish evacuation system in reality and (3) inappropriate design standard of tsunami. The report implied such conclusions; (1) almost no possibility to prevent core meltdown even without misjudgement after earthquake and tsunami, (2) almost impossible to establish evacuation system prepared for next accident with realistic cost and (3) request to revise design standard of tsunami based on latest knowledge and establish measures required from the standard. Preventive design against human errors was requisite for artificial system and safety engineering should be learned from experiences. Probability of accident occurrence at nuclear power station would be extremely low with safer design but damages suffered from reactor accident were widely different from other accidents and huge enough to be comparable to a large-scale natural disaster. Interim report proposed to prepare for actually possible accidents assuming continuation of reactor operation but most assured measure for next accident not to occur was obliged to stop the reactor operation. (T. Tanaka)

  18. 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

    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

  19. 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∗

    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。

  20. AGR-1 Data Qualification Interim Report

    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.

  1. Glass packages in interim storage

    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 % SiO2. 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

  2. Safety concept for interim storage facilities in Fukushima

    The Ministry of the Environment is planning to construct the Interim Storage Facility for soil and waste generated in Fukushima prefecture, due to the accident of Fukushima Daiichi Nuclear Power Plant. This paper describes the result of study for the safety concepts. Concrete components are estimation of soil/waste generation, soil characterization, structure and location of facilities, radioactive safety assessment, operational management, approach for transportation concept, basic principle of environmental conservation measures. (author)

  3. Radon Measurements in Schools: An Interim Report.

    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…

  4. 13 CFR 120.890 - Source of interim financing.

    2010-01-01

    ... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Source of interim financing. 120... Development Company Loan Program (504) Interim Financing § 120.890 Source of interim financing. A Project may use interim financing for all Project costs except the Borrower's contribution. Any source...

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

    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

    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 Ranges portion of the lower Russian River and its confluence with the...

  7. Interim and End States, Sellafield, United Kingdom

    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.

    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. Hitrex 1: an interim report on experimental and analytical work on BNL's zero power HTR

    Beynon, A.J.; Kitching, S.J.; Lewis, T.A.; Waterson, R.H.

    1972-06-15

    This report presents interim experimental and theoretical results for the BNL Hitrex reactor. Reactivity effects and thermal and fast reaction rate distributions have been measured. Preliminary analysis has been performed, and some initial comparisons between theory and experiments made. (auth)

  10. CANDU spent fuel dry storage interim technique

    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

    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. Methods Data Qualification Interim Report

    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 and 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.

  13. Interim Hanford Waste Management Plan

    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

  14. 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

    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.

  15. Interim Financial Reporting in Function of Proper Decision Makind

    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?

    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. Choosing a spent fuel interim storage system

    The Transnucleaire Group has developed different modular solutions to address spent fuel interim storage needs of NPP. These solutions, that are present in Europe, USA and Asia are metal casks (dual purpose or storage only) of the TN 24 family and the NUHOMS canister based system. It is not always simple for an operator to sort out relevant choice criteria. After explaining the basic designs involved on the examples of the TN 120 WWER dual purpose cask and the NUHOMS 56 WWER for WWER 440 spent fuel, we shall discuss the criteria that govern the choice of a given spent fuel interim storage system from the stand point of the operator. In conclusion, choosing and implementing an interim storage system is a complex process, whose implications can be far reaching for the long-term success of a spent fuel management policy. (author)

  18. Design review report FFTF interim storage cask

    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.

  19. Design review report FFTF interim storage cask

    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

  20. Transuranic storage and assay facility interim safety basis

    Porten, D.R., Fluor Daniel Hanford

    1997-02-12

    The Transuranic Waste Storage and Assay Facility (TRUSAF) Interim Safety Basis document provides the authorization basis for the interim operation and restriction on interim operations for the TRUSAF. The TRUSAF ISB demonstrates that the TRUSAF can be operated safely, protecting the workers, the public, and the environment. The previous safety analysis document TRUSAF Hazards Identification and Evaluation (WHC 1987) is superseded by this document.

  1. 200 Area Interim Storage Area Technical Safety Requirements

    The 200 Area Interim Storage Area Technical Safety Requirements define administrative controls and design features required to ensure safe operation during receipt and storage of canisters containing spent nuclear fuel. This document is based on the 200 Area Interim Storage Area, Annex D, Final Safety Analysis Report which contains information specific to the 200 Area Interim Storage Area

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

    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

  3. Loss of interim status (LOIS) under RCRA. RCRA Information Brief

    1992-09-01

    The Resource Conservation and Recovery Act (RCRA) requires owners and operators of facilities that treat store, or disposal of hazardous waste (TSDFs) to obtain an operating permit. Recognizing that it would take EPA many years to issue operating permits to all RCRA facilities, Congress created ``interim status`` under Section 3005(e) of the Act. Interim status allows facilities to operate under Subtitle C of RCRA until their permits are issued or denied. This information brief defines interim status and describes how failure to meet interim status requirements may lead to loss of interim status (LOIS).

