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Sample records for development facility quarterly

  1. Power Systems Development Facility. Quarterly report, January--March 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particular control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the Foster Wheeler portion of the facility towards completion and integrating the balance-of-plant processes and particulate control devices (PCDs) into the structural and process designs. Substantial progress in construction activities was achieved during the quarter.

  2. Power Systems Development Facility. Quarterly report, July 1--September 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    This quarterly technical progress report summarizes the work completed during the third quarter of a project entitled Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion. The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phase expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: carbonizer/pressurized circulating fluidized bed gas source; hot gas cleanup units to mate to all gas streams; combustion gas turbine; and fuel cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF).

  3. Projects at the component development and integration facility. Quarterly technical progress report, April 1, 1994--June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY94. The CDIF is a major Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; and Spray Casting Project

  4. Projects at the Component Development and Integration Facility. Quarterly technical progress report, January 1--March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    This quarterly technical progress report presents progress on several different projects at the Component Development and Integration Facility (CDIF) during the second quarter of FY93. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD Proof-of-Concept Project; Mine Waste Technology Pilot Program; Plasma Furnace Projects for waste destruction; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; Soil Washing Project for removal of radioactive materials; and Spray Casting Project.

  5. [Glass Development Laser (GDL) Facility upgrade.] LLE Review. Quarterly report, October-December 1984. Volume 21

    International Nuclear Information System (INIS)

    Kim, H.

    1984-01-01

    This volume of the LLE Review contains articles on the upgrade of the GDL (Glass Development) system, theoretical advances in the laser fusion effort, improved target fabrication capabilities, x-ray laser research, developments in the picosecond optics research of the LLE advanced technology program, and on the National Laser Users Facility activities for October-December 1984. 56 refs., 31 figs., 3 tabs

  6. Safeguards material control at licensed processing facilities. Quarterly report, April--June 1977

    International Nuclear Information System (INIS)

    Hollstien, R.B.; Maimoni, A.; Spogen, L.R.

    1977-01-01

    This is the third quarterly report of progress at LLL on assessment methodologies and tools to assist the NRC in the development and enforcement of performance based regulations pertaining to special nuclear material safeguards at licensed facilities. The first quarterly report presented an overview of LLL's approach as of February, 1977. The second quarterly report describes the design of a hypothetical material control system referred to as the ''test bed design'' which is being used at LLL in the development of techniques for the assessment of material control system effectiveness. This report describes one of these techniques, a specialized computer simulation program for determination of material control system responses to particular adversary action sequences that constitute a material diversion attempt. The report contains an overview description of the Material Control System Simulator (MCSS) program and its role in the LLL assessment procedure. The complete MCSS User's Manual is available in the LLL report UCID 17727. This and the previous quarterly are detailed topical reports and do not present progress made in other areas of this program. Future quarterly reports will resume broad coverage of all aspects of LLL's assistance to the NRC on Safeguards Material Control at Licensed Processing Facilities

  7. Atmospheric Radiation Measurement program climate research facility operations quarterly report.

    Energy Technology Data Exchange (ETDEWEB)

    Sisterson, D. L.; Decision and Information Sciences

    2006-09-06

    Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real time. Raw and processed data are then sent daily to the ACRF Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual data stream, site, and month for the current year and (2) site and fiscal year dating back to 1998. The U.S. Department of Energy requires national user facilities to report time-based operating data. The requirements concern the actual hours of operation (ACTUAL); the estimated maximum operation or uptime goal (OPSMAX), which accounts for planned downtime; and the VARIANCE [1-(ACTUAL/OPSMAX)], which accounts for unplanned downtime. The OPSMAX time for the third quarter for the Southern Great Plains (SGP) site is 2,074.80 hours (0.95 x 2,184 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,965.60 hours (0.90 x 2,184), and that for the Tropical Western Pacific (TWP) locale is 1,856.40 hours (0.85 x 2,184). The OPSMAX time for the ARM Mobile Facility (AMF) is 2,074.80 hours (0.95 x 2,184). The differences in OPSMAX performance reflect the complexity of local logistics and the frequency of extreme weather events. It is impractical to measure OPSMAX for each instrument or data stream. Data availability reported here refers to the average of the individual, continuous data streams that have been received by the Archive. Data not at the Archive are caused by downtime (scheduled or unplanned) of the individual instruments. Therefore, data availability is directly related to individual instrument uptime. Thus, the average percent of data in the Archive

  8. "The Career Development Quarterly": A Centennial Retrospective

    Science.gov (United States)

    Savickas, Mark L.; Pope, Mark; Niles, Spencer G.

    2011-01-01

    "The Career Development Quarterly" has been the premier journal in the field of vocational guidance and career intervention since its inception 100 years ago. To celebrate its centennial, 3 former editors trace its evolution from a modest and occasional newsletter to its current status as a major professional journal. They recount its history of…

  9. Metallurgical Laboratory Hazardous Waste Management Facility groundwater monitoring report. First quarter 1995

    International Nuclear Information System (INIS)

    1995-06-01

    During first quarter 1995, samples from AMB groundwater monitoring wells at the Metallurgical Laboratory Hazardous Waste Management Facility (Met Lab HWMF) were analyzed for selected heavy metals, field measurements, radionuclides, volatile organic compounds, and other constituents. Six parameters exceeded standards during the quarter. As in previous quarters, tetrachloroethylene and trichloroethylene exceeded final Primary Drinking Water Standards (PDWS). Total organic halogens exceeded its Savannah River Site (SRS) Flag 2 criterion during first quarter 1995 as in fourth quarter 1994. Aluminum, iron, and manganese, which were not analyzed for during fourth quarter 1994, exceeded the Flag 2 criteria in at least two wells each during first quarter 1995. Groundwater flow direction and rate in the M-Area Aquifer Zone were similar to previous quarters. Conditions affecting the determination of groundwater flow directions and rates in the Upper Lost Lake Aquifer Zone, Lower Lost Lake Aquifer Zone, and the Middle Sand Aquifer Zone of the Crouch Branch Confining Unit were also similar to previous quarters

  10. quarters

    Directory of Open Access Journals (Sweden)

    Elena Grigoryeva

    2016-10-01

    Full Text Available Are there many words combining both space and time? A quarter is one of such rare words: it means both a part of the city space and a period of the year. A regular city has parts bordered by four streets. For example, Chita is a city with an absolutely orthogonal historical center. This Utopian city was designed by Decembrists in the depth of Siberian ore-mines (120. The 130 Quarter in Irkutsk is irregular from its inception because of its triangular form. Located between two roads, the forked quarter was initially bordered by flows along the west-east axis – the main direction of the country. That is why it appreciated the gift for the 350 anniversary of its transit existence – a promenade for an unhurried flow of pedestrians. The quarter manages this flow quite well, while overcoming the difficulties of new existence and gathering myths (102. Arousing many expectations, the “Irkutsk’s Quarters” project continues the theme that was begun by the 130 Quarter and involved regeneration, revival and search for Genius Loci and the key to each single quarter (74. Beaded on the trading axis, these shabby and unfriendly quarters full of rubbish should be transformed for the good of inhabitants, guests and the small business. The triptych by Lidin, Rappaport and Nevlyutov is about happiness of urbanship and cities for people, too (58. The City Community Forum was also devoted to the urban theme (114. Going through the last quarter of the year, we hope that Irkutsk will keep to the right policy, so that in the near future the wooden downtown quarters will become its pride, and the design, construction and investment complexes will join in desire to increase the number of comfortable and lively quarters in our city. The Baikal Beam will get one more landmark: the Smart School (22 for Irkutsk’s children, including orphans, will be built in several years on the bank of Chertugeevsky Bay.

  11. ARM Climate Research Facility Quarterly Instrument Report Fourth Quarter: October 1–December 30, 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2011-01-17

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following sections: (1) new instrumentation in the process of being acquired and deployed, (2) existing instrumentation and progress on improvements or upgrades, (3) proposed future instrumentation, and (4) Small Business Innovation Research instrument development.

  12. Quarterly financial reports | IDRC - International Development ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Quarterly Financial Report for the period ending 31 December 2011 · Quarterly Financial Report for the period ending 30 September 2011 · Quarterly Financial Report for the period ending 30 June 2011 · Summary of Expense Reductions to Accommodate Budget 2012 Appropriation Reduction (PDF) · What we do · Funding ...

  13. Metallurgical Laboratory Hazardous Waste Management Facility groundwater monitoring report: Third quarter 1993

    International Nuclear Information System (INIS)

    1993-12-01

    During third quarter 1993, samples from AMB groundwater monitoring wells at the Metallurgical Laboratory Hazardous Waste Management Facility were analyzed for certain heavy metals, indicator parameters, radionuclides, volatile organic compounds, and other constituents. Eight parameters exceeded standards during the quarter. As in previous quarters, tetrachloroethylene and trichloroethylene exceeded final Primary Drinking Water Standards; and aluminum, iron, lead, manganese, pH, and total organic halogens exceeded the Savannah River Site Flag 2 criteria in one or more of the wells. Groundwater flow direction and rate in the water-table unit were similar to previous quarters

  14. Mixed Waste Management Facility Groundwater Monitoring Report, Fourth Quarter 1998 and 1998 Summary

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.

    1999-04-29

    During fourth quarter 1998, ten constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility. No constituents exceeded final PDWS in samples from the upgradient monitoring wells.

  15. Metallurgical Laboratory Hazardous Waste Management Facility groundwater monitoring report. Second quarter 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    During second quarter 1994, samples from AMB groundwater monitoring wells at the Metallurgical Laboratory Hazardous Waste Management Facility were analyzed for selected heavy metals, indicator parameters, radionuclides, volatile organic compounds, and other constituents. Three parameters exceeded standards during the quarter. As in previous quarters, tetrachloroethylene and trichloroethylene exceeded final Primary Drinking Water Standards. Total organic halogens exceeded the Savannah River Site (SRS) Flag 2 criteria in two of the wells. Groundwater flow direction and rate in the M-Area Aquifer Zone were similar to previous quarters. Conditions affecting determination of groundwater flow directions and rates in the Upper Lost Lake Aquifer Zone, Lower Lost Lake Aquifer Zone, and the Middle Sand Aquifer Zone of the Crouch Branch Confining Unit were also similar to previous quarters. During second quarter 1994, SRS received SCDHEC approval for five point-of-compliance wells and two plume definition wells near the Met Lab HWMF. Field work has begun on this project.

  16. ARM Climate Research Facility Quarterly Ingest Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Koontz, A. [DOE ARM Climate Research Facility, Washington, DC (United States); Sivaraman, C. [DOE ARM Climate Research Facility, Washington, DC (United States)

    2016-10-01

    The purpose of this report is to provide a concise status update for ingests maintained by the Atmospheric Radiation Measurement (ARM) Climate Research Facility. The report is divided into the following sections: (1) new ingests for which development has begun, (2) progress on existing ingests, (3) future ingests that have been recently approved, (4) other work that leads to an ingest, and (5) top requested ingests from the ARM Data Archive. New information is highlighted in blue text.

  17. ARM Climate Research Facility Quarterly Ingest Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Koontz, A. [ARM Climate Reesearch Facility, Washington, DC (United States); Sivaraman, C. [ARM Climate Reesearch Facility, Washington, DC (United States)

    2016-07-01

    The purpose of this report is to provide a concise status update for ingests maintained by the Atmospheric Radiation Measurement (ARM) Climate Research Facility. The report is divided into the following sections: (1) new ingests for which development has begun, (2) progress on existing ingests, (3) future ingests that have been recently approved, (4) other work that leads to an ingest, and (5) top requested ingests from the ARM Data Archive. New information is highlighted in blue text.

  18. Fuels Development Operation. Quarterly progress report, July, August, September, 1959

    Energy Technology Data Exchange (ETDEWEB)

    1959-10-15

    The present quarterly report is the continuation of a series issued by the new Fuels Development Operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations.

  19. ARM Climate Research Facility Quarterly Value-Added Product Report

    Energy Technology Data Exchange (ETDEWEB)

    Sivaraman, C. [DOE ARM Climate Research Facility, Washington, DC (United States)

    2016-10-01

    The purpose of this report is to provide a concise status update for Value-Added Products (VAPs) implemented by the Atmospheric Radiation Measurement (ARM) Climate Research Facility. The report is divided into the following sections: (1) new VAPs for which development has begun; (2) progress on existing VAPs; (3) future VAPs that have been recently approved; (4) other work that leads to a VAP; (5) top requested VAPs from the ARM Data Archive; and (6) a summary of VAP and data releases to production and evaluation. New information is highlighted in blue text. New information about processed data by the developer is highlighted in red text. The upcoming milestones and dates are highlighted in green.

  20. Metallurgical Laboratory Hazardous Waste Management Facility groundwater monitoring report. Fourth quarter 1992 and 1992 summary

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, C.Y.

    1993-03-01

    During fourth quarter 1992, samples from 18 groundwater monitoring wells of the AMB series at the Metallurgical Laboratory Hazardous Waste Management Facility were analyzed for certain heavy metals, indicator parameters, radionuclides, volatile organic compounds, and other constituents. Six parameters exceeded final Primary Drinking Water Standards (PDWS) and the Savannah River Site Flag 2 criteria during the quarter. The results for fourth quarter 1992 are fairly consistent with the rest of the year`s data. Tetrachloroethylene exceeded the final PDWS in well AMB 4D only two of the four quarters; in the other three wells in which it was elevated, it was present at similar levels throughout the year. Trichloroethylene consistently exceeded its PDWS in wells AMB 4A, 4B, 4D, 5, and 7A during the year. Trichloroethylene was elevated in well AMB 6 only during third and fourth quarters and in well AMB 7 only during fourth quarter. Total alpha-emitting radium was above the final PDWS for total radium in well AMB 5 at similar levels throughout the year and exceeded the PDWS during one of the three quarters it was analyzed for (third quarter 1992) in well AMB 10B.

  1. PFBC HGCU Test Facility. Technical progress report: Third Quarter, CY 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    This is the sixteenth Technical Progress Report submitted to the Department of Energy (DOE) in connection with the cooperative agreement between the DOE and Ohio Power Company for the Tidd PFBC (pressurized fluidized-bed combustion) Hot Gas Clean Up Test Facility (HGCU). This report covers the period of work completed during the Third Quarter of CY 1993. During this quarter, the Advanced Particle Filter (APF) was operated for a total of 1295 hours. This represents 58% availability during July, August, September, and including June 30 of the previous quarter. The operating dates and times since initial operation are summarized. The APF operating temperatures and differential pressures are provided. Details of the APF runs during this quarter are included in this report.

  2. Radioactivity in gaseous waste discharged from the separations facilities during fourth quarter of 1979

    Energy Technology Data Exchange (ETDEWEB)

    Sliger, G. J.

    1980-02-22

    This document is issued quarterly for the purpose of summarizing the radioactive gaseous wastes that are discharged from the facilities of the Rockwell Hanford Operations (Rockwell). Data on alpha and beta emissions during 1979 are presented where relevant to the gaseous effluent. Emission data are not included on gaseous wastes produced within the 200 areas by other Hanford contractors.

  3. Metallurgical Laboratory Hazardous Waste Management Facility groundwater monitoring report. Third quarter, 1994

    International Nuclear Information System (INIS)

    1994-12-01

    During third quarter 1994, samples from AMB groundwater monitoring wells at the Metallurgical Laboratory Hazardous Waste Management Facility (Met Lab HWMF) were analyzed for selected heavy metals, indicator parameters, radionuclides, volatile organic compounds, and other constituents. Eight parameters exceeded standards during the quarter. As in previous quarters, tetrachloroethylene and trichloroethylene exceeded final Primary Drinking Water Standards (PDWS). Bis(2-ethylhexyl) phthalate exceeded final PDWS in one well. Aluminum, iron, manganese, tin, and total organic halogens exceeded the Savannah River Site (SRS) Flag 2 criteria. Groundwater flow direction and rate in the M-Area Aquifer Zone were similar to previous quarters. Conditions affecting determination of groundwater flow directions and rates in the Upper Lost Lake Aquifer Zone, Lower Lost Lake Aquifer Zone, and the Middle Sand Aquifer Zone of the Crouch Branch Confining Unit were also similar to previous quarters. During second quarter 1994, SRS received South Carolina Department of Health and Environmental Control approval for constructing five point-of-compliance wells and two plume definition wells near the Met Lab HWMF. This project began in July 1994 and is complete; however, analytical data from these wells is not available yet

  4. Z-Area Saltstone Disposal Facility groundwater monitoring report, Fourth quarter 1995 and 1995 summary

    Energy Technology Data Exchange (ETDEWEB)

    Coward, L.S.

    1996-03-01

    Samples from the ZBG wells at the Z-Area Saltstone Disposal Facility are analyzed quarterly for constituents required by South Carolina Department of Health and Environmental Control Industrial Waster Permit IWP-217 and for other constituents as part of the Savannah River Site Groundwater Monitoring Program. During fourth quarter 1995, no constituents were reported above final Primary Drinking Water Standards or SRS flagging criteria. In the past, tritium has been detected sporadically in the ZBG wells at levels similar to those detected before Z Area began radioactive operations.

  5. Geothermal Loop Experimental Facility. Quarterly report, October-December 1978

    Energy Technology Data Exchange (ETDEWEB)

    Anastas, G.; Bischoff, W.S.; Bishop, H.K.

    1979-01-01

    The Geothermal Loop Experimental Facility (GLEF) was modified in April 1978 from a four stage flash/binary process to a two stage cycle for the extraction of energy from a high temperature, high salinity, liquid-dominated resource. The overhaul and cleaning during October and pigging problems which led to a limited shutdown in December are discussed. Reservoir assessment, including production and injection wells, are discussed. Results of tests that were accomplished are included. Laboratory data obtained for steam, brine, binary and cooling water, and scale are indicated. Any equipment that required repairs or modifications to equipment and the clarifier/media filter are discussed. The status of the feasibility and surge studies is covered. (MHR)

  6. Geothermal Loop Experimental Facility. Quarterly report, April--June 1978

    Energy Technology Data Exchange (ETDEWEB)

    Bischoff, W.S.; Bishop, H.K.; Cooney, C.S.; Hanenburg, W.H.; Hoaglin, G.J.; Jacobson, W.O.; Mulliner, D.K.; Newell, D.G.; Swanson, C.R.

    1978-07-01

    The Geothermal Loop Experimental Facility (GLEF) was modified to use a two stage flash process with two parallel flash trains for the extraction of energy from a high temperature, high salinity, liquid-dominated resource. Since plant start-up in May 1976, a substantial amount of information has been obtained on the operation of the plant, components, brine and steam composition, production and injection wells, and the potential of the Niland Reservoir. The general operation and accomplishments of the GLEF during the period April 1978 through June 1978 are discussed. The GLEF underwent a major redesign. Modifications and inspections of various GLEF equipment and systems are also discussed. Information about the production and injection wells flow testing and instrumentation are discussed. Information regarding coatings and linings for valves and piping is included. In the Chemistry Section there is a wide range of data taken from Brine, Steam, Scale, Binary, Condensate, and Cooling Water Systems.

  7. Mixed waste management facility groundwater monitoring report. Fourth quarter 1995 and 1995 summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    During fourth quarter 1995, seven constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility. No constituents exceeded final PDWS in samples from the upgradient monitoring wells. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents. Chloroethene, gross alpha, lead, mercury, and tetrachloroethylene also exceeded final PDWS in one or more wells. Elevated constituents were found in numerous Aquifer Zone IIB{sub 2} (Water Table) and Aquifer Zone IIB{sub 1} (Barnwell/McBean) wells and in three Aquifer Unit IIA (Congaree) wells. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

  8. Mixed Waste Management Facility (MWMF) groundwater monitoring report. First quarter 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    During first quarter 1993, eight constituents exceeded final Primary Drinking Water Standards in groundwater samples from downgradient monitoring wells at the Mixed Waste anagement Facility, the Old Burial Ground, the E-Area Vaults, and the proposed Hazardous Waste/Mixed Waste Disposal Vaults (HWMWDV). As in previous quarters, tritium and trichloroethylene were the most widespread constituents. Tetrachloroethylene, chloroethene, 1,1-dichloroethylene, gross alpha, lead, or nonvolatile beta levels also exceeded standards in one or more wells. The elevated constituents were found primarily in Aquifer Zone IIB{sub 2} (Water Table) and Aquifer Zone IIB{sub 1}, (Barnwell/McBean) wells. However, several Aquifer Unit IIA (Congaree) wells also contained elevated constituent levels. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to previous quarters.

  9. Mixed waste management facility groundwater monitoring report. Fourth quarter 1995 and 1995 summary

    International Nuclear Information System (INIS)

    1996-03-01

    During fourth quarter 1995, seven constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility. No constituents exceeded final PDWS in samples from the upgradient monitoring wells. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents. Chloroethene, gross alpha, lead, mercury, and tetrachloroethylene also exceeded final PDWS in one or more wells. Elevated constituents were found in numerous Aquifer Zone IIB 2 (Water Table) and Aquifer Zone IIB 1 (Barnwell/McBean) wells and in three Aquifer Unit IIA (Congaree) wells. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters

  10. Mixed waste management facility groundwater monitoring report. Fourth quarter 1996 and 1996 summary

    International Nuclear Information System (INIS)

    1997-03-01

    During fourth quarter 1996, nine constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility. No constituents exceeded final PDWS in samples from the upgradient monitoring wells. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents. Carbon tetrachloride, chloroethene, chloroform, 1,1-dichloroethylene, dichloromethane, gross alpha, and tetrachloroethylene also exceeded final PDWS in one or more wells. Elevated constituents were found in numerous Aquifer Zone llB2 (Water Table) and Aquifer Zone llB1 (Barnwell/McBean) wells and in six Aquifer Unit IIA (Congaree) wells. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters

  11. Quarterly Progress Report Fuels Development Operation: October - December 1959

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, J. J. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation; Tobin, J. C. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Physical Metallurgy; Minor, J. E. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuel Element Design; Evans, E. A. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Ceramic Fuels Development; Bush, S. H. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuels Fabrication Development

    1960-01-15

    The present Quarterly Report is the continuation of a series issued by the new Fuels Development operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations. Studies formerly reported by the Radiometallurgy, Metallography, and Welding and Corrosion Units, in addition to portions of the Fuels Technology work, are reported elsewhere.

  12. Quarterly Progress Report Fuels Development Operation: July - September 1957

    Energy Technology Data Exchange (ETDEWEB)

    Bush, S. H. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Physical Metallurgy; Minor, J. E. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuel Element Design; Evans, E. A. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Ceramic Fuels Development; Wallace, W. P. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuels Fabrication Development

    1957-10-15

    The present Quarterly Report is the continuation of a series issued by the new Fuels Development operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations. Studies formerly reported by the Radiometallurgy, Metallography, and Welding and Corrosion Units, in addition to portions of the Fuels Technology work, are reported elsewhere.

  13. Quarterly Progress Report Fuels Development Operation: January - March 1958

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, J. J. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation; Tobin, J. C. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Physical Metallurgy; Minor, J. E. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuel Element Design; Evans, E. A. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Ceramic Fuels Development; Bush, S. H. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuels Fabrication Development

    1958-04-15

    The present Quarterly Report is the continuation of a series issued by the new Fuels Development operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations. Studies formerly reported by the Radiometallurgy, Metallography, and Welding and Corrosion Units, in addition to portions of the Fuels Technology work, are reported elsewhere.

  14. MHD Coal-Fired Flow Facility. Quarterly/annual technical progress report, October-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    Dicks, J. B.; Chapman, J. N.; Crawford, L. W.

    1980-02-01

    In this Fourth Quarterly/Annual Report submitted under DOE contracts EX-76-C-01-1760 and DE-AC02-79ET10815, the University of Tennessee Space Institute (UTSI) reports on significant activity, task status, planned research, testing, and development, and conclusions for the Magnetohydrodynamics (MHD) Coal-Fired Flow Facility (CFFF) and the Research and Development Laboratory. Work on the CFFF progressed with only minor problems. Total construction activity for all site work presently awarded is nearly 98% complete. Water analysis shows that Woods Reservoir baseline conditions are within EPA or Tennessee drinking water standards. For the primary combustor, the vitiation heater and primary combustor fabrication drawings were completed and the nozzle design was completed. The drum module for the radiant slagging furnace was awarded. On the MHD Power Generator, development continued in several areas of advanced analysis including development of time-dependent models for use with the one-dimensional code. For seed regeneration, the tentative determination is that the Tomlinson Tampella is the most economically viable method. With regard to capped electrode erosion, investigations have shown that the major degradation of the cladding still present is at the leading edge of the capped anode. To alleviate this, plans are to hot work the noble metal in the bending operation. In resolving another problem, a system employing the modified line-reversal method has been assembled and successfully tested to measure absolute plasma temperatures.

  15. Mixed Waste Management Facility (MWMF) groundwater monitoring report. First quarter 1992

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, C.Y.

    1992-06-01

    During first quarter 1992, tritium, trichloroethylene, tetrachloroethylene, lead, antimony, I,I-dichloroethylene, 1,2-dichloroethane, gross alpha, mercury, nickel, nitrate, nonvolatile beta, and total alpha-emitting radium (radium-224 and radium-226) exceeded the US Environmental Protection Agency Primary Drinking Water Standards (PDWS) in groundwater samples from monitoring wells at the Mixed Waste Management Facility (MWMF) and adjacent facilities. Tritium and trichloroethylene were the most widespread constituents; 57 (49%) of the 116 monitored wells contained elevated tritium activities, and 21 (18%) wells exhibited elevated trichloroethylene concentrations Sixty-one downgradient wells screened in Aquifer Zone IIB2 (Water Table), Aquifer Zone IIB{sub 2} (Barnwell/McBean), and Aquifer Unit IIA (Congaree) contained constituents that exceeded the PDWS during first quarter 1992. Upgradient wells BGO 1D and HSB 85A, BC, and 85C did not contain any constituents that exceeded the PDWS. Upgradient well BGO 2D contained elevated tritium.

  16. Magnetohydrodynamic projects at the CDIF (Component Development and Integration Facility)

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    This quarterly technical progress report presents the tasks accomplished at the Component Development and Integration Facility during the fourth quarter of FY90. Areas of technical progress this quarter included: coal system development; seed system development; test bay modification; channel power dissipation and distribution system development; oxygen system storage upgrade; iron core magnet thermal protection system oxygen checkout; TRW slag rejector/CDIF slag removal project; stack gas/environmental compliance upgrade; coal-fired combustor support; 1A channels fabrication and assembly; support of Mississippi State University diagnostic testing; test operations and results; data enhancement; data analysis and modeling; technical papers; and projected activities. 2 tabs.

  17. Z-Area saltstone disposal facility groundwater monitoring report. First and second quarters 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    This report presents the results of groundwater sampling during the first and second quarters of 1997 in the Z-Area Saltstone Disposal Facility. This report presents only the data for sampling during the first half of 1997 as required by industrial Solid Waste Permit No. 025500-1603. For a detailed discussion of groundwater monitoring in the Z-Area Saltstone Disposal Facility, consult the 1996 Z-Area Saltstone Disposal Annual Report. Appendix A presents the proposed South Carolina Department of Health and Environmental Control Proposed Groundwater Monitoring Standards. Flagging criteria are described in Appendix B. In May 1997 SCDHEC granted approval for seven hydrocone sampling.

  18. Hot Gas Cleanup Test Facility for gasification and pressurized combustion. Quarterly report, October--December 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: carbonizer/pressurized circulating fluidized bed gas source; hot gas cleanup units to mate to all gas streams; combustion gas turbine; and fuel cell and associated gas treatment. The major emphasis during this reporting period was continuing the detailed design of the facility and integrating the particulate control devices (PCDs) into structural and process designs. Substantial progress in underground construction activities was achieved during the quarter. Delivery and construction of coal handling and process structural steel began during the quarter. Delivery and construction of coal handling and process structural steel began during the quarter. MWK equipment at the grade level and the first tier are being set in the structure.

  19. Power Systems Development Facility

    International Nuclear Information System (INIS)

    1993-06-01

    The objective of the PSDF would be to provide a modular facility which would support the development of advanced, pilot-scale, coal-based power systems and hot gas clean-up components. These pilot-scale components would be designed to be large enough so that the results can be related and projected to commercial systems. The facility would use a modular approach to enhance the flexibility and capability for testing; consequently, overall capital and operating costs when compared with stand-alone facilities would be reduced by sharing resources common to different modules. The facility would identify and resolve technical barrier, as well as-provide a structure for long-term testing and performance assessment. It is also intended that the facility would evaluate the operational and performance characteristics of the advanced power systems with both bituminous and subbituminous coals. Five technology-based experimental modules are proposed for the PSDF: (1) an advanced gasifier module, (2) a fuel cell test module, (3) a PFBC module, (4) a combustion gas turbine module, and (5) a module comprised of five hot gas cleanup particulate control devices. The final module, the PCD, would capture coal-derived ash and particles from both the PFBC and advanced gasifier gas streams to provide for overall particulate emission control, as well as to protect the combustion turbine and the fuel cell

  20. Mixed Waste Management Facility (MWMF) groundwater monitoring report. Fourth quarter 1992 and 1992 summary

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    During fourth quarter 1992, nine constituents exceeded final Primary Drinking Water Standards (PDWS) in one or more groundwater samples from monitoring wells at the Mixed Waste Management Facility (MWMF) and adjacent facilities. As in previous quarters, tritium and trichloroethylene were the most widespread constituents. Fifty-seven (48%) of the 120 monitoring wells, contained elevated tritium activities, and 23 (19%) contained elevated trichloroethylene concentrations. Total alpha-emitting radium, tetrachloroethylene, chloroethene, cadmium, 1,1-dichloroethylene, lead, or nonvolatile beta levels exceeded standards in one or more wells. During 1992, elevated levels of 13 constituents were found in one or more of 80 of the 120 groundwater monitoring wells (67%) at the MWMF and adjacent facilities. Tritium and trichloroethylene exceeded their final PDWS more frequently and more consistently than did other constituents. Tritium activity exceeded its final PDWS m 67 wells and trichloroethylene was. elevated in 28 wells. Lead, tetrachloroethylene, total alpha-emitting radium, gross alpha, cadmium, chloroethene, 1,1-dichloroethylene 1,2-dichloroethane, mercury, or nitrate exceeded standards in one or more wells during the year. Nonvolatile beta exceeded its drinking water screening level in 3 wells during the year.

  1. PFBC HGCU Test Facility. Technical progress report No. 24, Third quarter, CY 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This is the twenty-fourth and final Technical Progress Report submitted to the Department of Energy (DOE) in connection with the cooperative agreement between the DOE and Ohio Power Company for the Tidd PFBC Hot Gas Clean Up Test Facility. This report covers the work completed during the Third Quarter of CY 1995. All activity this quarter was directed toward the completion of the program final report. A draft copy of the final report was forwarded to DOE during this quarter, and DOE submitted their comments on the report to AEPSC. DOE requested that Westinghouse write an appendix to the report covering the performance of the fail-safe regenerator devices during Tad operation, and Westinghouse subsequently prepared the appendix. Additional DOE comments were incorporated into the report, and it will be issued in camera-ready form by the end of October, 1995, which is the program end date. Appendix 1 presents the results of filter candle posttest examination by Westinghouse performed on selected filter candles following final shutdown of the system.

  2. Oak Ridge Reservation Federal Facility Agreement: Quarterly report for the Environmental Restoration Program. Volume 2, January--March 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This report provides information about ER Program activities conducted on the Oak Ridge Reservation under the Federal Facility Agreement (FFA). Specifically, it includes information on milestones scheduled for completion during the reporting period as well as scheduled for completion during the next reporting period (quarter), accomplishments of the ER Program, concerns related to program work, and scheduled activities for the next quarter. It also provides a listing of the identity and assigned tasks of contractors performing ER Program work under the FFA.

  3. Oak Ridge Reservation Federal Facility Agreement. Quarterly report for the Environmental Restoration Program. Volume 4, July 1995--September 1995

    International Nuclear Information System (INIS)

    1995-10-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that are specified in the Oak Ridge Reservation Federal Facility Agreement (FFA) established between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA), and the Tennessee Department of Environment and Conservation (TDEC). The reporting period covered herein is July through September 1995 (fourth quarter of FY 1995). Sections 1.1 and 1.2 provide respectively the milestones scheduled for completion during the reporting period and a list of documents that have been proposed for transmittal during the following quarter but have not been approved as FY 1995 commitments

  4. Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2009-01-31

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, has routinely demonstrated gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This final report summarizes the results of the technology development work conducted at the PSDF through January 31, 2009. Twenty-one major gasification test campaigns were completed, for a total of more than 11,000 hours of gasification operation. This operational experience has led to significant advancements in gasification technologies.

  5. Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion Project. Quarterly report, April--June 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived as streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed Include the integration of the particulate control devices into coal utilization systems, on-line cleaning, techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing, Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: 1 . Carbonizer/Pressurized Circulating, Fluidized Bed Gas Source; 2. Hot Gas Cleanup Units to mate to all gas streams; 3. Combustion Gas Turbine; 4. Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during, this reporting period was continuing, the detailed design of the FW portion of the facility towards completion and integrating the balance-of-plant processes and particulate control devices (PCDS) into the structural and process designs. Substantial progress in construction activities was achieved during the quarter. Delivery and construction of the process structural steel is complete and the construction of steel for the coal preparation structure is complete.

  6. Instrumentation Design and Development Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — RTTC has facilities for design, development and fabrication of: custominstrumentation, mobile instrumentation, miniaturized instrumentation, wirelessinstrumentation,...

  7. PFBC HGCU Test Facility. Fourth quarterly technical progress report, CY 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    This is the thirteenth Technical Progress Report submitted to the Department of Energy (DOE) in connection with the cooperative agreement between the DOE and Ohio Power Company for the Tidd PFBC Hot Gas Clean Up Test Facility. This report covers the period of work completed during the Fourth Quarter of CY 1992. The following are highlights of the activities that occurred during this report period: Initial operation of the Advanced Particle Filter (APF) occurred during this quarter. The following table summarizes the operating dates and times. HGCU ash lockhopper valve plugged with ash. Primary cyclone ash pluggage. Problems with the coal water paste. Unit restarted warm 13 hours later. HGCU expansion joint No. 7 leak in internal ply of bellows. Problems encountered during these initial tests included hot spots on the APP, backup cyclone and instrumentation spools, two breakdowns of the backpulse air compressor, pluggage of the APF hopper and ash removal system, failure (breakage) of 21 filter candles, leakage of the inner ply of one (1) expansion joint bellows, and numerous other smaller problems. These operating problems are discussed in detail in a subsequent section of this report. Following shutdown and equipment inspection in December, design modifications were initiated to correct the problems noted above. The system is scheduled to resume operation in March, 1993.

  8. Technology Development Facility (TDF)

    International Nuclear Information System (INIS)

    Doggett, J.N.

    1982-01-01

    We have been studying small, driven, magnetic-mirror-based fusion reactors for the Technology Development Facility (TDF), that will test fusion reactor materials, components, and subsystems. Magnetic mirror systems are particularly interesting for this application because of their inherent steady-state operation, potentially high neutron wall loading, and relatively small size. Our design is a tandem mirror device first described by Fowler and Logan, based on the physics of the TMX experiments at Lawrence Livermore National Laboratory (LLNL). The device produces 20 MW of fusion power with a first-wall, uncollided 14-MeV neutron flux of 1.4 MW/m 2 on an area of approximately 8 m 2 , while consuming approximately 250 MW of electrical power. The work was done by a combined industrial-laboratory-university group

  9. Baseline gas turbine development program. Eighteenth quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, F W; Wagner, C E [comps.

    1977-04-30

    Progress is reported for a program whose goals are to demonstrate an experimental upgraded gas turbine powered automobile which meets the 1978 Federal Emissions Standards, has significantly improved fuel economy, and is competitive in performance, reliability, and potential manufacturing cost with the conventional piston engine powered, compact-size American automobile. Initial running of the upgraded engine took place on July 13, 1976. The engine proved to be mechanically sound, but was also 43% deficient in power. A continuing corrective development effort has to date reduced the power deficiency to 32%. Compressor efficiency was increased 2 points by changing to a 28-channel diffuser and tandem deswirl vanes; improved processing of seals has reduced regenerator leakage from about 5 to 2.5% of engine flow; a new compressor turbine nozzle has increased compressor turbine stage efficiency by about 1 point; and adjustments to burner mixing ports has reduced pressure drop from 2.8 to 2.1% of engine pressure. Key compressor turbine component improvements are scheduled for test during the next quarterly period. During the quarter, progress was also made on development of the Upgraded Vehicle control system; and instrumentation of the fourth program engine was completed by NASA. The engine will be used for development efforts at NASA LeRC.

  10. Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    None

    2003-07-01

    This report discusses Test Campaign TC12 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (SW) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). While operating as a gasifier, either air or oxygen can be used as the oxidant. Test run TC12 began on May 16, 2003, with the startup of the main air compressor and the lighting of the gasifier start-up burner. The Transport Gasifier operated until May 24, 2003, when a scheduled outage occurred to allow maintenance crews to install the fuel cell test unit and modify the gas clean-up system. On June 18, 2003, the test run resumed when operations relit the start-up burner, and testing continued until the scheduled end of the run on July 14, 2003. TC12 had a total of 733 hours using Powder River Basin (PRB) subbituminous coal. Over the course of the entire test run, gasifier temperatures varied between 1,675 and 1,850 F at pressures from 130 to 210 psig.

  11. POWER SYSTEMS DEVELOPMENT FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Unknown

    2002-11-01

    This report discusses test campaign GCT4 of the Kellogg Brown & Root, Inc. (KBR) transport reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The transport reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using one of two possible particulate control devices (PCDs). The transport reactor was operated as a pressurized gasifier during GCT4. GCT4 was planned as a 250-hour test run to continue characterization of the transport reactor using a blend of several Powder River Basin (PRB) coals and Bucyrus limestone from Ohio. The primary test objectives were: Operational Stability--Characterize reactor loop and PCD operations with short-term tests by varying coal-feed rate, air/coal ratio, riser velocity, solids-circulation rate, system pressure, and air distribution. Secondary objectives included the following: Reactor Operations--Study the devolatilization and tar cracking effects from transient conditions during transition from start-up burner to coal. Evaluate the effect of process operations on heat release, heat transfer, and accelerated fuel particle heat-up rates. Study the effect of changes in reactor conditions on transient temperature profiles, pressure balance, and product gas composition. Effects of Reactor Conditions on Synthesis Gas Composition--Evaluate the effect of air distribution, steam/coal ratio, solids-circulation rate, and reactor temperature on CO/CO{sub 2} ratio, synthesis gas Lower Heating Value (LHV), carbon conversion, and cold and hot gas efficiencies. Research Triangle Institute (RTI) Direct Sulfur Recovery Process (DSRP) Testing--Provide syngas in support of the DSRP commissioning. Loop Seal Operations--Optimize loop seal operations and investigate increases to previously achieved maximum solids-circulation rate.