  4. The EURATOM interim verification system of Natrium declarations

    Full text: Euratom's inspection scheme at the Thermal Oxide Reprocessing Plant THORP makes use of the Near Real Time Material Accountancy (NRTMA) tool developed by the operator to obtain In-Process Inventory (IPI) information in plutonium containing areas that are not accessible during operation. From a verification point of view, appropriate authentication of the data provided, NRTMA is sufficient to fulfil the timeliness component of the safeguards approach without further need to stop the process and carry out interim inventories, the flow component being covered by routine verification activities on a continuous inspection basis. Since commissioning time, the validation of the NRTMA process models, data collection methods, computational techniques and data transmission protocols has been the subject of extensive analyses and agreement procedures involving several departments of the Euratom Safeguards Office (ESO). The Terms of Reference regarding the use of NRTMA by E.S.O are recorded in the NRTMA Framework Document. In this context, the Data Evaluation Sector of ESO was assigned the task of studying the statistical models and anomaly resolutions tools used by NRTMA. The analysis rested on the description of a condensed operational process model and a related statistical model for the measurement errors and their propagation. It included the definition of particular testing variables suitable for safeguards anomaly detection and sensitivity studies based on Monte Carlo simulations. The conclusion of Euratom's statistical analysis was that, although BNFL's NRTMA data collection system is perfectly adequate for interim inventory data declaration, its anomaly detection margin, which was primarily designed to provide a very conservative process control tool, is too narrow for safeguards purposes. This high sensitivity, which, from the operator's point of view, may a desirable feature for taking early corrective action, would create a resource and efficiency problem

  5. LANDFILL BIOREACTOR PERFORMANCE, SECOND INTERIM REPORT

    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...

  6. 340 waste handling facility interim safety basis

    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.

  7. Disposal facility data for the interim performance

    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

  8. 12 CFR 268.505 - Interim relief.

    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,...

  9. 340 waste handling facility interim safety basis

    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

  10. ITER interim design report package documents

    This publication contains the Excerpt from the ITER Council (IC-8), the ITER Interim Design Report, Cost Review and Safety Analysis, ITER Site Requirements and ITER Site Design Assumptions and the Excerpt from the ITER Council (IC-9). 8 figs, 2 tabs

  11. 24 CFR 35.1330 - Interim controls.

    2010-04-01

    ...-lead hazards only if they effectively control access to areas with soil-lead hazards. Examples of land... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Interim controls. 35.1330 Section 35.1330 Housing and Urban Development Office of the Secretary, Department of Housing and...

  12. 7 CFR 1735.75 - Interim financing.

    2010-01-01

    ... preliminary approval from RUS. See § 1735.90 (g) See 7 CFR part 1737 for regulations on interim financing for... completed RUS Form 490, “Application for Telephone Loan or Loan Guarantee.” See 7 CFR part 1737. (3) The... on any investments in nonrural areas. See 7 CFR 1737. (4) The information required in § 1735.74...

  13. 78 FR 63276 - Interim Policy, FAA Review of Solar Energy System Projects on Federally Obligated Airports

    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....

  14. Interim storage facility for spent fuel

    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)

  15. Pathways to deep decarbonization - Interim 2014 Report

    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

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

    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)

  17. Gaz de France interim financial report 2007

    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.)

  18. Compilation of interim technical research memoranda. Volume I

    Four interim technical research memoranda are presented that describe the results of numerical simulations designed to investigate the dynamics of energetic plasma beams propagating across magnetic fields

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

    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.

  20. T Tank Farm Interim Cover Test - Design Plan

    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.

  1. The Homestake Interim Laboratory and Homestake DUSEL

    Lesko, Kevin T.

    2011-12-01

    The former Homestake gold mine in Lead South Dakota is proposed for the National Science Foundation's Deep Underground Science and Engineering Laboratory (DUSEL). The gold mine provides expedient access to depths in excess of 8000 feet below the surface (>7000 mwe). Homestake's long history of promoting scientific endeavours includes the Davis Solar Neutrino Experiment, a chlorine-based experiment that was hosted at the 4850 Level for more than 30 years. As DUSEL, Homestake would be uncompromised by competition with mining interests or other shared uses. The facility's 600-km of drifts would be available for conversion for scientific and educational uses. The State of South Dakota, under Governor Rounds' leadership, has demonstrated exceptionally strong support for Homestake and the creation of DUSEL. The State has provided funding totalling $46M for the preservation of the site for DUSEL and for the conversion and operation of the Homestake Interim Laboratory. Motivated by the strong educational and outreach potential of Homestake, the State contracted a Conversion Plan by world-recognized mine-engineering contractor to define the process of rehabilitating the facility, establishing the appropriate safety program, and regaining access to the facility. The State of South Dakota has established the South Dakota Science and Technology Authority to oversee the transfer of the Homestake property to the State and the rehabilitation and preservation of the facility. The Homestake Scientific Collaboration and the State of South Dakota's Science and Technology Authority has called for Letters of Interest from scientific, educational and engineering collaborations and institutions that are interested in hosting experiments and uses in the Homestake Interim Facility in advance of the NSF's DUSEL, to define experiments starting as early as 2007. The Homestake Program Advisory Committee has reviewed these Letters and their initial report has been released. Options for

  2. Site development interim removable dental prosthesis.

    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

  3. National NIF Diagnostic Program Interim Management Plan

    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

  4. Central waste complex interim safety basis

    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

  5. Central waste complex interim safety basis

    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.

  6. National NIF Diagnostic Program Interim Management Plan

    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

  7. Interim Reliability Evaluation Program procedures guide

    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

  8. The Federal interim storage facility for radioactive waste under construction

    A short description of the design of the Federal interim storage facility for radioactive waste, the security aspects and the storage material is given. The interim storage facility is currently under construction in Wuerenlingen at the Paul Scherrer Institute. figs., tabs., 27 refs

  9. Transuranic waste storage and assay facility (TRUSAF) interim safety basis

    The TRUSAF ISB is based upon current facility configuration and procedures. The purpose of the document is to provide the basis for interim operation or restrictions on interim operations and the authorization basis for the TRUSAF at the Hanford Site. The previous safety analysis document TRUSAF hazards Identification and Evaluation (WHC 1977) is superseded by this document

  10. 47 CFR 51.715 - Interim transport and termination pricing.

    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...

  11. Staff Reactions to Interim Leadership in a Student Affairs Organization

    Jones, Robin D.

    2011-01-01

    Interim leadership appointments in higher education are a common strategy used to fill leadership gaps in executive positions. Because student affairs executives are particularly vulnerable to high turnover rates, interim appointments are becoming more widespread. Even with the prevalence of this trend, little attention has been given to the…

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

    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.

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

    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.

  14. Transport and interim storage casks in Switzerland

    Full text: The Swiss utilities have chosen two different ways for the management of their spent fuel after initial on-site cooling: either reprocessing at La Hague plant (COGEMA) and Sellafield plant (COGEMA); or interim storage at the Central Interim Storage Facility called 'Zwischenlager Wuerenlingen AG' ( ZWILAG). Following international call for tenders, COGEMA LOGISTICS were awarded contracts for the supply of dual-purpose transport and storage casks for the interim storage of various spent fuel assemblies. All these casks belong to the family of the TN 24 dual purpose spent fuel storage casks in operation in the USA and in Belgium as well. They offer utilities a modular solution for the interim storage of spent fuel in robust metal casks which are fully suitable for off site transports. This flexible product can be readily adapted to suit individual user needs. The Leibstadt Nuclear Power Plant (KKL) has purchased six licensed dual-purpose TN97L spent fuel casks (97 BWR type fuel assemblies capacity). Three of them are already in operation at ZWILAG. COGEMA LOGISTICS has also delivered a dual-purpose TN52L spent fuel casks (52 BWR type fuel assemblies capacity) presently used for transport of spent fuel for reprocessing. The Goesgen Nuclear Power Plant (KKG) has purchased four licensed dual-purpose TN24G spent fuel casks (37 PWR type fuel assemblies capacity). They are all in operation at ZWILAG. The Muehleberg Nuclear Power Plant (BKW/KKM) has purchased 2 TN24BH spent fuel casks (69 BWR type fuel assemblies capacity). At the time of this abstract, cold trials are carried out involving the shuttle transport cask TN9/4 procured by COGEMA LOGISTICS as well. This paper will present the main features of these casks and the main steps of their development and implementation: 1) Main features of the casks: - The basic structure is a thick steel cylindrical forging with a welded on forged bottom and two forged steel lids. Containment and gamma shielding features of

  15. Interim report and accounts 1993/94

    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)

  16. Hierarchies of belief and interim rationalizability

    Jeffrey C. Ely

    2006-03-01

    Full Text Available In games with incomplete information, conventional hierarchies of belief are incomplete as descriptions of the players' information for the purposes of determining a player's behavior. We show by example that this is true for a variety of solution concepts. We then investigate what is essential about a player's information to identify behavior. We specialize to two player games and the solution concept of interim rationalizability. We construct the universal type space for rationalizability and characterize the types in terms of their beliefs. Infinite hierarchies of beliefs over conditional beliefs, which we call Delta-hierarchies, are what turn out to matter. We show that any two types in any two type spaces have the same rationalizable sets in all games if and only if they have the same Delta-hierarchies.

  17. Licensing procedure for interim stores in Germany

    The coalition agreement of October 1998 signed by the parties in government contains a provision about the treatment of spent fuel elements from nuclear power plants which, in principle, seeks to avoid transports and terminate, which would also end transports to France and the UK, by July 1, 2005. After that date, all fuel elements arising are to be managed by direct disposal. Pending the start of operation of a suitable repository, this concept requires safekeeping of spent fuel elements in appropriate storage facilities. The consensus agreement between the federal government and the power utilities contains this approach with the goal of building on-site storage facilities. The Federal Office for Radiation Protection (BfS), as the competent supervisory authority under Sec. 6 of the Atomic Energy Act, has received licensing applications for temporary and on-site stores, respectively, as decentralized interim stores for all nuclear power plant sites in Germany (with the exception of Muelheim-Kaerlich, for which special regulations exist). Three technical concepts, namely two variants of a hall structure, a tunnel concept for Neckarwestheim, and a temporary store, must be examined by BfS in a licensing procedure including as its main steps public participation, examination of the preconditions for a permit, and drafting of the licensing decision. In addition, on-site stores require that an environmental impact assessment be carried out. Proceedings are conducted at BfS largely in parallel and speedily by a project group set up. BfS intends to finish all steps involving public participation still this year. When all preconditions have been met for licensing decisions to be granted, and with an assumed construction period of two years, on-site interim stores ought to be available from 2005 on. (orig.)

  18. Interim Hanford Waste Management Technology Plan

    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

  19. Interim Land Use Plan : Muscatatuck National Wildlife Refuge

    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...

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

    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

  1. Tank Farm Interim Surface Barrier Materials And Runoff Alternatives Study

    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.

  2. Walnut Creek National Wildlife Refuge : Interim hunting plan

    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....

  3. Fire Hazards Analysis for the 200 Area Interim Storage Area

    This documents the Fire Hazards Analysis (FHA) for the 200 Area Interim Storage Area. The Interim Storage Cask, Rad-Vault, and NAC-1 Cask are analyzed for fire hazards and the 200 Area Interim Storage Area is assessed according to HNF-PRO-350 and the objectives of DOE Order 5480 7A. This FHA addresses the potential fire hazards associated with the Interim Storage Area (ISA) facility in accordance with the requirements of DOE Order 5480 7A. It is intended to assess the risk from fire to ensure there are no undue fire hazards to site personnel and the public and to ensure property damage potential from fire is within acceptable limits. This FHA will be in the form of a graded approach commensurate with the complexity of the structure or area and the associated fire hazards

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

    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...