  12. EVA Training and Development Facilities

    Science.gov (United States)

    Cupples, Scott

    2016-01-01

    Overview: Vast majority of US EVA (ExtraVehicular Activity) training and EVA hardware development occurs at JSC; EVA training facilities used to develop and refine procedures and improve skills; EVA hardware development facilities test hardware to evaluate performance and certify requirement compliance; Environmental chambers enable testing of hardware from as large as suits to as small as individual components in thermal vacuum conditions.

  13. Oak Ridge Reservation Federal Facility Agreement quarterly report for the Environmental Restoration Program, Volume 1, October--December 1992

    International Nuclear Information System (INIS)

    1993-01-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program which are specified in the Oak Ridge Reservation (ORR) Federal Facility Agreement (FFA) established between the US Department of Energy (DOE), the US Environmental Protection Agency (EPA), and the Tennessee Department of Environment and Conservation (TDEC). The reporting period covered is October through December 1992(first quarter of FY 1993). Sections 1.1 and 1.2 provide respectively the milestones scheduled for completion during the reporting period and a list of documents that have been proposed for transmittal during the following quarter but have not been formally approved as FY 1993 commitments. This first section is followed by: significant accomplishments; technical status at Y-12 operable units, Oak Ridge National Laboratory, Oak Ridge K-25 site, Clinch River, Oak Ridge Associated Universities, and technical oversight and technical programs; and response action contractor assignments

  14. POWER SYSTEMS DEVELOPMENT FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Unknown

    2002-05-01

    This report discusses test campaign GCT3 of the Halliburton KBR transport reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The transport reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using one of two possible particulate control devices (PCDs). The transport reactor was operated as a pressurized gasifier during GCT3. GCT3 was planned as a 250-hour test run to commission the loop seal and continue the characterization of the limits of operational parameter variations using a blend of several Powder River Basin coals and Bucyrus limestone from Ohio. The primary test objectives were: (1) Loop Seal Commissioning--Evaluate the operational stability of the loop seal with sand and limestone as a bed material at different solids circulation rates and establish a maximum solids circulation rate through the loop seal with the inert bed. (2) Loop Seal Operations--Evaluate the loop seal operational stability during coal feed operations and establish maximum solids circulation rate. Secondary objectives included the continuation of reactor characterization, including: (1) Operational Stability--Characterize the reactor loop and PCD operations with short-term tests by varying coal feed, air/coal ratio, riser velocity, solids circulation rate, system pressure, and air distribution. (2) Reactor Operations--Study the devolatilization and tar cracking effects from transient conditions during transition from start-up burner to coal. Evaluate the effect of process operations on heat release, heat transfer, and accelerated fuel particle heat-up rates. Study the effect of changes in reactor conditions on transient temperature profiles, pressure balance, and product gas composition. (3) Effects of Reactor Conditions on Syngas Composition--Evaluate the effect of air distribution, steam

  15. Oak Ridge Reservation Federal Facility Agreement for the Environmental Restoration Program. Volume 1, Quarterly report, October--December 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    This Oak Ridge Reservation Federal Facility Agreement Quarterly Report for the Environmental Restoration Program was prepared to satisfy requirements for progress reporting on Environmental Restoration Program (ER) activities as specified in the Oak Ridge Reservation Federal Facility Agreement (FFA) established between the US Department of Energy (DOE), the US Environmental Protection Agency, and the Tennessee Department of Environment and Conservation. The reporting period covered in this document is October through December 1995. This work was performed under Work Breakdown Structure 1.4.12.2.3.04 (Activity Data Sheet 8304). Publication of this document meets two FFA milestones. The FFA Quarterly Report meets an FFA milestone defined as 30 days following the end of the applicable reporting period. Appendix A of this report meets the FFA milestone for the Annual Removal Action Report for the period FYs 1991--95. This document provides information about ER Program activities conducted on the Oak Ridge Reservation under the FFA. Specifically, it includes information on milestones scheduled for completion during the reporting period, as well as scheduled for completion during the next reporting period (quarter); accomplishments of the ER Program; concerns related to program work; and scheduled activities for the next quarter. It also provides a listing of the identity and assigned tasks of contractors performing ER Program work under the FFA.

  16. US energy industry financial developments, 1991 third quarter

    International Nuclear Information System (INIS)

    1991-01-01

    Net income for the 218 energy companies included in this report was 15 percent lower in the third quarter of 1991 than in the third quarter of 1990. Declining income from oil and natural gas production, chemical operations, and coal operations resulted in a 33-percent fall in income for fossil fuel companies. The other category of energy companies included in this report, rate-regulated utilities, recorded essentially no change in income

  17. Safeguards material control and accounting at licensed processing facilities. Quarterly report, July--September 1977

    International Nuclear Information System (INIS)

    Sacks, I.J.

    1978-12-01

    Objective was to develop the methodology and software needed for assessing Material Control and Accounting (MC and A) systems at fixed site nuclear fuel facilities. The assessment of an MC and A system requires five steps: target identification, event set generation, MC and A response determination, component performance models, and thermo-physical property data base. Progress on each is reported

  18. Design, fabrication and operation of a biomass fermentation facility. First quarterly report, October 1-December 31, 1978

    Energy Technology Data Exchange (ETDEWEB)

    O' Neil, D.J.; Colcord, A.R.; Bery, M.K.; Day, S.W.; Roberts, R.S.; El-Barbary, I.A.; Havlicek, S.C.; Anders, M.E.; Sondhi, D.

    1978-01-01

    The objective of this project is to design, fabricate, and operate a fermentation facility which will demonstrate on a pilot-scale level (3 oven-dry tons (ODT) per day of feedstock) the economic and technical feasibility of producing anhydrous ethyl alcohol from lignocellulosic biomass residues (wood, corn stover, and wheat straw principally). The resultant process development unit (PDU) will be flexibly designed so as to evaluate current and projected unit operations, materials of construction, chemical and enzymatic systems which offer the potential of significant technological and economic breakthroughs in alcohol production from biomass. The principal focus of the project is to generate fuels from biomass. As such, in addition to alcohol which can be used as a transportation fuel, by-products are to be directed where possible to fuel applications. The project consists of two parts: (1) conceptual design, and (2) detailed engineering design. The first quarter's activities have focused on a critical review of several aspects of the conceptual design of the 3 ODT/day PDU, viz.: (1) biomass cost, availability, and characterization; (2) pretreatment processes for lignocellulosic residues; (3) hydrolytic processes (enzymatic and acidic); (4) fermentation processes; (5) alcohol recovery systems; (6) by-product streams utilization; and (7) process economics.

  19. Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending December 31, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Cash, R.J.; Dukelow, G.T.; Forbes, C.J.

    1993-03-01

    This is the seventh quarterly report on the progress of activities addressing safety issues associated with Hanford Site high-level radioactive waste tanks that contain ferrocyanide compounds. In the presence of oxidizing materials, such as nitrates or nitrites, ferrocyanide can be made to explode in the laboratory by heating it to high temperatures [above 285{degrees}C (545{degrees}F)]. In the mid 1950s approximately 140 metric tons of ferrocyanide were added to 24 underground high-level radioactive waste tanks. An implementation plan (Cash 1991) responding to the Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990) was issued in March 1991 describing the activities that were planned and underway to address each of the six parts of Recommendation 90-7. A revision to the original plan was transmitted to US Department of Energy by Westinghouse Hanford Company in December 1992. Milestones completed this quarter are described in this report. Contents of this report include: Introduction; Defense Nuclear Facilities Safety Board Implementation Plan Task Activities (Defense Nuclear Facilities Safety Board Recommendation for enhanced temperature measurement, Recommendation for continuous temperature monitoring, Recommendation for cover gas monitoring, Recommendation for ferrocyanide waste characterization, Recommendation for chemical reaction studies, and Recommendation for emergency response planning); Schedules; and References. All actions recommended by the Defense Nuclear Facilities Safety Board for emergency planning by Hanford Site emergency preparedness organizations have been completed.

  20. M-area hazardous waste management facility groundwater monitoring and corrective-action report, First quarter 1995, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    This report, in three volumes, describes the ground water monitoring and c corrective-action program at the M-Area Hazardous Waste Management Facility (HWMF) at the Savannah River Site (SRS) during the fourth quarter 1994 and first quarter 1995. Concise description of the program and considerable data documenting the monitoring and remedial activities are included in the document. This is Volume 1 covering the following topics: sampling and results; hydrogeologic assessment; water quality assessment; effectiveness of the corrective-action program; corrective-action system operation and performance; monitoring and corrective-action program assessment; proposed monitoring and corrective-action program modifications. Also included are the following appendicies: A-standards; B-flagging criteria; C-figures; D-monitoring results tables; E-data quality/usability assessment.

  1. M-area hazardous waste management facility groundwater monitoring and corrective-action report, First quarter 1995, Volume 1

    International Nuclear Information System (INIS)

    1995-05-01

    This report, in three volumes, describes the ground water monitoring and c corrective-action program at the M-Area Hazardous Waste Management Facility (HWMF) at the Savannah River Site (SRS) during the fourth quarter 1994 and first quarter 1995. Concise description of the program and considerable data documenting the monitoring and remedial activities are included in the document. This is Volume 1 covering the following topics: sampling and results; hydrogeologic assessment; water quality assessment; effectiveness of the corrective-action program; corrective-action system operation and performance; monitoring and corrective-action program assessment; proposed monitoring and corrective-action program modifications. Also included are the following appendicies: A-standards; B-flagging criteria; C-figures; D-monitoring results tables; E-data quality/usability assessment

  2. Illinois Association for Counseling and Development (IACD) Quarterly, 1990.

    Science.gov (United States)

    Illovsky, Michael E., Ed.

    1990-01-01

    This document consists of the four issues of the "IACD Quarterly" published in 1990. Articles in this volume include: (1) "A Comprehensive Program for Reducing School Anxieties in College Students" (David Ross); (2) "Issues in Child Custody Determination in Illinois" (Amy Jo Buwick); (3) "Finding Meaning in the Here and Now Through Gestalt Therapy…

  3. Development program to support industrial coal gasification. Quarterly report 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-15

    The Development Program to Support Industrial Coal Gasification is on schedule. The efforts have centered on collecting background information and data, planning, and getting the experimental program underway. The three principal objectives in Task I-A were accomplished. The technical literature was reviewed, the coals and binders to be employed were selected, and tests and testing equipment to be used in evaluating agglomerates were developed. The entire Erie Mining facility design was reviewed and a large portion of the fluidized-bed coal gasification plant design was completed. Much of the work in Task I will be experimental. Wafer-briquette and roll-briquette screening tests will be performed. In Task II, work on the fluidized-bed gasification plant design will be completed and work on a plant design involving entrained-flow gasifiers will be initiated.

  4. PFBC HGCU Test facility. Technical progress report, Fourth quarter, CY 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

    During this quarter, the Tidd Hot Gas Clean Up System completed a 691-hour test run which began during the third quarter. Table 1 summarizes all test runs since initial operation. Following this test run the system was shut down and the filter opened for inspection and recandling. The system remained out of service during the remainder of the quarter. In addition to monitoring and evaluating the performance of the HGCU system during testing, engineering effort was devoted to posttest inspection of the APF (Advanced Particle Filter) and evaluation of the effects of totally spoiling the primary cyclone. In addition, the authors worked with Westinghouse in the selection of replacement candles that were installed during the fourth quarter. During the unit outage this quarter, the primary cyclone upstream of the APF was modified to force all of the ash to pass through the cyclone and enter the APF without using spoiling air. Appendices to this report describe the dust shroud support strap design; an analysis of the effect of support-transferred vibrations on the failure of ceramic candle filters; the Tidd APF operation; the Tidd APF boroscope inspection; a general inspection of Tidd filter internals; tally of Tidd filters; ash formations in the W-APF-October 1994 post-test inspection; characterization of the as-manufactured and PFBC-exposed 3M CVI-SiC composite filter matrix; strength characterization of the first and second generation candle filters after 1,705 hours of PFBC operation at Tidd; and filters used in the December 1994 recandling effort at Tidd.

  5. Center for Supercomputing Research and Development: Quarterly report, First quarter, 1987

    Energy Technology Data Exchange (ETDEWEB)

    1987-06-01

    This paper discusses progress on hardware and applications of superconducting design. The topic titles covered are: hardware development, architecture research, operating system research and development, Cedar Fortran, symbolic processing, compiler research, scientific workstation environment, and numerical library. (LSP)

  6. Quarterly Progress Report Metallurgy Development Operation: January - March 1964

    Energy Technology Data Exchange (ETDEWEB)

    Wick, O. J. [Hanford Site (HNF), Richland, WA (United States). Metallurgy Development Operation; Last, G. A. [Hanford Site (HNF), Richland, WA (United States). Metallurgy Development Operation. Fuels Design; Minor, J. E. [Hanford Site (HNF), Richland, WA (United States). Metallurgy Development Operation. Metal Fabrication Development; Nelson, T. C. [Hanford Site (HNF), Richland, WA (United States). Metallurgy Development Operation. Plutonium Product Development; Stewart, R. W. [Hanford Site (HNF), Richland, WA (United States). Metallurgy Development Operation. Plutonium Metallurgy Development

    1964-05-20

    This progress report focuses on two topics: Metallic Fuels Technology and Metallic Fuel Development. Within Metallic Fuels Technology, the following subtopics are covered: new fuels design, fabrication development, and fuel evaluation. The addition of recently obtained swelling data on tubular fuel elements to the previously accumulated information has prompted a refinement to the swelling model. Analysis of data for the N-outer tube, the N-inner tube and the K-single tube geometries has led to separate empirical expressions for each of the three shapes in place of the single expression formerly used for all geometries. Within Metallic Fuel Development, the irradiation of thorium fuel continued. Three tubular elements containing 2.35 wt% U235 and 1 wt% Zr have reached an exposure of 5200 Mwd/ton in the ETR P-7 facility. Weight measurements indicate that the elements have undergone 0.8% volume increase. This figure is very close to the theoretical minimum volume expansion expected from fission product production.

  7. EDS coal liquefaction process development. Phase V. Quarterly technical progress report, July 1-September 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-02-01

    This report is the tenth Quarterly Technical Progress Report for US Department of Energy Cooperative Agreement No. DE-FC01-77ET10069 (formerly EF-77-A-01-2893) for Exxon Donor Solvent (EDS) Coal Liquefaction Process Development - Phase V. The Laboratory Process Research and Development studies were conducted at various Exxon Research and Engineering Co. (ER and E) facilities: Research and Development Division at Baytown, Texas; Products Research Division at Linden, New Jersey; and the Exxon Research and Development Laboratories at Baton Rouge, Louisiana. The Engineering Research and Development studies were performed at the Synthetic Fuels Engineering and Exxon Engineering Technology Departments of ER and E at Florham Park, New Jersey. The information dealing with the Management, Detailed Engineering, and Procurement activities related to revamp of the FLEXICOKING Prototype Unit was generated at Exxon Company, USA, Houston, Texas, and Exxon Engineering - Project Management Department of ER and E, Florham Park, New Jersey. The information dealing with operation of the 250 T/D Exxon Coal Liquefaction Pilot Plant (ECLP) was generated at Exxon Company, USA, Houston, Texas.

  8. Biomass power for rural development. Quarterly report, January 1, 1997--April 1, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.T.

    1997-05-01

    The following information summarizes the major areas of project activities accomplished during the last quarter. Activities addressing conversion technology have been geared towards gathering information and drawing comparisons to specific project need. Of major benefit was the trip taken to Denmark by Project Manager, Edward Woolsey. The first section of this report provides an overview of his experiences and findings. As a follow up to this trip, representatives from Iowa State University and from IES Utilities will also visit some of these facilities. Their information will be included in the next report. At the supply development level, the RC&D has been working to identify and organize producers of swithgrass. A major accomplishment has been the formation of the Prairie Lands Bio-Products group. This association will explore different business structures that energy crop producers can use to supply biomass and to effectively market their materials to the energy industry. Thus, the group will begin to interact with IES in the next few months to determine how the supplier and the utility must interact to establish a working relationship and to efficiently provide biomass as a boiler fuel. Other major areas of focus for the group will be the development and implementation of risk management strategies to overcome income loss and allow acreage increases during market development. These strategies include the development of niche markets for swithgrass, the use of CRP lands, and outside sources of cost share for establishment.

  9. Developing standardized facility contingency plans

    International Nuclear Information System (INIS)

    Davidson, D.A.

    1993-01-01

    Texaco consists of several operating departments that are, in effect, independent companies. Each of these departments is responsible for complying with all environmental laws and regulations. This includes the preparation by each facility to respond to an oil spill at that location. For larger spills, however, management of the response will rest with corporate regional response teams. Personnel from all departments make up the regional teams. In 1990, Congress passed the Oil Pollution Act. In 1991, the US Coast Guard began developing oil spill response contingency plan regulations, which they are still working on. Meanwhile, four of the five west coast states have also passed laws requiring contingency plans. (Only Hawaii has chosen to wait and see what the federal regulations will entail). Three of the states have already adopted regulations. Given these laws and regulations, along with its corporate structure, Texaco addressed the need to standardize local facility plans as well as its response organization. This paper discusses how, by working together, the Texaco corporate international oil spill response staff and the Texaco western region on-scene commander developed: A standard contingency plan format crossing corporate boundaries and meeting federal and state requirements. A response organization applicable to any size facility or spill. A strategy to sell the standard contingency plan and response organization to the operating units

  10. Bulk Shielding Facility quarterly report, July, August, and September of 1976

    Energy Technology Data Exchange (ETDEWEB)

    Hurt, III, S. S.; Lance, E. D.; Thomas, J. R.

    1977-06-01

    The BSR operated at an average power level of 1637 kW for 50.05 percent of the time during July, August, and September. Water-quality control in both the reactor primary and secondary cooling systems was satisfactory. The BSR was operated at low and variable power during this quarter for 27.327 hours as part of the training programs for nuclear reactor operator trainees from Memphis State University. The PCA was also used in the above-mentioned training programs and was operated on six occasions when the Oak Ridge Associated Universities or Memphis State University students actively participated in training laboratories.

  11. F-Area Hazardous Waste Management Facility Semiannual Corrective Action Report, First and Second Quarter 1998, Volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.

    1998-10-30

    This report addresses groundwater quality and monitoring data during first and second quarter 1998 for the F-Area Hazardous Waste management Facility (HWMF). The report fulfills the semiannual reporting requirements of Module III, Section D, of the 1995 Resource Conservation and Recovery Act (RCRA) Renewal Permit (South Carolina Hazardous and Mixed Waste Permit SC1-890-008-989), effective October 5, 1995 (hereafter referred to as the RCRA permit), and Section C of the Underground Injection Control Permit Application hereafter referred to as the Section C of the Underground Injection Control Permit Application (hereafter referred to as the UIC permit). The HWMF is described in the Introduction to Module III, Section C, of the RCRA permit.