  5. Technical bases for interim storage of spent nuclear fuel

    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

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

    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.

  7. Interim research assessment 2003-2005 - Computer Science

    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.

  8. Security of radioactive sources: Interim guidance for comment

    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)

  9. DOE Hanford Site tank farm interim stabilization during 1990

    Three single-shell nuclear waste storage tanks at the US Department of Energy (DOE) Hanford Site were interim stabilized during 1990 using a jet pump system. This paper discusses the pumping system, processes, stabilization criteria, and problems encountered during interim stabilization of these tanks. An upgraded pumping system was used that was developed from a previous jet pumping campaign completed in 1985. 6 figs

  10. ITER interim design report package and relevant documents

    This publication documents the technical basis which underlay the Interim Design Report, Cost Review and Safety Analysis submitted to the ITER Councils (IC-8 and IC-9) Records of decisions and the ''ITER Interim Design Report Package''. This publication contains ITER Site Requirements and ITER Site Design Assumptions, TAC-8 Report, SRG Report, CP's Report on Tentative Sequence of Events and Parties' Views on the IDR Package and Parties' Technical Comments on the IDR Package. Figs, tabs

  11. Interim Safety Basis for Fuel Supply Shutdown Facility

    BENECKE, M.W.

    2000-09-07

    This ISB, in conjunction with the IOSR, provides 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 or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines.

  12. Packaging, transportation and interim storage of unconditioned and conditioned wastes

    The methods and experiences for packaging, transport and possibilities for interim storage of unconditioned wastes are described. After the waste treatment and immobilization, it is packaged for transport and final disposal following the requirements of the IAEA transport regulations and national regulations. The characteristics of some common types of containe and shielding systems, and some techniques for interim storage of conditioned wastes, are presented. (Author)

  13. K basins interim remedial action health and safety plan

    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.

  14. Interim Safety Basis for Fuel Supply Shutdown Facility

    This ISB, in conjunction with the IOSR, provides 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 or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines

  15. RATIO BETWEEN ACCOUNTING PRINCIPLES AND INTERIM FINANCIAL REPORTING

    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...

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

    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

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

    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

  18. 340 Waste Handling Facility interim safety basis

    This document establishes the interim safety basis (ISB) for the 340 Waste Handling Facility (340 Facility). An ISB is a documented safety basis that provides a justification for the continued operation of the facility until an upgraded final safety analysis report is prepared that complies with US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports. The ISB for the 340 Facility documents the current design and operation of the facility. The 340 Facility ISB (ISB-003) is based on a facility walkdown and review of the design and operation of the facility, as described in the existing safety documentation. The safety documents reviewed, to develop ISB-003, include the following: OSD-SW-153-0001, Operating Specification Document for the 340 Waste Handling Facility (WHC 1990); OSR-SW-152-00003, Operating Limits for the 340 Waste Handling Facility (WHC 1989); SD-RE-SAP-013, Safety Analysis Report for Packaging, Railroad Liquid Waste Tank Cars (Mercado 1993); SD-WM-TM-001, Safety Assessment Document for the 340 Waste Handling Facility (Berneski 1994a); SD-WM-SEL-016, 340 Facility Safety Equipment List (Berneski 1992); and 340 Complex Fire Hazard Analysis, Draft (Hughes Assoc. Inc. 1994)

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

    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.

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

    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.

  1. The UN Interim Administration Mission in Kosovo (UNMIK

    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.

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

    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)

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

    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

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

    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

  5. Next Generation Melter Optioneering Study - Interim Report

    The next generation melter (NOM) development program includes a down selection process to aid in determining the recommended vitrification technology to implement into the WTP at the first melter change-out which is scheduled for 2025. This optioneering study presents a structured value engineering process to establish and assess evaluation criteria that will be incorporated into the down selection process. This process establishes an evaluation framework that will be used progressively throughout the NGM program, and as such this interim report will be updated on a regular basis. The workshop objectives were achieved. In particular: (1) Consensus was reached with stakeholders and technology providers represented at the workshop regarding the need for a decision making process and the application of the D20 process to NGM option evaluation. (2) A framework was established for applying the decision making process to technology development and evaluation between 2010 and 2013. (3) The criteria for the initial evaluation in 2011 were refined and agreed with stakeholders and technology providers. (4) The technology providers have the guidance required to produce data/information to support the next phase of the evaluation process. In some cases it may be necessary to reflect the data/information requirements and overall approach to the evaluation of technology options against specific criteria within updated Statements of Work for 2010-2011. Access to the WTP engineering data has been identified as being very important for option development and evaluation due to the interface issues for the NGM and surrounding plant. WRPS efforts are ongoing to establish precisely data that is required and how to resolve this Issue. It is intended to apply a similarly structured decision making process to the development and evaluation of LAW NGM options.

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

    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)

  7. The Proposal to Create the Czech Accounting Standards – Interim Financial Reporting

    Jana Gláserová

    2013-01-01

    This paper examines the importance of the position and role of interim financial statements in the Czech financial reporting.The paper created a proposal for the creation of a new Czech Accounting Standard – “Interim Financial Statements”. Its purpose is both to unify the existing fragmented legislation issues examined under the Czech law and also to define the essential terms of the lack of interim financial statements. This is the definition of the interim reporting period, the obligation o...

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

    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

    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. Single-shell tank interim stabilization project plan

    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

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

    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.