  12. Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Cash, R.J.; Dukelow, G.T.; Forbes, C.J.; Meacham, J.E.

    1993-06-01

    This is the eighth quarterly report on the progress of activities addressing safety issues associated with Hanford Site high-level radioactive waste tanks that contain ferrocyanide compounds. In the presence of oxidizing materials, such as nitrates or nitrites, ferrocyanide can be made to explode in the laboratory by heating it to high temperatures [above 285{degree}C (545{degree}F)]. In the mid 1950s, approximately 140 metric tons of ferrocyanide were added to 24 underground high-level radioactive waste tanks. An implementation plan (Cash 1991) responding to the Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990) was issued in March 1991 describing the activities that were planned and underway to address each of the six parts of Recommendation 90-7. A revision to the original plan was transmitted to the US Department of Energy by Westinghouse Hanford Company in December 1992.

  13. F-Area Hazardous Waste Management Facility Semiannual Corrective Action Report, First and Second Quarter 1998, Volume I and II

    International Nuclear Information System (INIS)

    Chase, J.

    1998-01-01

    This report addresses groundwater quality and monitoring data during first and second quarter 1998 for the F-Area Hazardous Waste management Facility (HWMF). The report fulfills the semiannual reporting requirements of Module III, Section D, of the 1995 Resource Conservation and Recovery Act (RCRA) Renewal Permit (South Carolina Hazardous and Mixed Waste Permit SC1-890-008-989), effective October 5, 1995 (hereafter referred to as the RCRA permit), and Section C of the Underground Injection Control Permit Application hereafter referred to as the Section C of the Underground Injection Control Permit Application (hereafter referred to as the UIC permit). The HWMF is described in the Introduction to Module III, Section C, of the RCRA permit

  14. Fast Breeder Blanket Facility. Quarterly progress report, April 1, 1978--June 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Clikeman, F. M. [ed.

    1978-06-01

    The work performed in the reporting period was primarily concerned with the initial measurements and checkout of the Purdue Fast Breeder Blanket Facility (TASK C). The safety calculations for the ''as built'' are also presented and compared with the initial safety calculations (TASK B). Safety calculations on the FBBR facility have been completed for a variety of new flooded-dry combinations. Specifically the effect of adding boron carbide to the transformer regions was investigated. The investigation showed the stabilizing effect of the boron carbide in the flooded cases while the effect in the dry cases is minimal. Measurements of the k/sub eff/ of the FBBF facility, of the effectiveness of the shielding, and of the radiation levels in the rooms surrounding the laboratory have been completed and compare well with the calculations presented in the license application.

  15. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report July 1 – September 30, 2006

    Energy Technology Data Exchange (ETDEWEB)

    DL Sisterson

    2006-10-01

    Description. Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real time. Raw and processed data are then sent daily to the ACRF Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual data stream, site, and month for the current year and (2) site and fiscal year dating back to 1998.

  16. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report April 1 – June 30, 2006

    Energy Technology Data Exchange (ETDEWEB)

    DL Sisterson

    2006-07-01

    Description. Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real time. Raw and processed data are then sent daily to the ACRF Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual data stream, site, and month for the current year; and (2) site and fiscal year dating back to 1998.

  17. Development Economics and Method: A Quarter Century of ABCDE

    OpenAIRE

    Kaushik Basu; Andrew Foster

    2015-01-01

    This, the twenty-fifth anniversary of the Annual Bank Conference on Development Economics (ABCDE) and also of the Washington Consensus, is a good time to take stock of development economics. What have we learned? What do we need to unlearn? What is the right methodology for development economics so that future knowledge is on firmer footing? These are important questions and this year’s ABCDE and this introduction is a stocktaking of where we stand on these questions. Development economics ha...

  18. Baseline Gas Turbine Development Program. Fourteenth quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, F W; Wagner, C E

    1976-04-30

    Progress is reported for a Baseline Gas Turbine Development Program sponsored by the Heat Engine Systems Branch, Division of Transportation Energy Conservation (TEC) of the Energy Research and Development Administration (ERDA). Structurally, this program is made up of three parts: (1) documentation of the existing automotive gas turbine state-of-the-art; (2) conduction of an extensive component improvement program; and (3) utilization of the improvements in the design, and building of an Upgraded Engine capable of demonstrating program goals.

  19. Safeguards Technology Development Program 1st Quarter FY 2018 Report

    Energy Technology Data Exchange (ETDEWEB)

    Prasad, Manoj K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2018-01-10

    LLNL will evaluate the performance of a stilbene-based scintillation detector array for IAEA neutron multiplicity counting (NMC) applications. This effort will combine newly developed modeling methodologies and recently acquired high-efficiency stilbene detector units to quantitatively compare the prototype system performance with the conventional He-3 counters and liquid scintillator alternatives.

  20. Development of a Control System for the Teat-End Vacuum in Individual Quarter Milking Systems

    Science.gov (United States)

    Ströbel, Ulrich; Rose-Meierhöfer, Sandra; Öz, Hülya; Brunsch, Reiner

    2013-01-01

    Progress in sensor technique and electronics has led to a decrease in the costs of electronic and sensor components. In modern dairy farms, having udders in good condition, a lower frequency of udder disease and an extended service life of dairy cows will help ensure competitiveness. The objective of this study was to develop a teat-end vacuum control system with individual quarter actor reaction. Based on a review of the literature, this system is assumed to protect the teat tissue. It reduces the mean teat-end vacuum in the maximum vacuum phase (b) to a level of 20 kPa at a flow rate of 0.25 L/min per quarter. At flow rates higher than 1.50 L/min per quarter, the teat-end vacuum can be controlled to a level of 30 kPa, because in this case it is desirable to have a higher vacuum for the transportation of the milk to the receiver. With this system it is possible for the first time to supply the teat end with low vacuum at low flow rates and with higher vacuum at increasing flow rates in a continuous process with a three second reaction-rate on individual quarter level. This system is completely automated. PMID:23765272

  1. Baseline Gas Turbine Development Program ninth quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, C.E.

    1975-01-31

    Progress is reported for a program to demonstrate by 1976 an experimental gas turbine powered automobile which meets the 1978 Federal Emissions Standards, has significantly improved fuel economy, and is competitive in performance, reliability, and potential manufacturing cost with the conventional piston engine powered, standard size American automobile. NASA completed the first phase of their baseline engine heat balance tests, and an upgraded engine compressor is being scaled for test. EPA completed their report on vehicle tests including emissions and vehicle performance, and a new endurance engine is on test. Significant development progress was made on both fixed and variable geometry combustors. After 45 hours of engine operation with Vendor A ceramic regenerator, no significant deterioration of the matrix, seals, or elastomeric mount was encountered. Ceramic regenerator stress analysis has commenced. Additional developments in non-nickel oxide regenerator rubbing seals are encouraging. The first preprototype integrated control system is in vehicle operation. Control adaptation for variable inlet guide vanes and water injection is progressing. AiRefrac turbine wheels were verified dimensionally and are being processed for engine testing. Water injection tests with a four nozzle system were run, and additional performance documentation of variable inlet guide vanes was obtained. Linerless insulation is on test in the free rotor engine, the new endurance engine, and a performance engine. The free rotor engine completed test cell checkout and was installed in a vehicle. Vehicle checkout, including a preprototype integrated control, is underway. Detailed specifications of the upgraded engine were written.

  2. Advanced turbine systems program conceptual design and product development. Quarterly report, February 1995--April 1995

    Energy Technology Data Exchange (ETDEWEB)

    Karstensen, K.W.

    1995-07-01

    This Quarterly Technical Progress Report covers the period February 1, 1995, through April 30, 1995, for Phase II of the Advanced Turbine Systems (ATS) Program by Solar Turbines Incorporated under DOE contract No. DE-AC21-93MC30246. The objective of Phase II of the ATS Program is to provide the conceptual design and product development plan for an ultra high efficiency, environmentally superior and cost competitive industrial gas turbine system to be commercialized by the year 2000. A secondary objective is to begin early development of technologies critical to the success of ATS. Tasks 1, 2, 3, 5, 6 and 7 of Phase II have been completed in prior quarters. Their results have been discussed in the applicable quarterly reports and in their respective topical reports. With the exception of Task 7, final editions of these topical reports have been submitted to the DOE. This quarterly report, then, addresses only Task 4 and the nine subtasks included in Task 8, {open_quotes}Design and Test of Critical Components.{close_quotes} These nine subtasks address six ATS technologies as follows: (1) Catalytic Combustion - Subtasks 8.2 and 8.5, (2) Recuperator - Subtasks 8.1 and 8.7, (3) Autothermal Fuel Reformer - Subtask 8.3, (4) High Temperature Turbine Disc - Subtask 8.4, (5) Advanced Control System (MMI) - Subtask 8.6, and (6) Ceramic Materials - Subtasks 8.8 and 8.9. Major technological achievements from Task 8 efforts during the quarter are as follows: (1) The subscale catalytic combustion rig in Subtask 8.2 is operating consistently at 3 ppmv of NO{sub x} over a range of ATS operating conditions. (2) The spray cast process used to produce the rim section of the high temperature turbine disc of Subtask 8.4 offers additional and unplanned spin-off opportunities for low cost manufacture of certain gas turbine parts.

  3. Baseline Gas Turbine Development Program. Tenth quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, F.W.; Wagner, C.E.

    1975-04-30

    Progress is reported for a program to demonstrate by 1976 an experimental gas turbine powered automobile which meets the 1978 Federal Emissions Standards, has significantly improved fuel economy, and is competitive in performance, reliability, and potential manufacturing cost with the conventional piston engine powered, standard size American automobile. A fuel control system is being developed to allow program evaluation of a very promising low emissions, single stage, fixed geometry proprietary burner. Ceramic regenerators are under test in the free-rotor vehicle, and some have completed 30 hours of performance evaluation. Three-dimensional ceramic regenerator transient thermal and structural analysis programs are operational. Initial friction and wear test fixture results show that zirconium oxide fully stabilized by yttrium oxide is an effective substitute for nickel oxide in a plasma sprayed seal. A preprototype control system was adapted for variable inlet guide vane control in a vehicle installation. An evaluation of the free-rotor accessory drive concept in a vehicle showed no serious mechanical integrity problems. Simplifications are being made to the water injection system; significant metallurgical analysis of observed erosion/corrosion problems was accomplished. Variable inlet guide vane aerodynamic loss characteristics were determined. Generally satisfactory results with linerless insulation are resulting in extended use and application. Pattern work for the upgraded engine housing and the power turbine wheel castings are in process. A computer design analysis of the regenerator drive gears was made, and an analysis was completed of a three peripheral roller regenerator support and drive proposal for the upgraded engine.

  4. NST Quarterly

    International Nuclear Information System (INIS)

    1995-01-01

    NST Quarterly reports current development in nuclear science and technology in Malaysia. It keeps readers informed on the progress of research, services, application of nuclear science and technology, and other technical news. It highlights MINT activities and also announces coming events

  5. Biomass power for rural development. Quarterly report, April 2, 1997--July 2, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.T.

    1997-10-01

    The information in this report summarizes the major areas of project activities accomplished during the last quarter. Activities concerning conversion technologies have continued to be focused on gaining information and comparing similar systems world wide with project needs. One major effort was a trip to Denmark and Finland; the first section of the report details some of the trip highlights. The second section is a writeup of a previous trip. Additional conversion work undertaken at Iowa State University on the development of material handling, gas sampling, and gas analysis equipment is detailed. An update on the installation of field trial plots is also included. Very brief summaries are provided of quarterly activities, briquette production from switchgrass, and the development of geographical information systems are also included. 8 figs., 1 tab.

  6. Hot gas cleanup test facility for gasification and pressurized combustion. Quarterly technical progress report, July 1--September 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the existing Transport Reactor gas source and Hot Gas Cleanup Units: Carbonizer/Pressurized Circulating Fluidized Bed Gas Source; hot Gas Cleanup Units to mate to all gas streams; and Combustion Gas Turbine. Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF).

  7. Development of an advanced high efficiency coal combustor for boiler retrofit. Quarterly report, November 1986--January 1987

    Energy Technology Data Exchange (ETDEWEB)

    Rini, M.J.; LaFlesh, R.C. [Combustion Engineering, Inc., Windsor, CT (United States); Beer, J.M.; Togan, M.A.; Yu, T.U. [Massachusetts Inst. of Tech., Cambridge, MA (United States); McGowan, J.G. [Univ. of Massachusetts, MA (US)

    1987-05-06

    During the quarter from October 1986 to January 1987 the following technical progress was made: (1) Initiated a literature study focusing on optimized burner aerodynamics and design methodologies for high efficiency swirl generation devices, (2) Completed design of Swirler Test Facility (STF) to be used for comparative swirler evaluations, and (3) Initiated facility preparation at MIT for thermal atomization studies and high shear viscosity measurements.

  8. Strategic Petroleum Reserve: Annual/quarterly report

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-16

    Section 165 of the Energy Policy and Conservation Act (Public Law 94-163), as amended, requires the Secretary of Energy to submit annual and quarterly reports to the President and the Congress on activities of the Strategic Petroleum Reserve. This report combines the fourth quarter 1993 Quarterly Report with the 1993 Annual Report. Key activities described include appropriations; life extension planning; expansion planning; Strategic Petroleum Reserve oil acquisition; the oil stabilization program; and the refined petroleum product reserve test programs. Sections of this report also describe the program mission; the storage facility development program; environmental compliance; budget and finance; and drawdown and distribution.

  9. Lead Coolant Test Facility Development Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Paul A. Demkowicz

    2005-06-01

    A workshop was held at the Idaho National Laboratory on May 25, 2005, to discuss the development of a next generation lead or lead-alloy coolant test facility. Attendees included representatives from the Generation IV lead-cooled fast reactor (LFR) program, Advanced Fuel Cycle Initiative, and several universities. Several participants gave presentations on coolant technology, existing experimental facilities for lead and lead-alloy research, the current LFR design concept, and a design by Argonne National Laboratory for an integral heavy liquid metal test facility. Discussions were focused on the critical research and development requirements for deployment of an LFR demonstration test reactor, the experimental scope of the proposed coolant test facility, a review of the Argonne National Laboratory test facility design, and a brief assessment of the necessary path forward and schedule for the initial stages of this development project. This report provides a summary of the presentations and roundtable discussions.

  10. Biomass power for rural development. Quarterly report, October 3, 1998--January 1, 1999

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.T.

    1999-02-01

    Information and education activities for this quarter include both the monthly progress activities with some copies of materials developed and a copy of the annual report prepared for the Leopold Center for Sustainable Agriculture. The Leopold Center is a project partner and the primary sponsor of the information and education activities. The Leopold annual report references many prepared documents and assorted presentation materials. The Energy and Geological Resources Division of the Iowa Department of Natural Resources sponsors a meeting four times a year in order to bring members of the Iowa biomass energy community together to share information. In this quarter the Stakeholders meeting was held on October 21, 1998, in Des Moines Iowa. The first phase of the Geographic Information System (GIS) efforts have been completed and a final report with a map presentation of materials will be included in the next Quarterly Report. A meeting with Ed Gray of The Antares Group and project staff/cooperators was held October 23, 1998. The authors discussed the Niagara Project and the efforts to value the biomass material and partner contributions. Niagara has identified a value to the grid support capabilities of the dispersed generation.

  11. Imperial County, geothermal development. Quarterly report, October 1-December 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    Geothermal development activities have increased during the October to December period. Nine power plant projects are proceeding, this includes two constructed facilities, one facility under construction, three facilities scheduled to begin construction in 1982, and three facilities in the planning or permitting stage. Geothermal exploration activities are continuing with activities in East Brawley, Truckhaven, and near the Superstition Mountains. Interest in direct heat development seems to be increasing. The City of El Centro project is under construction and there are several direct heat projects in preliminary planning stages. Permitting, planning, and waste disposal activities are reviewed.

  12. Development program for a 200-kW, c-w gyrotron. Quarterly report No. 7, January-March 1981

    International Nuclear Information System (INIS)

    Tancredi, J.J.; Caplan, M.; Sandoval, J.J.; Jordan, E.; Matranga, V.A.

    1981-01-01

    The objective of this program is the design and development of a millimeter-wave device to produce 200 kW of continuous-wave power at 60 GHz. The device, which will be a gyrotron oscillator, will be compatible with power delivery to an electron-cyclotron plasma. Smooth control of rf power output over a 17 dB range is required, and the device should be capable of operation into a severe time-varying rf load mismatch. An interim program goal is to demonstrate operation at 100 ms pulse widths by 31 December 1981. During this quarter, progress was made in the areas of tube, solenoid, and facility construction. Two magnetron injection gun assemblies were completed, and one was partially evaluated as a gun tester. The superconducting solenoid was assembled, but a vacuum leak prevented early delivery in March. Construction began on the gyrotron test facility by enclosing the area and providing bake-out and vacuum processing utilities

  13. Biomass power for rural development. Quarterly report, July 1--September 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.T.

    1998-10-01

    In this quarter a large amount of time was spent doing project planning and budget preparation for the fiscal years 1998 and 1999. Many issues of long-term strategic planning and budgeting depend on the availability of Federal support, including financial, technical and political. It has become increasingly obvious that several significant barriers must be overcome in order to reach the final project goal of commercial replication of the technology. This report describes switchgrass conversion development, production activities, environmental analysis planning, and information and education. Appendices discuss the biomass project, sediment delivery, successful establishment of switchgrass, and legislative support for the biomass project.

  14. Detector development and test facility

    International Nuclear Information System (INIS)

    Reeder, D.D.

    1993-01-01

    Following the ideas presented in the proposal to the DoE, we have begun to acquire the equipment needed to design, develop construct and test the electronic and mechanical features of detectors used in High Energy Physics Experiments. A guiding principle for the effort is to achieve integrated electronic and mechanical designs which meet the demanding specifications of the modern hadron collider environment yet minimize costs. This requires state of the art simulation of signal processing as well as detailed calculations of heat transfer and finite element analysis of structural integrity

  15. Development of cancer therapy facility of HANARO

    International Nuclear Information System (INIS)

    Jun, Byung Jin; Hwang, S. Y.; Kim, M. J. and others

    2000-04-01

    Facilities of the research and clinical treatments of neutron capture therapy using HANARO are developed, and they are ready to install. They are BNCT irradiation facility and prompt gamma neutron activatiion analysis facility. Since every horizontal neutron facility of HANARO is long and narrow tangential beam tube, it is analysed that sufficient epithermal neutrons for the BNCT cannot be obtained but sufficient thermal neutrons can be obtained by a filter composed of silicon and bismuth single crystals. Since the thermal neutron penetaration increases significantly when the crystals are cooled, a filter cooled by liquid nitrogen is developed. So as to avoid interference with the reactor operation, a water shutter is developed. The irradiation room is designed for the temporary surgical operation as well. Handling tools to remove activated beam port plug and to install water shutter and filter are developed. The basic structure of the irradiation room is already installed and most of other parts are ready to install. Since no free beam port is available for the prompt gamma neutron activation analysis, a method obtaining almost pure thermal neutrons by the vertical diffraction of extra beam for the polarized neutron spectrometer is developed. This method is confirmed by analysis and experiments to give high enough neutron beam. Equipment and devices are provided to install this facility

  16. Development of cancer therapy facility of HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Byung Jin; Hwang, S. Y.; Kim, M. J. and others

    2000-04-01

    Facilities of the research and clinical treatments of neutron capture therapy using HANARO are developed, and they are ready to install. They are BNCT irradiation facility and prompt gamma neutron activatiion analysis facility. Since every horizontal neutron facility of HANARO is long and narrow tangential beam tube, it is analysed that sufficient epithermal neutrons for the BNCT cannot be obtained but sufficient thermal neutrons can be obtained by a filter composed of silicon and bismuth single crystals. Since the thermal neutron penetaration increases significantly when the crystals are cooled, a filter cooled by liquid nitrogen is developed. So as to avoid interference with the reactor operation, a water shutter is developed. The irradiation room is designed for the temporary surgical operation as well. Handling tools to remove activated beam port plug and to install water shutter and filter are developed. The basic structure of the irradiation room is already installed and most of other parts are ready to install. Since no free beam port is available for the prompt gamma neutron activation analysis, a method obtaining almost pure thermal neutrons by the vertical diffraction of extra beam for the polarized neutron spectrometer is developed. This method is confirmed by analysis and experiments to give high enough neutron beam. Equipment and devices are provided to install this facility.

  17. M-Area and Metallurgical Laboratory Hazardous Waste Management Facilities Groundwate Monitoring and Corrective-Action Report, First and Second Quarters 1998, Volumes I, II, & III

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.

    1998-10-30

    This report describes the groundwater monitoring and corrective-action program at the M-Area Hazardous waste Management Facility (HWMF) and the Metallurgical Laboratory (Met Lab) HWMF at the Savannah river Site (SRS) during first and second quarters 1998. This program is required by South Carolina Hazardous Waste Permit SC1-890-008-989 and Section 264.100(g) of the South Carolina Hazardous Waste Management Regulations. Report requirements are described in the 1995 RCRA Renewal Permit, effective October 5, 1995, Section IIIB.H.11.b for the M-Area HWMF and Section IIIG.H.11.b for the Met Lab HWMF.

  18. Biomass power for rural development. Quarterly report, April 3--July 1, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.T.

    1998-10-01

    In this quarter a large amount of time was spent doing project planning and budget preparation for the fiscal years 1998 and 1999. Many issues of long-term strategic planning and budgeting depend on the availability of Federal support, including financial, technical and political. It has become increasingly obvious that several significant barriers must be overcome in order to reach the final goal of commercial replication of the technology. Technical barriers include the designing of a cost effective harvest, storage, transport, process and conversion system. While farmers in this region have many decades of experience in harvest, storage and transport of grass, switchgrass presents new challenges due to the harvest requirements and the switchgrass yield potential. The author has identified two locations in the United States that have similar material handling situations, one site in Minnesota the other in Oregon. He has visited the Minnesota site in order to learn from their experience and they may visit the Oregon site in the future. The processing technology remains in a stage of development. As he grows closer to the time for a test co-fire he is beginning to include additional test objectives which individually seem minor, but when taken together provide drivers which impact overall machinery requirement decisions. The next quarter will provide additional levels of detail. This report describes progress in switchgrass conversion development, production activities, environmental analysis planning, and information and education activities.

  19. National Ignition Facility frequency converter development

    International Nuclear Information System (INIS)

    Barker, C.E.; Auerbach, J.M.; Adams, C.H.

    1996-01-01

    A preliminary error budget for the third harmonic converter for the National Ignition Facility (NIF) laser driver has been developed using a root-sum-square-accumulation of error sources. Such a budget sets an upper bound on the allowable magnitude of the various effects that reduce conversion efficiency. Development efforts on crystal mounting technology and crystal quality studies are discussed

  20. Planning and Development of a Conservation Facility.

    Science.gov (United States)

    Coley, Betty A.

    This paper reviews the current literature on the preservation of library materials and develops an overview of the state-of-the-art for conservation programs. The 13 references provided are concerned with the preservation of book materials, the design of processes and facilities to prevent or retard deterioration, development of disaster planning,…

  1. Industrial advanced turbine systems: Development and demonstration. Quarterly report, January 1--March 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-08-01

    The US Department of Energy (DOE) has initiated a program for advanced turbine systems (ATS) that will serve industrial power generation markets. The objective of the cooperative agreements granted under the program is to join the DOE with industry in research and development that will lead to commercial offerings in the private sector. The ATS will provide ultra-high efficiency, environmental superiority, and cost competitiveness. The ATS will foster (1) early market penetration that enhances the global competitiveness of US industry, (2) public health benefits resulting from reduced exhaust gas emissions of target pollutants, (3) reduced cost of power used in the energy-intensive industrial marketplace, and (4) the retention and expansion of the skilled US technology base required for the design, development and maintenance of state-of-the-art advanced turbine products. The Industrial ATS Development and Demonstration program is a multi-phased effort. Solar Turbines Incorporated (Solar) has participated in Phases 1 and 2 of the program. On September 14, 1995 Solar was awarded a Cooperative Agreement for Phases 3 and 4 of the program. Phase 3 of the work is separated into two subphases: Phase 3A entails Component Design and Development; Phase 3B will involve Integrated Subsystem Testing. Phase 4 will cover Host Site Testing. As of the end of the reporting period work on the program is 29.1% complete (24.7% last quarter). Work on the Mercury 50 development and ATS technology development portions of the program (WBS 10000 et seq) is 48.9% complete (41.6% last quarter). Estimates of percent complete are based upon milestones completed. In order to maintain objectivity in assessing schedule progress, Solar uses a 0/100 percent complete assumption for milestones rather than subjectively estimating progress toward completion of milestones. Cost and schedule variance information is provided in Section 4.0 Program Management.

  2. DeBeNe Test Facilities for Fast Breeder Development

    International Nuclear Information System (INIS)

    Storz, R.

    1980-10-01

    This report gives an overview and a short description of the test facilities constructed and operated within the collaboration for fast breeder development in Germany, Belgium and the Netherlands. The facilities are grouped into Sodium Loops (Large Facilities and Laboratory Loops), Special Equipment including Hot Cells and Reprocessing, Test Facilities without Sodium, Zero Power Facilities and In-pile Loops including Irradiation Facilities

  3. Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Cash, R.J.; Dukelow, G.T.; Forbes, C.J.; Meacham, J.E.

    1993-10-01

    This is the ninth quarterly report on the progress of activities that address safety issues associated with Hanford Site high-level radioactive waste tanks containing ferrocyanide compounds. Milestones completed this quarter include (1) a report on the credibility of hot spots and a recommendation on infrared scans; (2) a document discussing the strength and limitations of proposed moisture monitoring technologies; (3) limited calibration of the neutron probe in simulant-filled drums; (4) a report interpreting data from auger surface samples of ferrocyanide tank 241-BY-104; (5) a document on the effect of possible catalyst, initiator, and diluents on ferrocyanide reactivity; (6) a report on small scale sensitivity tests of ferrocyanide flowsheet simulants; and (7) preparation and shipment of T Plant simulants for calorimetric and dryout tests.

  4. Industrial advanced turbine systems: Development and demonstration. Quarterly report, October 1--December 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    The US DOE has initiated a program for advanced turbine systems (ATS) that will serve industrial power generation markets. The ATS will provide ultra-high efficiency, environmental superiority, and cost competitiveness. The Industrial ATS Development and Demonstration program is a multi-phased effort. Solar Turbines Incorporated (Solar) has participated in Phases 1 and 2 of the program. On September 14, 1995 Solar was awarded a Cooperative Agreement for Phases 3 and 4 of the program. Phase 3 of the work is separated into two subphases: Phase 3A entails Component Design and Development; Phase 3B will involve Integrated Subsystem Testing. Phase 4 will cover Host Site Testing. Forecasts call for completion of the program within budget as originally estimated. Scheduled completion is forecasted to be approximately 3 years late to original plan. This delay has been intentionally planned in order to better match program tasks to the anticipated availability of DOE funds. To ensure the timely realization of DOE/Solar program goals, the development schedule for the smaller system (Mercury 50) and enabling technologies has been maintained, and commissioning of the field test unit is scheduled for May of 2000. As of the end of the reporting period work on the program is 24.7% complete (22.8% last quarter). Work on the Mercury 50 development and ATS technology development portions of the program (WBS 10000 et seq) is 41.6% complete. Although a great amount of work occurred in the quarter, a significant amount of this work entailed the revision and rerelease of several Mercury 50 drawings. Estimates of percent compete are based upon milestones completed. In order to maintain objectivity in assessing schedule progress, Solar uses a 0/100 percent complete assumption for milestones rather than subjectively estimating progress toward completion of milestones. Cost and schedule variation information is provided in Section 4.0 Program Management.

  5. Decontamination Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Oh, Won Zin; Jung, Chong Hun; Choi, Wang Kyu; Won, Hui Jun; Kim, Gye Nam

    2004-02-01

    Technology development of surface decontamination in the uranium conversion facility before decommissioning, technology development of component decontamination in the uranium conversion facility after decommissioning, uranium sludge treatment technology development, radioactive waste soil decontamination technology development at the aim of the temporary storage soil of KAERI, Optimum fixation methodology derivation on the soil and uranium waste, and safety assessment methodology development of self disposal of the soil and uranium waste after decontamination have been performed in this study. The unique decontamination technology applicable to the component of the nuclear facility at room temperature was developed. Low concentration chemical decontamination technology which is very powerful so as to decrease the radioactivity of specimen surface under the self disposal level was developed. The component decontamination technology applicable to the nuclear facility after decommissioning by neutral salt electro-polishing was also developed. The volume of the sludge waste could be decreased over 80% by the sludge waste separation method by water. The electrosorption method on selective removal of U(VI) to 1 ppm of unrestricted release level using the uranium-containing lagoon sludge waste was tested and identified. Soil decontamination process and equipment which can reduce the soil volume over 90% were developed. A pilot size of soil decontamination equipment which will be used to development of real scale soil decontamination equipment was designed, fabricated and demonstrated. Optimized fixation methodology on soil and uranium sludge was derived from tests and evaluation of the results. Safety scenario and safety evaluation model were development on soil and uranium sludge aiming at self disposal after decontamination

  6. Preliminary design for a maglev development facility

    Energy Technology Data Exchange (ETDEWEB)

    Coffey, H.T.; He, J.L.; Chang, S.L.; Bouillard, J.X.; Chen, S.S.; Cai, Y.; Hoppie, L.O.; Lottes, S.A.; Rote, D.M. [Argonne National Lab., IL (United States); Zhang, Z.Y. [Polytechnic Univ., Brooklyn, NY (United States); Myers, G.; Cvercko, A. [Sterling Engineering, Westchester, IL (United States); Williams, J.R. [Alfred Benesch and Co., Chicago, IL (United States)

    1992-04-01

    A preliminary design was made of a national user facility for evaluating magnetic-levitation (maglev) technologies in sizes intermediate between laboratory experiments and full-scale systems. A technical advisory committee was established and a conference was held to obtain advice on the potential requirements of operational systems and how the facility might best be configured to test these requirements. The effort included studies of multiple concepts for levitating, guiding, and propelling maglev vehicles, as well as the controls, communications, and data-acquisition and -reduction equipment that would be required in operating the facility. Preliminary designs for versatile, dual 2-MVA power supplies capable of powering attractive or repulsive systems were developed. Facility site requirements were identified. Test vehicles would be about 7.4 m (25 ft) long, would weigh form 3 to 7 metric tons, and would operate at speeds up to 67 m/s (150 mph) on a 3.3-km (2.05-mi) elevated guideway. The facility would utilize modular vehicles and guideways, permitting the substitution of levitation, propulsion, and guideway components of different designs and materials for evaluation. The vehicle would provide a test cell in which individual suspension or propulsion components or subsystems could be tested under realistic conditions. The system would allow economical evaluation of integrated systems under varying weather conditions and in realistic geometries.

  7. Power Systems Development Facility. Environmental Assessment

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    The objective of the PSDF would be to provide a modular facility which would support the development of advanced, pilot-scale, coal-based power systems and hot gas clean-up components. These pilot-scale components would be designed to be large enough so that the results can be related and projected to commercial systems. The facility would use a modular approach to enhance the flexibility and capability for testing; consequently, overall capital and operating costs when compared with stand-alone facilities would be reduced by sharing resources common to different modules. The facility would identify and resolve technical barrier, as well as-provide a structure for long-term testing and performance assessment. It is also intended that the facility would evaluate the operational and performance characteristics of the advanced power systems with both bituminous and subbituminous coals. Five technology-based experimental modules are proposed for the PSDF: (1) an advanced gasifier module, (2) a fuel cell test module, (3) a PFBC module, (4) a combustion gas turbine module, and (5) a module comprised of five hot gas cleanup particulate control devices. The final module, the PCD, would capture coal-derived ash and particles from both the PFBC and advanced gasifier gas streams to provide for overall particulate emission control, as well as to protect the combustion turbine and the fuel cell.

  8. Heat source component development program. Quarterly report for April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    Foster, E.L. Jr. (comp.)

    1977-07-01

    This is the third in a series of quarterly reports describing the results of several experimental programs being conducted at Battelle-Columbus to develop components for advanced radioisotope heat source applications. The heat sources will for the most part be used in advanced static and dynamic power conversion systems. The specific component development efforts which are described include: improved selective and nonselective vents for helium release from the fuel containment; an improved reentry member and an improved impact member, singly and combined. The unitized reentry-impact member (RIM) is under development to be used as a bifunctional ablator. The development of a unitized reentry-impact member (RIM) has been stopped and the efforts are being redirected to the evaluation of materials that could be used in the near term for the module housing of the General Purpose Heat Source (GPHS). This redirection will be particularly felt in the selection of (improved) materials for reentry analysis and in the experimental evaluation of materials in impact tests. Finally thermochemical supporting studies are reported.

  9. Development of Diagnostic Technology for Substation Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kweon, D.J.; Yoon, J.Y. [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1998-09-01

    This report contains the conceptual design of predictive diagnostic system for KEPCO 765kV substation apparatus which will be operated in 2001. Various kinds of techniques in the world for power transformer and GIS monitoring were examined, then the integrated diagnosis system configuration which will be most effective in our future substation was suggested. In addition, the development of the optimum life management for substation facilities. development of a system to measure the ESDD of substation insulator surfaces at a distance and application study of the degradation sensor(PCS) were described also. (author) 55 refs., 27 figs., 68 tabs.

  10. Atlantic Richfield Hanford Company process technology and process development. Quarterly report, July 1976--September 1976

    Energy Technology Data Exchange (ETDEWEB)

    1976-11-01

    This quarterly report is the second in a series intended to provide information on research and engineering activities being performed to improve the processing of irradiated reactor fuels, the production of plutonium, and the management of resultant chemical wastes.

  11. H-Area Hazardous Waste Management Facility Corrective Action Report, Third and Fourth Quarter 1998, Volumes I and II

    International Nuclear Information System (INIS)

    Chase, J.

    1999-01-01

    The groundwater in the uppermost aquifer beneath the H-Area Hazardous Waste Management Facility (HWMF), also known as the H-Area Seepage Basins, at the Savannah Site (SRS) is monitored periodically for selected hazardous and radioactive constituents. This report presents the results of the required groundwater monitoring program

  12. Advanced Turbine Systems Program: Conceptual design and product development. Quarterly report, February--April 1994

    Energy Technology Data Exchange (ETDEWEB)

    Benjamin, G.J.

    1994-06-01

    Objective (Phase II) is to develop an industrial gas turbine system to operate at a thermal efficiency of 50% (ATS50) with efficiency enhancements to be added as they become possible. During this quarter, Solar`s engine design team has refined both the 1- and 2-spool cycle concepts, to determine sensitivity to key component efficiencies, cooling air usage and origin, and location of compressor surge lines. The refined analysis included more detailed component work such as compressor and turbine design; different speed trade-offs for the low-and high-pressure compressor in the 1-spool configuration were examined for the best overall compressor efficiency. High-temperature and creep testing of recuperator candidate materials continued. Creep, yield, and proportional limit were measured for foil thicknesses 0.0030--0.0050 for Type 347 ss, Inconel 625, and Haynes 230. Combustor design work included preliminary layout of a multi-can annular combustor integrated into the main engine layout. During the subscale catalytic combustion rig testing, NOx emissions < 5 ppmv were measured. Integration of the engine concept designs into the full power plant system designs has started.

  13. Trend chart: biogas. First quarter 2016

    International Nuclear Information System (INIS)

    Cavaud, Denis

    2016-05-01

    This publication presents the biogas industry situation of continental France and overseas territories during the first quarter 2016: total connected load of biogas power plants, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus power and type, evolution forecasts of biogas power generation, detailed regional results, biomethane injection in natural gas distribution systems, methodology used

  14. Trend chart: biogas. Forth quarter 2016

    International Nuclear Information System (INIS)

    Cavaud, Denis

    2017-02-01

    This publication presents the biogas industry situation of continental France and overseas territories during the forth quarter 2016: total connected load of biogas power plants, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus power and type, evolution forecasts of biogas power generation, detailed regional results, biomethane injection in natural gas distribution systems, methodology used

  15. Trend chart: biogas. Second quarter 2016

    International Nuclear Information System (INIS)

    Cavaud, Denis

    2016-08-01

    This publication presents the biogas industry situation of continental France and overseas territories during the Second quarter 2016: total connected load of biogas power plants, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus power and type, evolution forecasts of biogas power generation, detailed regional results, biomethane injection in natural gas distribution systems, methodology used

  16. Trend chart: biogas. Third quarter 2016

    International Nuclear Information System (INIS)

    Cavaud, Denis

    2016-11-01

    This publication presents the biogas industry situation of continental France and overseas territories during the third quarter 2016: total connected load of biogas power plants, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus power and type, evolution forecasts of biogas power generation, detailed regional results, biomethane injection in natural gas distribution systems, methodology used

  17. Artist conception of the Avian Development Facility

    Science.gov (United States)

    2003-01-01

    The Avian Development Facility (ADF) supports 36 eggs in two carousels, one of which rotates to provide a 1-g control for comparing to eggs grown in microgravity. The ADF was designed to incubate up to 36 Japanese quail eggs, 18 in microgravity and 18 in artificial gravity. The two sets of eggs were exposed to otherwise identical conditions, the first time this is been accomplished in space. Eggs are preserved at intervals to provide snapshots of their development for later analysis. Quails incubate in just 15 days, so they are an ideal species to be studied within the duration of space shuttle missions. Further, several investigators can use the same specimens to address different questions. The ADF originated in NASA's Shuttle Student Involvement program in the 1980s and was developed under the NASA Small Business Irnovation Research program. In late 2001, the ADF made its first flight and carried eggs used in two investigations.

  18. 1Q/2Q00 M-Area and Metallurgical Laboratory Hazardous Waste Management Facilities Groundwater Monitoring and Corrective-Action Report - First and Second Quarters 2000 - Volumes I, II, and II

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.

    2000-10-24

    This report describes the groundwater monitoring and corrective-action program at the M-Area Hazardous Waste Management Facility (HWMF) and the Metallurgical Laboratory (Met Lab) HWMF at the Savannah River site (SRS) during first and second quarters of 2000.