  12. Fear of permanence: The challenge of siting interim facilities

    This paper examines an increasingly urgent and surprisingly difficult task: siting potentially hazardous facilities that are intended to operate for a limited period, such as a Monitored Retrievable Storage facility (MRS) for radioactive waste. Other examples are at-reactor radioactive waste storage facilities (e.g., dry cask storage) an interim storage facilities for plutonium recovered from retired nuclear weapons. Conventional wisdom holds that such facilities will be easier to site than facilities that are intended to be permanent, such as a radioactive waste repository. Yet the record to date has not provided much support for this expectation. Efforts to site an MRS are approaching the decade mark, despite several acts of Congress and the implementation of a variety of innovative institutional mechanisms designed to facilitate the siting process. And there is no end in sight exclamation point As the title of this paper suggests, we argue that a distinctive challenge to siting interim facilities is meeting the concern of interested publics that the facility may turn out not to be interim and instead achieve de facto permanence. Unless this concern is successfully addressed, siting an interim facility becomes just as difficult as siting as permanent facility because the concerned publics have to assume the worst (that the interim facility will be permanent) and act accordingly. Our analysis of this challenge is in four parts. First, we describe a generalized scenario that captures the logic of the dilemma. Second, we briefly recount four cases where the scenario is being played out (or has the potential to do so). Third, we explore several more specific siting issues through the lens of the interim facilities dilemma. Fourth, we draw conclusions and policy implications

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

    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

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

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

    1992-04-01

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

  15. 40 CFR 57.302 - Performance level of interim constant controls.

    2010-07-01

    ... 40 Protection of Environment 5 2010-07-01 2010-07-01 false Performance level of interim constant... Performance level of interim constant controls. (a) Maximum feasible efficiency. Each NSO shall require: that the smelter operate its interim constant control systems at their maximum feasible...

  16. 24 CFR 960.257 - Family income and composition: Regular and interim reexaminations.

    2010-04-01

    ... move to an appropriate size unit. (b) Interim reexaminations. A family may request an interim... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Family income and composition... and Reexamination § 960.257 Family income and composition: Regular and interim reexaminations....

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

    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...

  18. Interim safety basis for fuel supply shutdown facility

    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

  19. Single-shell tank interim stabilization risk analysis

    The purpose of the Single-Shell Tank (SST) Interim Stabilization Risk Analysis is to provide a cost and schedule risk analysis of HNF-2358, Rev. 1, Single-Shell Tank Interim Stabilization Project Plan (Project Plan) (Ross et al. 1998). The analysis compares the required cost profile by fiscal year (Section 4.2) and revised schedule completion date (Section 4.5) to the Project Plan. The analysis also evaluates the executability of the Project Plan and recommends a path forward for risk mitigation

  20. Single-shell tank interim stabilization risk analysis

    Basche, A.D.

    1998-07-31

    The purpose of the Single-Shell Tank (SST) Interim Stabilization Risk Analysis is to provide a cost and schedule risk analysis of HNF-2358, Rev. 1, Single-Shell Tank Interim Stabilization Project Plan (Project Plan) (Ross et al. 1998). The analysis compares the required cost profile by fiscal year (Section 4.2) and revised schedule completion date (Section 4.5) to the Project Plan. The analysis also evaluates the executability of the Project Plan and recommends a path forward for risk mitigation.

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

    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

  2. 32 CFR 94.4 - Policy and procedures.

    2010-07-01

    ... Forces of the United States may result in the loss of their native country citizenship but this same service may make them eligible for U.S. citizenship. (b) Their eligibility for naturalization, based upon... Islands, they should apply for citizenship only if they expect to be stationed at the base for at least...

  3. Continuation of the summarizing interim report on previous results of the Gorleben site survey as of May 1983

    In addition to results from the 1983 interim report, this report contains, in order to supplement the surface explorations, seismic reflection measurements, hydrogeologic and seismologic investigations, sorption experiments, and studies of glacial development in the site region and of long-term safety of final waste repositories in salt domes. The site's high grade of suitability for becoming a final radioactive waste repository, the legal basis as well as quality assurance are evaluated. (orig.)

  4. LDEF materials: An overview of the interim findings

    The flight and retrieval of the National Aeronautics and Space Administration's Long Duration Exposure Facility (LDEF) provided an opportunity for the study of the low-Earth orbit (LEO) environment and long-duration space environmental effect (SEE) on materials that are unparalleled in the history of the U.S. space program. The 5.8-year flight of LDEF greatly enhanced the potential value of materials data from LDEF to the international SEE community, compared to that of the original 1-year flight plan. The remarkable flight attitude stability of LDEF enables specific analyses of various individual and combined effects of LEO environmental parameters on identical materials of the same space vehicle. NASA recognized the potential by forming the LDEF Space Environmental Effects on Materials Special Investigation Group (MSIG) to address the greatly expanded materials and LEO space environment parameter analysis opportunities available in the LDEF structure, experiment trays, and corollary measurements, so that the combined value of all LDEF materials data to current and future space missions will be assessed and documented. This paper provides an overview of the interim LDEF materials findings of the Principal Investigators and the Materials Special Investigation Group. These revelations are based on observations of LEO environmental effects on materials made in-space during LDEF retrieval and during LDEF tray deintegration at the Kennedy Space Center, and on findings of approximately 1.5 years of laboratory analyses of LDEF materials by the LDEF materials scientists. These findings were extensively reviewed and discussed at the MSIG-sponsored LDEF Materials Workshop '91. The results are presented in a format which categorizes the revelations as clear findings or confusing/unexplained findings and resultant needs for new space materials developments and ground simulation testing/analytical modeling

  5. 46 CFR 308.103 - Insured amounts under interim binder.

    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:...

  6. Single-shell tank interim stabilization project 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, and interfaces; and operational methods. This plan serves as the project executional baseline

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

    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.