  19. Industrial advanced turbine systems: Development and demonstration. Quarterly report, July 1--September 30, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The US DOE has initiated a program for advanced turbine systems (ATS) that will serve industrial power generation markets. The ATS will foster (1) early market penetration that enhances the global competitiveness of US industry, (2) public health benefits resulting from reduced exhaust gas emissions of target pollutants, (3) reduced cost of power used in the energy-intensive industrial marketplace and (4) the retention and expansion of the skilled US technology base required for the design, development and maintenance of state-of-the-art advanced turbine products. The Industrial ATS Development and Demonstration program is a multi-phased effort. Solar Turbines Incorporated (Solar) has participated in Phases 1 and 2 of the program. On September 14, 1995 Solar was awarded a Cooperative Agreement for Phases 3 and 4 of the program. Phase 3 of the work is separated into two subphases: Phase 3A entails Component Design and Development; Phase 3B will involve Integrated Subsystem Testing. Phase 4 will cover Host Site Testing. Forecasts call for completion of the program within budget as originally estimated. Scheduled completion is forecasted to be approximately 3 years late to original plan. Significant efforts were spent this quarter to reforecast and control expenditures due to Solar`s and DOE`s current funding and resource constraints. Selective reductions and delays in program activities were identified and implemented. Although these actions will increase technical risk and the attainment of stretch goals, it is not anticipated that the schedule for initial test units or the attainment of basic program performance requirements will be impacted. As of the end of the reporting period work on the program is 22.80% complete based upon milestones completed. This measurement is considered quite conservative as numerous drawings on the Mercury 50 are near release. Variance information is provided in Section 4.0-Program Management.

  20. High-energy gas-fracturing development. Quarterly report, October-December 1982

    Energy Technology Data Exchange (ETDEWEB)

    Cuderman, J.F.

    1983-02-01

    The purpose of this study is to develop and optimize the High Energy Gas Fracturing (HEGF) technique to produce multiple fractures around a wellbore in order to stimulate natural-gas production in Devonian shale. The HEGF technique uses a wellbore charge of a propellant tailored to produce pressure loading in the borehole that avoids crushing yet produces multiple fractures radiating from the wellbore. The multiple-fracture regime has been characterized and releated to parameters such as borehole size, pressure risetime, and surface-wave velocity. Pressure risetimes and peak pressures, measured for different propellants in boreholes to specify a propellant for a desired peak pressure and pressure risetime. Semiempirical models, using results from previous experiments, successfully relate stress, acceleration, and fracture radii in surrounding rock to peak pressure and pressure risetime. A finite-element model also has been developed which predicts fracture type and direction of fractures as a function of pressure loading, in situ stress, and material properties. A full-scale HEGF system has been developed for application in gas-well-stimulation experiments in Devonian shale. During this quarter, a proof test of the full-scale HEGF was conducted at the Nevada Test Site (NTS). The designed pressure pulse of 0.5 ms risetime was achieved, and the tamp remained in place during the test. The borehole was successfully cleared posttest. Multiple fracturing was verified with a downhole TV camera. The test of the full-scale hardware and its operational capability was successful. As a result, the HEGF system is ready for application in gas-well-stimulation experiments in Devonian shale. Tests were conducted to determine worst-case accident scenarios to establish sensitivity to shock and fire. There appears to be no risk of initiation resulting from shock or breakage of the propellant-canister segments.

  1. ARM Operations Quarterly Report October 1-December 31, 2013

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, Jimmy W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-12-31

    The U.S. Department of Energy requires national user facilities to report time-based operating data. This quarterly report is written to comply with this requirement. This reports on the first quarter facility statistics.

  2. F-Area Hazardous Waste Management Facility Corrective Action Report - Third and Fourth Quarter 1999, Volumes I and II

    International Nuclear Information System (INIS)

    Chase, J.

    2000-01-01

    Savannah River Site (SRS) monitors groundwater quality at the F-Area Hazardous Waste management Facility (HWMF) and provides results of this monitoring to the South Carolina Department of Health and Environmental Control (SCDHEC) semiannually as required by the Resource Conservation and Recovery Act (RCRA) permit. SRS also performs monthly sampling of the Wastewater Treatment Unit (WTU) effluent in accordance with Section C of the Underground Injection Control (UIC) application

  3. Large sample NAA facility and methodology development

    International Nuclear Information System (INIS)

    Roth, C.; Gugiu, D.; Barbos, D.; Datcu, A.; Aioanei, L.; Dobrea, D.; Taroiu, I. E.; Bucsa, A.; Ghinescu, A.

    2013-01-01

    A Large Sample Neutron Activation Analysis (LSNAA) facility has been developed at the TRIGA- Annular Core Pulsed Reactor (ACPR) operated by the Institute for Nuclear Research in Pitesti, Romania. The central irradiation cavity of the ACPR core can accommodate a large irradiation device. The ACPR neutron flux characteristics are well known and spectrum adjustment techniques have been successfully applied to enhance the thermal component of the neutron flux in the central irradiation cavity. An analysis methodology was developed by using the MCNP code in order to estimate counting efficiency and correction factors for the major perturbing phenomena. Test experiments, comparison with classical instrumental neutron activation analysis (INAA) methods and international inter-comparison exercise have been performed to validate the new methodology. (authors)

  4. Sports Facilities Development and Urban Generation

    OpenAIRE

    Maassoumeh Barghchi; Dasimah B.   Omar; Mohd S.   Aman

    2009-01-01

    Problem statement: One major issue on sports facilities construction is the question of their funding and justification for investment. Due to, requirement of huge money for construction, constant maintenance costs and ancillary needs, which are almost certainly with substantial public investment, therefore, sports facilities have been considered. Further, sports facilities construction boom have been started for more than two decades. Approach: Recent sports facilities construction was not p...

  5. Isotopic power materials development. Quarterly progress report for period ending March 31, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Schaffhauser, A.C.

    1976-06-01

    The second in a series of quarterly reports for Technology and Space Applications materials programs conducted by the Metals and Ceramics Division of Oak Ridge National Laboratory for the Nuclear Research and Applications Division of ERDA is presented. These quarterly reports replace the monthly and annual reports previously issued on this work. The areas of research covered include high-temperature alloys for space isotopic heat sources, physical and mechanical metallurgy of heat source containment materials, isotope Brayton system materials support, and space nuclear flight systems hardware. (TFD)

  6. HYBRID SULFUR ELECTROLYZER DEVELOPMENT, NHI WORK PACKAGE N-SR07TC0301, FY07 FIRST QUARTER REPORT

    Energy Technology Data Exchange (ETDEWEB)

    Summers, W

    2006-12-20

    The proof of concept of SO2 electrolysis for the hybrid sulfur (HyS) process is the second priority research target of the DOE Nuclear Hydrogen Initiative's thermochemical program for FY07. The proof of concept of the liquid-phase option must be demonstrated at the single cell level for an extended run times (>100 hours). The rate of development of HyS will depend on the identification of a promising membrane or an alternative means for controlling sulfur formation. Once successful long-duration operation has been demonstrated, SRNL will develop a multi-cell stack that can be connected to the H2SO4 decomposer being developed by SNL for the S-I ILS for a Hybrid Sulfur Integrated Laboratory-Scale Experiment during FY 2008. During the first quarter of FY07, SRNL continued the component development and membrane development activities with the goal of identifying and characterizing improved electrodes, electrocatalysts, membranes and MEA configurations which could then be tested at larger scale in the SDE test facility. A modified glass cell was fabricated to allow measurements of sulfur dioxide (SO2) transport across membrane samples at elevated temperatures (up to 70 C). This testing also includes evaluating SO2 transport in different sulfuric acid concentrations (30-70 wt%). A new potentiostat/frequency analyzer was installed for determining ionic conductivity of membranes. This instrument enhances our capabilities to characterize membrane, electrocatalyst and MEA properties and performance. Continuing work from FY06, evaluations were preformed on various commercial and experimental membranes and electrocatalyst materials for the SDE. Several different types of commercially-available membranes were analyzed for sulfur dioxide transport as a function of acid strength including perfluorinated sulfonic acid (PFSA), sulfonated polyetherketone-ketone, and poly-benzimidazole (PBI) membranes. Experimental membranes from the sulfonated diels-alder polyphenylenes (SDAPP

  7. Training development in Juzbado's Fuel Cycle Facility

    International Nuclear Information System (INIS)

    Perez, A.; Cunado, E.; Ortiz, D.

    2003-01-01

    In Juzbado's fuel cycle facility, because of the special activities developed, training is a very important issues. Training has been evolved, due to changes on the standards applicable each moment, and also due to the technological resources available. Both aspects have resulted in an evolution of the documents referred to training, such as training programs procedures, Radiation Protection Manual as well as the teaching methods. In the report we are going to present, we will show more precisely the changes that take place, referring to the different training methods used, present training sanitations, and the improvements already planned in training subjects as well as tools used, accomplishing with the legislation and improving in our effort of a better assimilation of the necessary knowledge. (Author)

  8. Fusion Development Facility Machine Design Aspects

    Science.gov (United States)

    Smith, J. P.; Chan, V. S.; Garofalo, A. M.; Stambaugh, R. D.; Wong, C. P. C.

    2008-11-01

    To fill the gap prior to building a fusion demonstration power plant (DEMO), a Fusion Development Facility (FDF) is proposed. As currently configured, FDF is a copper, water-cooled coil machine capable of running continuously for several weeks with the goal to test several blanket configurations in its lifetime. To accommodate multiple changes in blankets, a machine configuration must be chosen that allows for the efficient remote exchange. The TF coil configuration drives the primary maintenance approach decision. A TF coil with joints similar to DIII-D and Alcator C-Mod, allows for one maintenance approach while a continuously wound TF coil drives a different approach. The base machine design parameters are described. The different machine configuration options are presented which consider the design aspects for the machine including alignment of the first wall and divertor, coolant access, and exchange of the blanket.

  9. F-Area Hazardous Waste Management Facility groundwater monitoring report, Third and fourth quarters 1995: Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    Groundwater at the F-Area Hazardous Waste Management Facility (HWMF) is monitored in compliance with applicable regulations. Monitoring results are compared to the South Carolina Department of Health and Environmental Control (SCDHEC) Groundwater Protection Standard (GWPS). Historically and currently, gross alpha, nitrates, nonvolatile beta, and tritium are among the primary constituents to exceed standards. Numerous other radionuclides and hazardous constituents also exceed the GWPS in the groundwater during the second half of 1995, notably cadmium, lead, radium-226, radium-228, strontium-90, and total alpha-emitting radium. The elevated constituents were found primarily in the water table (aquifer zone IIB{sub 2}), however, several other aquifer unit monitoring wells contained elevated levels of constituents. Water-level maps indicate that the groundwater flow rates and directions at the F-Area HWMF have remained relatively constant since the basins ceased to be active in 1988.

  10. H-Area Hazardous Waste Management Facility groundwater monitoring report, Third and fourth quarters 1995: Volume 1

    International Nuclear Information System (INIS)

    1996-03-01

    Groundwater at the H-Area Hazardous Waste Management Facility (HWMF) is monitored in compliance with applicable regulations. Monitoring results are compared to the South Carolina Department of Health and Environmental control (SCDHEC) Groundwater Protection Standard (GWPS). Historically as well as currently, nitrate-nitrite as nitrogen, nonvolatile beta, and tritium have been among the primary constituents to exceed standards. Other radionuclides and hazardous constituents also exceeded the GWPS in the second half of 1995. Elevated constituents were found primarily in the water table (Aquifer Zone IIB 2 ), however, constitutents exceeding standards also occurred in several different aquifer zones monitoring wells. Water-level maps indicate that the groundwater flow rates and directions at the H-Area HWMF have remained relatively constant since the basins ceased to be active in 1988

  11. F-Area Hazardous Waste Management Facility groundwater monitoring report, Third and fourth quarters 1995: Volume 1

    International Nuclear Information System (INIS)

    1996-03-01

    Groundwater at the F-Area Hazardous Waste Management Facility (HWMF) is monitored in compliance with applicable regulations. Monitoring results are compared to the South Carolina Department of Health and Environmental Control (SCDHEC) Groundwater Protection Standard (GWPS). Historically and currently, gross alpha, nitrates, nonvolatile beta, and tritium are among the primary constituents to exceed standards. Numerous other radionuclides and hazardous constituents also exceed the GWPS in the groundwater during the second half of 1995, notably cadmium, lead, radium-226, radium-228, strontium-90, and total alpha-emitting radium. The elevated constituents were found primarily in the water table (aquifer zone IIB 2 ), however, several other aquifer unit monitoring wells contained elevated levels of constituents. Water-level maps indicate that the groundwater flow rates and directions at the F-Area HWMF have remained relatively constant since the basins ceased to be active in 1988

  12. Inertial Confinement Fusion quarterly report, January--March 1995. Volume 5, No. 2

    International Nuclear Information System (INIS)

    1995-01-01

    The ICF quarterly report is published by the Inertial Confinement Fusion Program at the Lawrence Livermore National Laboratory. Topics included this quarter include: the role of the National Ignition Facility in the development of Inertial Confinement Fusion, laser-plasma interactions in large gas-filled hohlraums, evolution of solid-state induction modulators for a heavy-ion recirculator, the National Ignition Facility project, and terminal-level relaxation in Nd-doped laser material

  13. Inertial Confinement Fusion quarterly report, January--March 1995. Volume 5, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The ICF quarterly report is published by the Inertial Confinement Fusion Program at the Lawrence Livermore National Laboratory. Topics included this quarter include: the role of the National Ignition Facility in the development of Inertial Confinement Fusion, laser-plasma interactions in large gas-filled hohlraums, evolution of solid-state induction modulators for a heavy-ion recirculator, the National Ignition Facility project, and terminal-level relaxation in Nd-doped laser material.

  14. Developments in radiation, stimulation and observation facilities in luminescence measurements

    DEFF Research Database (Denmark)

    Bøtter-Jensen, L.; Andersen, C.E.; Duller, G.A.T.

    2003-01-01

    This paper summarises recent developments in the Riscircle divide TL/OSL reader. These new developments include an elevated temperature irradiation facility that has been expanded to measure variable temperature radioluminescence (RL) during beta irradiation. This RL facility allows the measurement...... facilities, and illustrates their applications with representative measurements. (C) 2003 Elsevier Science Ltd. All rights reserved....

  15. Development of the Jyvaeskylae microbeam facility

    Energy Technology Data Exchange (ETDEWEB)

    Norarat, Rattanaporn, E-mail: rattanaporn.norarat@phys.jyu.fi [Department of Physics, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 Jyvaeskylae (Finland); Sajavaara, Timo; Laitinen, Mikko; Heikkinen, Pauli; Ranttila, Kimmo; Ylikorkala, Kari; Haenninen, Vaeinoe; Rossi, Mikko; Jones, Pete [Department of Physics, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 Jyvaeskylae (Finland); Marjomaeki, Varpu; Gilbert, Leona [Department of Environmental and Biological Sciences, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 Jyvaeskylae (Finland); Whitlow, Harry J. [Department of Physics, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 Jyvaeskylae (Finland)

    2012-02-01

    Research highlights: Black-Right-Pointing-Pointer A MeV ion microbeam for biomedical materials research is being developed. Black-Right-Pointing-Pointer High accuracy scanning using electrostatic post-focus deflection. Black-Right-Pointing-Pointer Imaging and direct lithographic image writing using time-stamping methods. Black-Right-Pointing-Pointer New scanning modes and fluorescence detectors permit low ion-fluence cell imaging. Black-Right-Pointing-Pointer Thermal compensated beam-line support design for high positional accuracy. - Abstract: A new microbeam facility is being constructed at the 1.7 MV Pelletron Accelerator in Jyvaeskylae. The facility is designed for easy upgrading and incorporates a number of innovative features. Initially, it is based on a Heidelberg doublet with a design capability of a 3 Multiplication-Sign 5 {mu}m beamspot at PIXE intensities and later upgraded to nanobeam performance. A thermal-expansion compensated rigid frame mounted on a mechanically isolated floor section is used to support the ion optical components. A compact-post focusing electrostatic deflector is used for high linearity beam scanning. This together with a novel time-stamped data collection (TDC) allows dynamic effects in IBIC, fluorescence bleaching to be studied as well as facilitating multi-resolution image support for low-fluence imaging of cells. The target chamber is fitted with a novel low-cost large working distance optical microscope, extremely compact large solid angle photon detectors as well as conventional secondary electron, PIXE and Scanning Transmission Ion Microscopy (STIM) detectors.

  16. Development of a state radioactive materials storage facility

    International Nuclear Information System (INIS)

    Schmidt, P.S.

    1995-01-01

    The paper outlines the site selection and facility development processes of the state of Wisconsin for a radioactive materials facility. The facility was developed for the temporary storage of wastes from abandoned sites. Due to negative public reaction, the military site selected for the facility was removed from consideration. The primary lesson learned during the 3-year campaign was that any project involving radioactive materials is a potential political issue

  17. Quarterly report April 1 - June 30, 1997 [ARPA TRP turboalternator development

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-12

    This is a quarterly report of CALSTART's progress with their programs. Their overall objectives remain: (1) efficiently and responsible management of the program and; (2) assist in the commercialization of the technology by doing the following: identifying potential strategic partners; explaining need and value of turbogenerator; reach important audiences for AlliedSignal; showcase technology at key conferences/briefings; raise technology profile via custom Web information; and extend AlliedSignal turbogenerator outreach efforts.

  18. Technology development for iron Fischer-Tropsch catalysis. Quarterly technical progress report, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Davis, B.H.

    1996-11-01

    The objective of this research project is to develop the technology for the production of physically robust iron-based Fischer-Tropsch catalysts that have suitable activity, selectivity and stability to be used in the slurry phase synthesis reactor development. The catalysts that are developed shall be suitable for testing in the Advanced Fuels Development Facility at LaPorte, Texas, to produce either low- or high-alpha product distributions. Previous work by the offeror has produced a catalyst formulation that is 1.5 times as active as the ``standard-catalyst`` developed by German workers for slurry phase synthesis. The proposed work will optimize the catalyst composition and pretreatment operation for this low-alpha catalyst. In parallel, work will be conducted to design a high-alpha iron catalyst this is suitable for slurry phase synthesis. Studies will be conducted to define the chemical phases present at various stages of the pretreatment and synthesis stages and to define the course of these changes. The oxidation/reduction cycles that are anticipated to occur in large, commercial reactors will be studied at the laboratory scale. Catalyst performance will be determined for catalysts synthesized in this program for activity, select and aging characteristics. The research is divided into four major topical areas: (a) catalyst preparation and characterization, (b) product characterization, (c) reactor operations, and (d) data assessment. Accomplishments for this period are described.

  19. Trend chart: wind power. Third quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-11-01

    This publication presents the wind energy situation of continental France and overseas territories during the third quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  20. Trend chart: wind power. Second quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-08-01

    This publication presents the wind energy situation of continental France and overseas territories during the second quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  1. Trend chart: wind power. First quarter 2017

    International Nuclear Information System (INIS)

    2017-05-01

    This publication presents the wind energy situation of continental France and overseas territories during the first quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  2. Trend chart: wind power. First quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-05-01

    This publication presents the wind energy situation of continental France and overseas territories during the first quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  3. Trend chart: wind power. Third quarter 2015

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2015-11-01

    This publication presents the wind energy situation of continental France and overseas territories during the third quarter 2015: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  4. Trend chart: wind power. Forth quarter 2015

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-02-01

    This publication presents the wind energy situation of continental France and overseas territories during the forth quarter 2015: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  5. Trend chart: wind power. Forth quarter 2016

    International Nuclear Information System (INIS)

    Coltier, Yves

    2017-02-01

    This publication presents the wind energy situation of continental France and overseas territories during the forth quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  6. Trend chart: wind power. Fourth quarter 2017

    International Nuclear Information System (INIS)

    Moreau, Sylvain

    2018-02-01

    This publication presents the wind energy situation of continental France and overseas territories during the fourth quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, revision of results

  7. Trend chart: wind power. Third quarter 2017

    International Nuclear Information System (INIS)

    2017-11-01

    This publication presents the wind energy situation of continental France and overseas territories during the third quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, revision of results

  8. Trend chart: wind power. Second quarter 2017

    International Nuclear Information System (INIS)

    2017-08-01

    This publication presents the wind energy situation of continental France and overseas territories during the second quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, revision of results

  9. Advanced research and technology development fossil energy materials program. Quarterly progress report for the period ending September 30, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Bradley, R.A. (comp.)

    1981-12-01

    This is the fourth combined quarterly progress report for those projects that are part of the Advanced Research and Technology Development Fossil Energy Materials Program. The objective is to conduct a program of research and development on materials for fossil energy applications with a focus on the longer-term and generic needs of the various fossil fuel technologies. The program includes research aimed toward a better understanding of materials behavior in fossil energy environments and the development of new materials capable of substantial enhancement of plant operations and reliability. Work performed on the program generally falls into the Applied Research and Exploratory Development categories as defined in the DOE Technology Base Review, although basic research and engineering development are also conducted. A substantial portion of the work on the AR and TD Fossil Energy Materials Program is performed by participating cntractor organizations. All subcontractor work is monitored by Program staff members at ORNL and Argonne National Laboratory. This report is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1981 in which projects are organized according to fossil energy technologies. We hope this series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program.

  10. Development of a Micro- and Nano-Fabrication Facility

    National Research Council Canada - National Science Library

    Couzis, Alexander; Gilchrist, Lane; Maldarelli, Charles; Rumschitzki, David; Vazquez, Maribel

    2004-01-01

    .... This facility has fostered several research grant awards and applications from the PIs, has encouraged the development of undergraduate and graduate courses involving micro and nanotechnology at CCNY...

  11. Research and development for the declassification productivity initiative. Quarterly report, January 1997--August 1997

    Energy Technology Data Exchange (ETDEWEB)

    Bessonet, C.G. de

    1997-03-05

    The highlight for the first quarter was the presentation of research progress and findings at the DPI Symposium on March 5, 1997. Since that presentation, additional progress was slowed down due to the decreased budget funding for year two, and consequently, the decrease in time-effort of the principal investigators. This report summarizes the progress in each of the topical areas to date. A research article has been prepared for publication for the Optical Character Recognition project; two progress reports are included for the Logical Analysis project; and two progress reports for the Knowledge Representation project. Research activities for the Tipster Technology project will resume this fall.

  12. Coal liquefaction. Quarterly report, July-September 1979

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-07-01

    The status of coal liquefaction pilot plants supported by US DOE is reviewed under the following headings: company involved, location, contract, funding, process name, process description, flowsheet, history and progress during the July-September 1979 quarter. Supporting projects such as test facilities, refining and upgrading coal liquids, catalyst development, and gasification of residues from coal gasification plants are discussed similarly. (LTN)

  13. DOE research and development and field facilities

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    This report describes the roles of DOE's headquarters, field offices, major multiprogram laboratories, Energy Technology and Mining Operations Centers, and other government-owned, contractor-operated facilities which are located in all regions of the United States. It gives brief descriptions of resources, activities, and capabilities of each field facility (sections III through V). These represent a cumulative capital investment of $12 billion and involve a work force of approximately 12,000 government (field) employees and approximately 100,000 contractor employees.

  14. Technology development for long-term management of Hanford high-level waste. Quarterly report, January 1976--March 1976

    Energy Technology Data Exchange (ETDEWEB)

    Kounts, J S [ed.

    1976-06-01

    This document is the seventh in a series of quarterly reports on work in support of long-term management of Hanford high-level wastes. The work reported here was performed during the period January through March 1976. The specific topics discussed are grouped into the subject areas of: Storage System Integrity and Engineered Improvements; Waste Retrieval; Waste Immobilization and Storage; Contaminated Equipment Volume Reduction; and Analytical Methods Development. Previous reports were published as ARH-ST-110 A through D and ARH-ST-132 A and B.

  15. Upgrades of Hanford Engineering Development Laboratory hot cell facilities

    International Nuclear Information System (INIS)

    Daubert, R.L.; DesChane, D.J.

    1987-01-01

    The Hanford Engineering Development Laboratory operates the 327 Postirradiation Testing Laboratory (PITL) and the 324 Shielded Materials Facility (SMF). These hot cell facilities provide diverse capabilities for the postirradiation examination and testing of irradiated reactor fuels and materials. The primary function of these facilities is to determine failure mechanisms and effects of irradiation on physical and mechanical properties of reactor components. The purpose of this paper is to review major equipment and facility upgrades that enhance customer satisfaction and broaden the engineering capabilities for more diversified programs. These facility and system upgrades are providing higher quality remote nondestructive and destructive examination services with increased productivity, operator comfort, and customer satisfaction

  16. Development of automatic facilities for ZEPHYR

    International Nuclear Information System (INIS)

    Eder, O.; Lackner, E.; Pohl, F.; Schilling, H.B.

    1982-04-01

    This concept of remotely controlled facilities for repair and maintenance tasks inside the ZEPHYR vacuum vessel uses a supporting structure to insert various types of mobile automatic devices are guided by an egg-shaped disc which is part of the supporting structure. Considerations of adapting the guiding disc to the vessel contour are included. (orig.)

  17. Advanced computing for evaluating facility needs and enhancing sustainable development of public facility investment plan

    CSIR Research Space (South Africa)

    Green, Cheri A

    2009-06-01

    Full Text Available This paper describes the use of a GIS-based methodology for assessing and planning social facility provision and developing an integrated facility plan which is defensible and impacts meaningfully on resource allocation. A case study of community...

  18. Biomass power for rural development. Quarterly report, January 1--April 2, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.T.

    1998-07-01

    During the period of January 2 to April 2, 1998, efforts revolved around the design of the switchgrass materials handling/feeding system for the co-fire test and permanent system, the development of a revised statement of work and budget for fiscal years 1998--1999 and, the continuation of farmer/land conversion, and public relations efforts. The weather continues to be a major problem with an unprecedented warm winter. Much of Iowa has had little or no frost in the ground. This lack of frost has prevented farmers from getting into their fields and harvesting switchgrass. Farmers are hesitant to drive processing equipment into unfrozen fields due to the large ruts left by the wheels. The producers group has continued to gather information and develop resources necessary to supply the switchgrass to the facility in a competitive manner. Information and contacts are starting to be gathered which will help establish a market for the dedicated biomass generated electricity. The report describes the progress in the following tasks: Switchgrass conversion development including fuel analysis and engineering; Production activities which include: soil studies, carbon studies, switchgrass production economics, and switchgrass yield improvements; Information and education; and Miscellaneous which includes legislation and regulatory activities. Appendices contain the following: Switchgrass sample analysis; Chariton Valley biomass project cooperator agreement; Soil and landscape characterization status report for switchgrass project; Agreement with Center for Global and Regional Environmental Research; A literature review of reed canarygrass utility for biomass; Prairie Lands Bio-Products, Inc. agenda; Feasibility analysis and cooperative structure for value-added switchgrass products; and Information and education efforts.

  19. Report of the committee on a commercially developed space facility

    Science.gov (United States)

    Shea, Joseph F.; Stever, H. Guyford; Cutter, W. Bowman, III; Demisch, Wolfgang H.; Fink, Daniel J.; Flax, Alexander H.; Gatos, Harry C.; Glicksman, Martin E.; Lanzerotti, Louis J.; Logsdon, John M., III

    1989-01-01

    Major facilities that could support significant microgravity research and applications activity are discussed. The ground-based facilities include drop towers, aircraft flying parabolic trajectories, and sounding rockets. Facilities that are intrinsically tied to the Space Shuttle range from Get-Away-Special canisters to Spacelab long modules. There are also orbital facilities which include recoverable capsules launched on expendable launch vehicles, free-flying spacecraft, and space stations. Some of these existing, planned, and proposed facilities are non-U.S. in origin, but potentially available to U.S. investigators. In addition, some are governmentally developed and operated whereas others are planned to be privately developed and/or operated. Tables are provided to show the facility, developer, duration, estimated gravity level, crew interaction, flight frequency, year available, power to payload, payload volume, and maximum payload mass. The potential of direct and indirect benefits of manufacturing in space are presented.

  20. Development of a real-time monitor for airborne alpha emissions. First quarter report, TTP AL 142003

    Energy Technology Data Exchange (ETDEWEB)

    Gritzo, R.E.; Fowler, M.M.

    1994-02-01

    This is the first quarterly report for Fiscal Year (FY) 1994 for TTP AL 142003, Development of a Real-Time Monitor for Airborne Alpha Emissions. Los Alamos National Laboratory (LANL) is developing a new technology for on-line, real-time monitoring of incinerator stacks for low levels of airborne alpha activity. While initially developed for incinerators, this new technology may well find other applications in continuous air monitoring, process monitoring, and monitoring during remediation activities. Referred to as the Large-Volume Flow Thru Detector System (LVFTDS), this technology responds directly to the need for fast responding, high sensitivity effluent monitoring systems. With DOE EM-50 funding, LANL has fabricated a bench-top proof of concept detector system and is conducting tests to evaluate its performance. A second- generation prototype is being designed, based on requirements driven by potential field test sites. An industrial partner is being solicited to license the technology. Field trials of a full-scale detector system are planned for FY 95. Accomplishments during the first quarter of FY 94 are chronicled in this report, including budgetary data. A schedule for the remainder of the fiscal year is also provided.

  1. Development of fusion first-wall radiation damage facilities

    International Nuclear Information System (INIS)

    McElroy, R.J.; Atkins, T.

    1986-11-01

    The report describes work performed on the development of fusion-reactor first-wall simulation facilities on the Variable Energy Cyclotron, at Harwell, United Kingdom. Two irradiation facilities have been constructed: i) a device for helium and hydrogen filling up to 1000 ppm for post-irradiation mechanical properties studies, and ii) a helium implantation and damage facility for simultaneous injection of helium and radiation damage into a specimen under stress. These facilities are now fully commissioned and are available for investigations of first-wall radiation damage and for intercorrelation of fission- and fusion -reactor materials behaviour. (U.K.)

  2. A development of multiphase flow facility

    International Nuclear Information System (INIS)

    Ismail Mustapha; Jaafar Abdullah

    2004-01-01

    Multiphase liquid flow facility shall be enabling to transport of oil/gas/water in pipelines. In horizontal pipelines, the different flow patterns that could be observed. The flow pattern will depend mainly on the gas and liquid velocities, and gas liquid ratio. For very high liquid velocities and low gas liquid ratios, the dispersed bubble flow is observed. For low flow rates of liquid and gas, a smooth or wavy stratified flow is expected. For intermediate liquid velocities, rolling waves of liquids are formed. The rolling waves increase to the point of forming a plug flow and a slug flow. For very high gas velocities, the annular flow is observed Also include a tillable test section allowing for testing at any angle between 0 0 degree from horizontal, lowering the measurement uncertainties and increased capabilities with respect to flow rates and gas fractions. (Author)

  3. Developing a LLW disposal facility in California

    International Nuclear Information System (INIS)

    Romano, S.A.; Gaynor, R.K.; Hanrahan, T.P.

    1988-01-01

    US Ecology has been designated by the State of California to site and operate a low-level radioactive waste disposal facility. The firm identified three sites for detailed characterization work in February, 1987. Ecological and archaeological studies and related environmental assessments were undertaken to obtain land use permits from the Bureau of Land Management, which holds title to the sites. Geophysics investigations, exploratory borings, well drilling and weather station installation followed. Local Committees were established for each site to assist US Ecology in evaluating socio-economic impacts, and Native Americans were consulted regarding cultural resources. The project's Citizens Advisory Committee assisted in evaluating the three candidate sites. US Ecology systematically integrated citizen involvement into the technical studies leading to selection of the two site finalists. This approach furthered two objectives. Community leaders and the public received accurate information on the nature of low-level radioactive waste and the environmental conditions appropriate for its disposal

  4. The Copper Substrate Developments for the HIE-ISOLDE High-Beta Quarter Wave Resonator

    CERN Document Server

    Alberty, L; Aviles, I; Calatroni, S; Capatina, O; Foffano, G; Kadi, Y; Moyret, P; Schirm, K-M; Tardy, T; Venturini Delsolaro, W; D'Elia, A

    2013-01-01

    A new Linac using superconducting Quarter-Wave Resonators (QWRs) is under construction at CERN in the framework of the HIE-ISOLDE project. The QWRs are made by niobium sputtered on a bulk copper substrate. The working frequency at 4.5 K is 101.28 MHz and they will provide 6 MV/m accelerating gradient on the beam axis with a total maximum power dissipation of 10 W. The properties of the cavity substrate have a direct impact on the final cavity performance. The copper substrate has to ensure an optimum surface for the niobium sputtered layer. It has also to fulfil the required geometrical tolerances, the mechanical stability during operation and the thermal performance to optimally extract the RF dissipated power on cavity walls. The paper presents the mechanical design of the high β cavities. The procurement process of the copper raw material is detailed, including specifications and tests. The manufacturing sequence of the complete cavity is then explained and the structural and thermo-mechanical behaviour...

  5. Development of risk-based decision methodology for facility design.

    Science.gov (United States)

    2014-06-01

    This report develops a methodology for CDOT to use in the risk analysis of various types of facilities and provides : illustrative examples for the use of the proposed framework. An overview of the current practices and applications to : illustrate t...

  6. Development of the radioisotope production facility for the HANARO

    International Nuclear Information System (INIS)

    Lee, Ji Bok; Wu, J. S.; Baik, S. T.

    1998-06-01

    Hot cell and related facilities were developed in the RI production building of the HANARO. 1. development of concrete H/C and related components 2. development of lead H/C and related components 3. development of the hydraulic transfer system 4. development of radiation monitoring system 5. development of purification system for Co-60 storage pool 6. development of the fire fighting system for H/C 7. development of the experimental equipment. (author). 15 figs

  7. Weldon Spring Site Remedial Action Project quarterly environmental data summary (QEDS) for fourth quarter 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-02-01

    This report contains the Quarterly Environmental Data Summary (QEDS) for the fourth quarter of 1998 in support of the Weldon Spring Site Remedial Action Project Federal Facilities Agreement. The data, except for air monitoring data and site KPA generated data (uranium analyses) were received from the contract laboratories, verified by the Weldon Spring Site verification group, and merged into the database during the fourth quarter of 1998. KPA results for on-site total uranium analyses performed during fourth quarter 1998 are included. Air monitoring data presented are the most recent complete sets of quarterly data.

  8. Sustainable development in the Gruenau-Werdwies quarter, Zurich; Nachhaltige Quartierentwicklung Gruenau-Werdwies Zuerich; Auswirkungen der Ersatzneubauten Bernerstrasse Werdwies - Schlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Jenny, A.; Ott, W.

    2009-12-15

    This comprehensive final report for the Swiss Federal Office of Energy (SFOE) examines the effects of new, replacement residential buildings in the Bernerstrasse in Zurich, Switzerland. The authors state that this replacement development project is exemplary for sustainable residential development, incorporating ecological solutions for building and mobility, addressing financial and social aspects and allowing resident participation. The report includes the results of surveys made among the residents of the area and compares the Werdwies quarter with the whole area's social structures and mobility aspects. The quarter's energy consumption is discussed on the basis of a result checking survey. Finally, the findings of the project are discussed.

  9. Accelerator-driven subcritical facility:Conceptual design development

    Science.gov (United States)

    Gohar, Yousry; Bolshinsky, Igor; Naberezhnev, Dmitry; Duo, Jose; Belch, Henry; Bailey, James

    2006-06-01

    A conceptual design development of an accelerator-driven subcritical facility has been carried out in the preparation of a joint activity with Kharkov Institute of Physics and Technology of Ukraine. The main functions of the facility are the medical isotope production and the support of the Ukraine nuclear industry. An electron accelerator is considered to drive the subcritical assembly. The neutron source intensity and spectrum have been studied. The energy deposition, spatial neutron generation, neutron utilization fraction, and target dimensions have been quantified to define the main target performance parameters, and to select the target material and beam parameters. Different target conceptual designs have been developed based the engineering requirements including heat transfer, thermal hydraulics, structure, and material issues. The subcritical assembly is designed to obtain the highest possible neutron flux level with a Keff of 0.98. Different fuel materials, uranium enrichments, and reflector materials are considered in the design process. The possibility of using low enrichment uranium without penalizing the facility performance is carefully evaluated. The mechanical design of the facility has been developed to maximize its utility and minimize the time for replacing the target and the fuel assemblies. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements, upgrades, and new missions. In addition, it has large design margins to accommodate different operating conditions and parameters. In this paper, the conceptual design and the design analyses of the facility will be presented.

  10. National RF Test Facility as a multipurpose development tool

    International Nuclear Information System (INIS)

    McManamy, T.J.; Becraft, W.R.; Berry, L.A.

    1983-01-01

    Additions and modifications to the National RF Test Facility design have been made that (1) focus its use for technology development for future large systems in the ion cyclotron range of frequencies (ICRF), (2) expand its applicability to technology development in the electron cyclotron range of frequencies (ECRF) at 60 GHz, (3) provide a facility for ELMO Bumpy Torus (EBT) 60-GHz ring physics studies, and (4) permit engineering studies of steady-state plasma systems, including superconducting magnet performance, vacuum vessel heat flux removal, and microwave protection. The facility will continue to function as a test bed for generic technology developments for ICRF and the lower hybrid range of frequencies (LHRF). The upgraded facility is also suitable for mirror halo physics experiments

  11. Trend of development of robots for nuclear facilities

    International Nuclear Information System (INIS)

    Maki, Hideo; Sasaki, Masayoshi

    1984-01-01

    Robot technology becomes more and more important in the field of atomic energy industries. Hitachi Ltd. has energetically engaged in the development of the robot technology for nuclear facilities, recognizing these situations. The course of the development of robot technology and the robots for nuclear facilities is described. As the practical examples of the robots for nuclear facilities, there have been automatic fuel exchangers, the remotely operated automatic exchangers for control rod driving mechanism, automatic and semi-automatic ultrasonic flaw detectors and so on. As the robots for nuclear facilities under development, control rod driving mechanism disassembling and cleaning system, the volume reduction device for spent fuel channel boxes and control rods and others are reported. (Kako, I.)

  12. MHD power generation research, development and engineering. Quarterly progress report, October-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-01-01

    Progress is reported on the following tasks: characterization of coal for open-cycle MHD power generation systems; compressive creep and strength studies of MHD preheater materials; preparation of coals for utilization in direct coal-fired MHD generation; characterization of volatile matter in coal; MHD materials evaluation; operability of the Moderate Temperature Slag Flow Facility; slag-seed equilibria and separations related to the MHD system; thermionic emission of coal and electrode materials; MHD instrumentation, consolidated inversion simulator, and data acquisition; combined MHD-steam plant cycle analysis and control; and slag physical properties - electrical and thermal conductivity. (WHK)

  13. Decommissioning Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kang, Y. A.; Kim, G. H.

    2007-06-01

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely

  14. Decommissioning Technology Development for Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. W.; Kang, Y. A.; Kim, G. H. (and others)

    2007-06-15

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely.