  8. The Children's Behavioral Classification Project: An Interim Report

    Dreger, Ralph Mason

    1977-01-01

    Described in the interim report of the Children's Behavioral Classification Project (CBCP) is the CBCP instrument, a duplicated list of 274 behavioral items and three demographic items which provides a profile of the emotionally disordered child based on observations by the parent or parent-surrogate. (SBH)

  9. System Specification for Immobilized High-Level Waste Interim Storage

    CALMUS, R.B.

    2000-12-27

    This specification establishes the system-level functional, performance, design, interface, and test requirements for Phase 1 of the IHLW Interim Storage System, located at the Hanford Site in Washington State. The IHLW canisters will be produced at the Hanford Site by a Selected DOE contractor. Subsequent to storage the canisters will be shipped to a federal geologic repository.

  10. Single-shell tank interim stabilization project plan

    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.

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

    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.

  12. Single-Shell Tank (SST) Interim Stabilization Project Plan

    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

  13. System Specification for Immobilized High-Level Waste Interim Storage

    This specification establishes the system-level functional, performance, design, interface, and test requirements for Phase 1 of the IHLW Interim Storage System, located at the Hanford Site in Washington State. The IHLW canisters will be produced at the Hanford Site by a Selected DOE contractor. Subsequent to storage the canisters will be shipped to a federal geologic repository

  14. On-site interim stores for spent fuel elements

    Since June 14 this year, the subject of a nuclear power consensus has been mentioned in the headlines less frequently than in past years. On that day, the government and operators of power plants agreed in Berlin on residual amounts of electricity to be produced and on management of the spent fuel elements of the nineteen German nuclear power plants. One sub-item under the heading of waste management, which continues to arouse debates not only at nuclear power plant sites despite the consensus reached, and which may become vitally important to the operation of plants, will be covered in more detail below: the construction of so-called decentralized interim stores. When present contracts with French and British firms on nuclear fuel reprocessing have been fulfilled and reprocessing has been phased out, these interim stores are to minimize the number of transports within Germany, a notorious source of general unrest, and are supposed to accommodate the spent fuel elements until a suitable repository will have been built where they can then be stored permanently. The whole development of a management concept for spent nuclear fuel in the Federal Republic of Germany, and the requirements to be met by decentralized interim stores, are explained in the article. The resultant standardized concept of dry interim cask storage is outlined in the light of its legal and technical criteria. Finally, the site-dependent variants of this concept are presented, and the status and the special features of the ongoing licensing procedures are explained. (orig.)

  15. Minish Named Interim Head of Admissions at Virginia Tech

    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.

  16. 40 CFR 80.141 - Interim detergent gasoline program.

    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....

  17. Interim analysis in long-term clinical trials

    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

  18. 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

    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...

  19. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    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

  20. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    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

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

    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

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

    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

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

    1990-05-01

    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.

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

    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.

  5. Final Safety Report for Central Interim Storage Facility for Radioactive Waste from Small Producers in Brinje near Ljubljana

    In 1999 the Agency for Radwaste Management took over the management of the Central Interim Storage for radioactive waste from small producers in Brinje. At the same time in accordance with a Decree on the Mode, Subject and Terms of Performing the Public Service of Radioactive Waste Management (Official Gazette of RS, 32/99) the ARAO agency was appointed to perform the public service of radioactive waste management for waste produced in Slovenia in industry, medicine and research. After taking over responsibility for the storage the ARAO thoroughly reviewed the facility and the stored inventory. Based on the findings of this review the ARAO agency prepared a basic document for the facility i.e. Final Safety Report for the Central Interim Storage for radioactive waste from small producers in Brinje. The safety report is based on the present state of the facility, its location, stored inventory and present operation. The latter is limited to storing of already stored waste, acceptance of new waste only in emergency cases, and internal transport of the accepted waste with a forklift or manually. The Final Safety Report is prepared in accordance with the requirements of Regulation E2 and deals with the following areas: The safety approach to LILW storage, Description and location analysis of the Central interim storage, Technical features of the Central interim storage, Safety analysis of the Central interim storage, Organisational measures for normal operation of the Central interim storage, Operational conditions and limitations, Ionising 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 the closure of the Central interim storage. Safety analysis proves that the facility

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

    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

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

    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.

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

    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.

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

    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.

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

    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.

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

    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.

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

    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

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

    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

  14. EMDEX Project Residential Study: Interim report

    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.

  15. 105-C Reactor interim safe storage project technology integration plan

    The 105-C Reactor Interim Safe Storage Project Technology Integration Plan involves the decontamination, dismantlement, and interim safe storage of a surplus production reactor. A major goal is to identify and demonstrate new and innovative D and D technologies that will reduce costs, shorten schedules, enhance safety, and have the potential for general use across the RL complex. Innovative technologies are to be demonstrated in the following areas: Characterization; Decontamination; Waste Disposition; Dismantlement, Segmentation, and Demolition; Facility Stabilization; and Health and Safety. The evaluation and ranking of innovative technologies has been completed. Demonstrations will be selected from the ranked technologies according to priority. The contractor team members will review and evaluate the demonstration performances and make final recommendations to DOE

  16. Ad interim legal remedy in case of large projects

    Action for ad interim judicial relief in response to large projects approved of by the authorities very frequently take several years until a decision is taken by the court. Experience has shown that this applies in particular to large projects such as the construction of nuclear power plants, large-size industrial plants, or airports. It has become regular practice by the authorities concerned to issue an order for immediate execution upon the plan approving decision and granting of licence for said projects, in accordance with section 80, sub-section (2), no.4 of the VwGO. The problems thus created with regard to interim legal remedy sought by the parties concerned are of great significance. The book in hand discusses the question as to whether the practice of the administrative authorities and the courts satisfies the requirements embodied in the law, to provide for efficient legal protection. (orig./HSCH)

  17. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    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

  18. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    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.

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

    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.

  20. Species management in aquatic habitats WRc RD Interim 1997

    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...

  1. 105-H Reactor Interim Safe Storage Project Final Report

    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.

  2. Dry storage of spent fuel elements: interim facility

    Apart from the existing facilities to storage nuclear fuel elements at Argentina's nuclear power stations, a new interim storage facility has been planned and projected by the Argentinean Atomic Energy Commission (CNEA) that will be constructed by private group. This article presents the developments and describes the activities undertaken until the national policy approach to the final decision for the most suitable alternative to be adopted. (B.C.A.). 09 refs, 01 fig, 09 tabs

  3. Conditioning of radioactive waste for long - term interim storage

    There are currently 4800 drums of treated radioactive waste originating from the operation and subsequent decommissioning of Siemens' former nuclear fuel fabrication plant in Hanau (Siemens RB) that are in interim storage at two sites in Germany. Some of this waste is in an interim store at the Karlsruhe Research Center operated by its Decontamination Division (HDB). The store also contains around 30,000 drums of radwaste from the research center itself as well as local institutions. Germany's Federal Government anticipates that interim storage will be necessary for a further 30 years until a suitable final repository goes into operation. However, since the waste drums were not designed for such a long period of storage, other steps must now be taken to ensure safe interim storage in the long term. The objective is to condition the existing waste drums as well as future waste arisings in accordance with the 1989 regulatory guideline on non-heat-generating radioactive waste such that they satisfy the acceptance criteria applicable since 1995 for final disposal at the Konrad repository. The drums are to be immobilized in concrete inside Konrad containers designed for long-term corrosion resistance in order to obtain waste packages that can be safely stored for a prolonged period without maintenance. If the activity limit for the container is not reached, low-level waste can be added as an aggregate to the concrete, which occupies around half the volume of each container, in order to save storage capacity at the repository. This waste conditioning, to be performed at HDB and Siemens RB, will convert around 65% of all non-heat-generating waste in Germany to a form that is suitable for final storage and is maintenance-free. (orig.)

  4. Interim dry storage system technologies and innovations VARNA 2002

    The main concepts of the TN24 Family and NUHOMS System are explained in the paper. It is discussed how the NPPs specific requirements and economics trends contributes to the growing families of interim dry storage systems delivered under COGEMA LOGICTICS license. It is concluded that modular solutions are currently dominating because they are derived from main concepts evolved over time, benefited from both the transport aspects with internationally recognised stringent regulations, and various specific ISFSI requirements and economic trends

  5. Bucy named interim assistant vice president, head of sponsored programs

    Trulove, Susan

    2006-01-01

    Linda Bucy of Christiansburg, Va., director of post award administration in the Office of Sponsored Programs (OSP), has been appointed interim assistant vice president and director of the Office of Sponsored Programs. She replaces David Richardson, assistant vice president for sponsored program administration in the Office of the Vice President for Research, who has accepted a position at Penn State University as assistant vice president for research and director of the Office of Sponsored Pr...

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

    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

  7. Waste Encapsulation and Storage Facility interim operational safety requirements

    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.

  8. FRACTIONAL CRYSTALLIZATION TESTING WITH INTERIM PRETREATMENT SYSTEM FEEDS

    The fractional crystallization process was developed as a pretreatment method for saltcake waste retrieved from Hanford single-shell tanks (SST). The process separates the retrieved SST waste into a high-level waste stream containing the bulk of the radionuclides and a low-activity waste stream containing the bulk of the nonradioactive sodium salts. The Interim Pretreatment System project shifted the focus on pretreatment planning from SST waste to double-shell tank waste

  9. Loss of approval for interim storage by time schedule

    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.

  10. Transformationale Führung als Erfolgsfaktor des Interim Management

    Bollinger, Jan Andreas

    2010-01-01

    In der vorliegenden Arbeit wurde untersucht, wie Führung zur Bewältigung von Unternehmenskrisen und Umsetzung von Veränderungen im Kontext des Interim Management beitragen kann. Dazu wurde die Theorie transformationaler Führung um aufgabenbezogene und indirekte Führung und den Einsatz von Positionsmacht ergänzt. Damit wurden diese erfolgskritischen Führungsdimensionen erstmals in einem gemeinsamen theoretischen Rahmen verbunden und die Auswirkungen einer kombinierten Anwendung untersucht. Die...

  11. AN INTERIM THERMODYNAMIC PROPERTY FORMULATION FOR SUPERCRITICAL n-HEXANE

    Azzedine Abbaci; Anissa Acidi; Aicha Rizi; Salaheddine Azzouz

    2010-01-01

    Accurate information on the thermodynamic properties of supercritical fluids is highly sought for the chemical technology, especially, supercritical extraction technology. The thermodynamic properties of fluids near the critical region are strongly affected by the presence of fluctuations and therefore, can not be described by conventional equation. We have investigated an interim formulation for the behavior of the thermodynamic properties of n-hexane in the vicinity of the critical region. ...

  12. Interim prediction method for low frequency core engine noise

    Huff, R. G.; Clark, B. J.; Dorsch, R. G.

    1974-01-01

    A literature survey on low-frequency core engine noise is presented. Possible sources of low frequency internally generated noise in core engines are discussed with emphasis on combustion and component scrubbing noise. An interim method is recommended for predicting low frequency core engine noise that is dominant when jet velocities are low. Suggestions are made for future research on low frequency core engine noise that will aid in improving the prediction method and help define possible additional internal noise sources.

  13. Interim storage and transport casks in Switzerland. COGEMA logistics experience

    The Swiss utilities have chosen two different ways for the management of their spent fuel after initial on-site cooling: (1) reprocessing at La Hague plant (COGEMA) and Sellafield plant (BNFL); (2) interim storage at the Central Interim Storage Facility called 'Zwischenlager Wuerenlingen AG' ( ZWILAG). Following international call for tenders by Swiss utilities, COGEMA LOGISTICS has been awarded several contracts for the supply of dual-purpose transport and storage casks for the interim storage of various spent fuel assemblies. All these casks belong to the family of the TN 24 dual purpose spent fuel storage casks in operation in the USA and in Belgium as well. They offer utilities a modular solution for the interim storage of spent fuel in robust metal casks which are fully suitable for off site transports. This flexible product can be readily adapted to suit individual user needs. The Leibstadt Nuclear Power Plant (KKL) has purchased nine licensed dual-purpose TN 97L spent fuel casks (97 BWR type fuel assemblies capacity). Three of them are already in operation at ZWILAG. COGEMA LOGISTICS has also delivered a dual-purpose TN 52L spent fuel casks (52 BWR type fuel assemblies capacity) presently used for transport of spent fuel for reprocessing. The Goesgen Nuclear Power Plant (KKG) has purchased four licensed dual-purpose TN 24G spent fuel casks (37 PWR type fuel assemblies capacity). They are all in operation at ZWILAG. The Muehleberg Nuclear Power Plant (BKW/KKM) has purchased two TN 24BH spent fuel casks (69 BWR type fuel assemblies capacity). At the time of this abstract, cold trials are carried out involving the shuttle transport cask TN 9/4 procured by COGEMA LOGISTICS as well. (author)

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

    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

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

    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)

  16. Interim Dry Storage of Spent Fuel in Casks

    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

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

    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

  18. Interim guidelines for protecting fire-fighting personnel from multiple hazards at nuclear plant sites

    This report provides interim guidelines for reducing the impact to fire fighting and other supporting emergency response personnel from the multiple hazards of radiation, heat stress, and trauma when fighting a fire in a United States commercial nuclear power plant. Interim guidelines are provided for fire brigade composition, training, equipment, procedures, strategies, heat stress and trauma. In addition, task definitions are provided to evaluate and further enhance the interim guidelines over the long term. 19 refs

  19. DATA MINING METHODOLOGY FOR DETERMINING THE OPTIMAL MODEL OF COST PREDICTION IN SHIP INTERIM PRODUCT ASSEMBLY

    Damir Kolich; Nikša Fafandjel; Y. Lawrence Yao

    2016-01-01

    In order to accurately predict costs of the thousands of interim products that are assembled in shipyards, it is necessary to use skilled engineers to develop detailed Gantt charts for each interim product separately which takes many hours. It is helpful to develop a prediction tool to estimate the cost of interim products accurately and quickly without the need for skilled engineers. This will drive down shipyard costs and improve competitiveness. Data mining is used extensively for developi...

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

    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...

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

    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...

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

    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.

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

    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

  4. Labour Force Survey: interim reweighting 2007

    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...

  5. Magnetosphere imager science definition team interim report

    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.

  6. Interim report on hydrogen storage system

    Hydrogen can be stored in the form of a metal hydride. The formation of the hydride is highly exothermic. Hence the rate at which hydrogen can be added to or removed from the storage system is limited by the rate of heat transfer. Heat transfer is facilitated by displaying the hydride on a metal support that conducts heat. The task was to find a binder to make hydride stay put on a metal support through at least 2500 cycles of hydriding-dehydriding and to measure the rate of hydrogen uptake. 1 tab

  7. Characterization of void volume VOC concentration in vented TRU waste drums - an interim report

    A test program is underway at the Idaho National Engineering Laboratory to determine if the concentration of volatile organic compounds (VOCs) in the drum headspace is representative of the VOC concentration in the entire drum void space and to demonstrate that the VOC concentration in the void space of each layer of confinement can be estimated using a model incorporating diffusion and permeation transport principles and limited waste drum sampling data. An experimental test plan was developed requiring gas sampling of 66 transuranic (TRU) waste drums. This interim report summarizes the experimental measurements and model predictions of VOC concentration in the innermost layer of confinement from waste drums sampled and analyzed in FY 1994

  8. Colonie Interim Storage Site: Annual environmental report for calendar year 1990, Colonie, New York

    Environmental monitoring of the US Department of Energy's (DOE) Colonie Interim Storage Site (CISS) and surrounding area began in 1984. CISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sties 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 routine environmental monitoring program at CISS includes sampling networks for external gamma radiation exposures and for radium-226, throium-232, an total uranium concentrations in surface water, sediment, and groundwater. Additionally, the nonradiological parameters volatile and semivolatile organics, pesticides/polychlorinated biphenyls (PCBs), metals, total organic carbon (TOC), total organic halides (TOX), specific conductivity, and pH are measured in groundwater. 14 refs., 20 figs., 25 tabs

  9. Wayne Interim Storage Site: Annual environmental report for calendar year 1990, Wayne, New Jersey

    Environmental monitoring of the US Department of Energy's (DOE) Wayne Interim Storage Site (WISS) (a National Priorities List site) and surrounding area began in 1984. WISS 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 environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Sediment samples were also analyzed for thorium-230, and several nonradiological parameters were measured in groundwater. 16 refs., 12 figs., 23 tabs

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

    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...