  15. Facilities for Research and Development of Medical Radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Byung Chul; Choung, Won Myung; Park, Jin Ho

    2003-03-15

    This study is carried out by KAERI(Korea Atomic Energy Research Institute) to construct the basic facilities for development and production of medical radioisotope. For the characteristics of radiopharmaceuticals, the facilities should be complied with the radiation shield and GMP(Good Manufacturing Practice) guideline. The KAERI, which has carried out the research and development of the radiopharmaceuticals, made a design of these facilities and built them in the HANARO Center and opened the technique and facilities to the public to give a foundation for research and development of the radiopharmaceuticals. In the facilities, radiation shielding utilities and GMP instruments were set up and their operating manuals were documented. Every utilities and instruments were performed the test to confirm their efficiency and the approval for use of the facilities will be achieved from MOST(Ministry of Science and Technology). It is expected to be applied in development of therapeutic radioisotope such as Re-188 generator and Ho-166, as well as Tc-99m generator and Sr-89 chloride for medical use. And it also looks forward to the contribution to the related industry through the development of product in high demand and value.

  16. Alloy development for irradiation performance. Quarterly progress report for period ending December 31, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1981-04-01

    Progress is reported in eight sections: analysis and evaluation studies, test matrices and test methods development, Path A Alloy Development (austenitic stainless steels), Path C Alloy Development (Ti and V alloys), Path D Alloy Development (Fe alloys), Path E Alloy Development (ferritic steels), irradiation experiments and materials inventory, and materials compatibility and hydrogen permeation studies. (DLC)

  17. Alloy development for irradiation performance. Quarterly progress report for period ending December 31, 1980

    International Nuclear Information System (INIS)

    1981-04-01

    Progress is reported in eight sections: analysis and evaluation studies, test matrices and test methods development, Path A Alloy Development (austenitic stainless steels), Path C Alloy Development (Ti and V alloys), Path D Alloy Development (Fe alloys), Path E Alloy Development (ferritic steels), irradiation experiments and materials inventory, and materials compatibility and hydrogen permeation studies

  18. Development of Prototype Production ESR Facilities

    Science.gov (United States)

    1977-07-01

    Continuo on reverse aide ff necessary and identify by block number) This report describes the procedures employed to produce and develop a technique to...only after the attempted castings of the first and the final ingot in this program. An improved method of cooling the mandrel is through the use of a...refitted by welding to improve their straightness. The vendor gained proficiency in electrode casting too late in the course of this project work

  19. Development of a Large Scale, High Speed Wheel Test Facility

    Science.gov (United States)

    Kondoleon, Anthony; Seltzer, Donald; Thornton, Richard; Thompson, Marc

    1996-01-01

    Draper Laboratory, with its internal research and development budget, has for the past two years been funding a joint effort with the Massachusetts Institute of Technology (MIT) for the development of a large scale, high speed wheel test facility. This facility was developed to perform experiments and carry out evaluations on levitation and propulsion designs for MagLev systems currently under consideration. The facility was developed to rotate a large (2 meter) wheel which could operate with peripheral speeds of greater than 100 meters/second. The rim of the wheel was constructed of a non-magnetic, non-conductive composite material to avoid the generation of errors from spurious forces. A sensor package containing a multi-axis force and torque sensor mounted to the base of the station, provides a signal of the lift and drag forces on the package being tested. Position tables mounted on the station allow for the introduction of errors in real time. A computer controlled data acquisition system was developed around a Macintosh IIfx to record the test data and control the speed of the wheel. This paper describes the development of this test facility. A detailed description of the major components is presented. Recently completed tests carried out on a novel Electrodynamic (EDS) suspension system, developed by MIT as part of this joint effort are described and presented. Adaptation of this facility for linear motor and other propulsion and levitation testing is described.

  20. Development of cloud-operating platform for detention facility design

    Science.gov (United States)

    Tun Lee, Kwan; Hung, Meng-Chiu; Tseng, Wei-Fan; Chan, Yi-Ping

    2017-04-01

    In the past 20 years, the population of Taiwan has accumulated in urban areas. The land development has changed the hydrological environment and resulted in the increase of surface runoff and shortened the time to peak discharge. The change of runoff characteristics increases the flood risk and reduces resilient ability of the city during flood. Considering that engineering measures may not be easy to implement in populated cities, detention facilities set on building basements have been proposed to compromise the increase of surface runoff resulting from development activities. In this study, a web-based operational platform has been developed to integrate the GIS technologies, hydrological analyses, as well as relevant regulations for the design of detention facilities. The design procedure embedded in the system includes a prior selection of type and size of the detention facility, integrated hydrological analysis for the developing site, and inspection of relevant regulations. After login the platform, designers can access the system database to retrieve road maps, land use coverages, and storm sewer information. Once the type, size, inlet, and outlet of the detention facility are assigned, the system can acquire the rainfall intensity-duration-frequency information from adjacent rain gauges to perform hydrological analyses for the developing site. The increase of the runoff volume due to the development and the reduction of the outflow peak through the construction of the detention facility can be estimated. The outflow peak at the target site is then checked with relevant regulations to confirm the suitability of the detention facility design. The proposed web-based platform can provide a concise layout of the detention facility and the drainageway of the developing site on a graphical interface. The design information can also be delivered directly through a web link to authorities for inspecting to simplify the complex administrative procedures.

  1. Professional Sports Facilities, Franchises and Urban Economic Development

    OpenAIRE

    Dennis Coates; Brad R. Humphreys

    2003-01-01

    Local political and community leaders and the owners of professional sports teams frequently claim that professional sports facilities and franchises are important engines of economic development in urban areas. These structures and teams allegedly contribute millions of dollars of net new spending annually and create hundreds of new jobs, and provide justification for hundreds of millions of dollars of public subsidies for the construction of many new professional sports facilities in the Un...

  2. Geothermal Drilling and Completion Technology Development Program. Quarterly progress report, October 1980-December 1980

    Energy Technology Data Exchange (ETDEWEB)

    Kelsey, J.R. (ed.)

    1981-03-01

    The progress, status, and results of ongoing Research and Development (R and D) within the Geothermal Drilling and Completion Technology Development Program are described. The program emphasizes the development of geothermal drilling hardware, drilling fluids, completion technology, and lost circulation control methods. Advanced drilling systems are also under development.

  3. Space facilities: Meeting future needs for research, development, and operations

    Science.gov (United States)

    1994-01-01

    The National Facilities Study (NFS) represents an interagency effort to develop a comprehensive and integrated long-term plan for world-class aeronautical and space facilities that meet current and projected needs for commercial and government aerospace research and development and space operations. At the request of NASA and the DOD, the National Research Council's Committee on Space Facilities has reviewed the space related findings of the NFS. The inventory of more than 2800 facilities will be an important resource, especially if it continues to be updated and maintained as the NFS report recommends. The data in the inventory provide the basis for a much better understanding of the resources available in the national facilities infrastructure, as well as extensive information on which to base rational decisions about current and future facilities needs. The working groups have used the inventory data and other information to make a set of recommendations that include estimates of cast savings and steps for implementation. While it is natural that the NFS focused on cost reduction and consolidations, such a study is most useful to future planning if it gives equal weight to guiding the direction of future facilities needed to satisfy legitimate national aspirations. Even in the context of cost reduction through facilities closures and consolidations, the study is timid about recognizing and proposing program changes and realignments of roles and missions to capture what could be significant savings and increased effectiveness. The recommendations of the Committee on Space Facilities are driven by the clear need to be more realistic and precise both in recognizing current incentives and disincentives in the aerospace industry and in forecasting future conditions for U.S. space activities.

  4. Geothermal drilling and completion technology development program. Quarterly progress report, January-March 1980

    Energy Technology Data Exchange (ETDEWEB)

    Varnado, S.G. (ed.)

    1980-04-01

    The progress, status, and results of ongoing Research and Development (R and D) within the Geothermal Drilling and Completion Technology Development Program are described. The program emphasizes the development of geothermal drilling hardware, drilling fluids, completion technology, and lost circulation control methods. Advanced drilling systems are also under development. The goals of the program are to develop the technology required to reduce well costs by 25% by 1983 and by 50% by 1987.

  5. Geothermal drilling and completion technology development program. Quarterly progress report, April-June 1980

    Energy Technology Data Exchange (ETDEWEB)

    Varnado, S.G.

    1980-07-01

    The progress, status, and results of ongoing research and development (R and D) within the Geothermal Drilling and Completion Technology Development Program are reported. The program emphasizes the development of geothermal drilling hardware, drilling fluids, completion technology, and lost circulation control methods. Advanced drilling systems are also under development. The goals of the program are to develop the technology required to reduce well costs by 25% by 1983 and by 50% by 1987.

  6. Detecting Development Pattern of Urban Business Facilities Using Reviews Data

    Directory of Open Access Journals (Sweden)

    JIANG Botao

    2015-09-01

    Full Text Available This paper reveals and utilizes the growing power of online customer reviews in the space and time context. The location of commercial facilities and online customer reviews offered by Dianping.com provide an important data source for the study of spatial and temporal dynamics of urban commercial facilities. The constraints of road network are taken into account towards computing the density of urban commercial facilities and associated online customer reviews, as well as their spatial distribution, temporal trend, and the coupling relationship between facility number and stratification level. This paper maps the spatial distribution of commercial facilities onto the nearby road network, reflecting the influences of the locations, number and satisfaction levels of other commercial facilities across various street types. Because more and more customers tend to make a final shopping decision by sorting through search results by ratings and feedback, the research conducted in this paper can provide the proof for quantitative evaluation of urban planning on commercial facility development.

  7. Geothermal Drilling and Completion Technology Development Program. Quarterly progress report, January 1981-March 1981

    Energy Technology Data Exchange (ETDEWEB)

    Kelsey, J.R. (ed.)

    1981-06-01

    The progress, status, and results of ongoing Research and Development (R and D) within the Geothermal Drilling and Completion Technology Development Program are described. The program emphasizes the development of geothermal drilling hardware, drilling fluids, completion technology, and lost circulation control methods as they apply to advanced drilling systems.

  8. EDIN-USVI Clean Energy Quarterly: Volume 1, Issue 2, March 2011, Energy Development in Island Nations, U.S. Virgin Islands (Newsletter)

    Energy Technology Data Exchange (ETDEWEB)

    2011-03-01

    This quarterly newsletter provides timely news and information about the plans and progress of the Energy Development in Island Nations U.S. Virgin Islands pilot project, including significant events and milestones, work undertaken by each of the five working groups, and project-related renewable energy and energy efficiency projects.

  9. NST Quarterly - issue April 2002

    International Nuclear Information System (INIS)

    2002-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activity in radiocarbon dating and discusses the topic - Radiation energy technologies are finding new niches in the marketplace

  10. NST Quarterly. July 1996 issue

    International Nuclear Information System (INIS)

    1996-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in in-vitro mutagenesis of ornamental plants, soil erosion studies and animal feed production from agricultural waste

  11. NST Quarterly - January 1998 issue

    International Nuclear Information System (INIS)

    1998-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in proposal of national networking for biotechnology culture collection centre (NNBCCC)

  12. Developing a model lifeline protection program for DOE facilities

    International Nuclear Information System (INIS)

    Lowing, A.N.

    1996-01-01

    A National Lifeline Standard Development Program is currently being conducted by FEMA and NIST. The Department of Energy is following these developments and supplementing them to meet Life-Safety and mission requirements for all DOE facilities as part of the Natural Phenomena Hazards Mitigation Plan. The task will be overseen by a DOE management team with technical guidance provided by a Steering Group of management and operating contractor representatives. The DOE will participate in the federal program by conducting a workshop on lifeline protection issues, developing an overall plan, organizing a Steering Group, and conducting a pilot study at a DOE facility

  13. Development of a fault test experimental facility model using Matlab

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Iraci Martinez; Moraes, Davi Almeida, E-mail: martinez@ipen.br, E-mail: dmoraes@dk8.com.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The Fault Test Experimental Facility was developed to simulate a PWR nuclear power plant and is instrumented with temperature, level and pressure sensors. The Fault Test Experimental Facility can be operated to generate normal and fault data, and these failures can be added initially small, and their magnitude being increasing gradually. This work presents the Fault Test Experimental Facility model developed using the Matlab GUIDE (Graphical User Interface Development Environment) toolbox that consists of a set of functions designed to create interfaces in an easy and fast way. The system model is based on the mass and energy inventory balance equations. Physical as well as operational aspects are taken into consideration. The interface layout looks like a process flowchart and the user can set the input variables. Besides the normal operation conditions, there is the possibility to choose a faulty variable from a list. The program also allows the user to set the noise level for the input variables. Using the model, data were generated for different operational conditions, both under normal and fault conditions with different noise levels added to the input variables. Data generated by the model will be compared with Fault Test Experimental Facility data. The Fault Test Experimental Facility theoretical model results will be used for the development of a Monitoring and Fault Detection System. (author)

  14. Development of a fault test experimental facility model using Matlab

    International Nuclear Information System (INIS)

    Pereira, Iraci Martinez; Moraes, Davi Almeida

    2015-01-01

    The Fault Test Experimental Facility was developed to simulate a PWR nuclear power plant and is instrumented with temperature, level and pressure sensors. The Fault Test Experimental Facility can be operated to generate normal and fault data, and these failures can be added initially small, and their magnitude being increasing gradually. This work presents the Fault Test Experimental Facility model developed using the Matlab GUIDE (Graphical User Interface Development Environment) toolbox that consists of a set of functions designed to create interfaces in an easy and fast way. The system model is based on the mass and energy inventory balance equations. Physical as well as operational aspects are taken into consideration. The interface layout looks like a process flowchart and the user can set the input variables. Besides the normal operation conditions, there is the possibility to choose a faulty variable from a list. The program also allows the user to set the noise level for the input variables. Using the model, data were generated for different operational conditions, both under normal and fault conditions with different noise levels added to the input variables. Data generated by the model will be compared with Fault Test Experimental Facility data. The Fault Test Experimental Facility theoretical model results will be used for the development of a Monitoring and Fault Detection System. (author)

  15. HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1975

    International Nuclear Information System (INIS)

    1975-01-01

    The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and the data are presented in tables, graphs, and photographs

  16. Practical superconductor development for electrical power applications. Quarterly report for the period ending March 31, 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This is a multiyear experimental research program focused on improving relevant material properties of high-T c superconductors (HTSs) and on development of fabrication methods that can be transferred to industry for production of commercial conductors. The development of teaming relationships through agreements with industrial partners is a key element of the Argonne program. Recent results are presented on YBa 2 Cu 3 O x (Y-123) coated conductors, sheathed (Bi,Pb) 2 Sr 2 Ca 2 Cu 3 O x (Bi-2223) tapes, and applications development

  17. Practical superconductor development for electrical power applications: Quarterly report for the period ending December 31, 1999

    International Nuclear Information System (INIS)

    2000-01-01

    This is a multiyear experimental research program focused on improving relevant material properties of high-T c superconductors (HTSS) and on development of fabrication methods that can be transferred to industry for production of commercial conductors. The development of teaming relationships through agreements with industrial partners is a key element of the Argonne (ANL) program. Recent results on substrate deposition for coated conductors, vortex studies, development of hardened Ag-alloy sheaths for powder-in-tube conductors, and sol-gel processing of NdBa 2 Cu 3 O x (Nd-123) are presented

  18. Practical superconductor development for electrical power applications quarterly report for the period ending March 31, 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-04-19

    This is a multiyear experimental research program focused on improving relevant material properties of high-T{sub c} superconductors (HTSs) and on development of fabrication methods that can be transferred to industry for production of commercial conductors. The development of teaming relationships through agreements with industrial partners is a key element of the Argonne program. Recent results are presented on YBa{sub 2}Cu{sub 3}O{sub x} (Y-123) coated conductors, sheathed (Bi,Pb){sub 2}Sr{sub 2}Ca{sub 2}Cu{sub 3}O{sub x} (Bi-2223) tapes, and applications development.

  19. Quarterly Progress Report Research And Development Activities Waste Fixation Program October Through December 1976

    International Nuclear Information System (INIS)

    McElroy, J. L.

    1977-01-01

    Research and development activities of the Waste Fixation Program for October through December 1976 are described in this report. The objective of this program is to develop processes to convert high-level radioactive liquid waste (HLLW) to solid forms that are demonstrated to be physically, chemically, and radiolytically stable and inert. The scope of this program encompasses plans to make available a flexible advancing technology for the solidification of radioactive waste. Early technology will produce borosilicate glass by in-can melting and continuous electric melters. Multibarrier waste forms will be developed for future application

  20. Alloy development for irradiation performance. Quarterly progress report for period ending September 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-12-01

    This report is organized along topical lines in parallel to a Program Plan of the same title so that activities and accomplishments may be followed readily relative to that Program Plan. Thus, the work of a given laboratory may appear throughout the report. Chapters 1, 2, 8, and 9 review activities on analysis and evaluation, test methods development, status of irradiation experiments, and corrosion testing and hydrogen permeation studies, respectively. These activities relate to each of the alloy development paths. Chapters 3, 4, 5, 6, and 7 present the ongoing work on each alloy development path. The Table of Contents is annotated for the convenience of the reader.

  1. Standards development: status summary report. Quarterly report, April-June 1982

    International Nuclear Information System (INIS)

    1982-01-01

    This report gives in summary form, the current schedule plans for development of regulations, guides, reports, petitions and environmental statements. Approved schedules are identified by a T (Target) date below each milestone description on the computerized network. Schedule estimates that have not yet been approved by standards development management are also included and are identified by an E (estimated) date below the approved target date. E dates do not represent approved changes and are printed for information purposes only

  2. Development of the flow control irradiation facility for JOYO

    International Nuclear Information System (INIS)

    Soroi, Masatoshi; Miyakawa, Shun-ichi

    1998-05-01

    This report describes the present situation and problems with the development of the flow control irradiation facility (FLORA). The purpose of FLORA is to run the cladding breach (RTCB) irradiation test under loss of flow conditions in the experimental fast reactor 'JOYO'. FLORA is a facility like FPTF (Fuel Performance Test Facility) plus BFTF (Breached Fuel Test Facility) in EBR-II, USA. The technical feature of FLORA is its annular linear induction pump (A-LIP), which was developed in response to a need identified through the experiences in the mechanical flow control of FPTF. We have already designed the basic system facility of FLORA for the JOYO MK-II core. However, to put FLORA to practical use in the future, we have to confirm the stability of the JOYO MK-III core condition, solve problems and improve the design. We are going to freeze and review the FLORA project, taking into consideration the fuel development situation and the research project of JOYO MK-III core. (J.P.N.)

  3. Quarterly environmental data summary for fourth quarter 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The Quarterly Environmental Data Summary (QEDS) for the fourth quarter of 1997 is prepared in support of the Weldon Spring Site Remedial Action Project Federal Facilities Agreement. The data presented constitute the QEDS. The data were received from the contract laboratories, verified by the Weldon Spring Site verification group and, except for air monitoring data and site KPA generated data (uranium analyses), merged into the data base during the fourth quarter of 1997. Air monitoring data presented are the most recent complete sets of quarterly data. Air data are not stored in the data base and KPA data are not merged into the regular data base. Significant data, defined as data values that have exceeded defined ``above normal`` level 2 values, are discussed in this letter for Environmental Monitoring Plan (EMP) generated data only. Above normal level 2 values are based, in ES and H procedures, on historical high values, DOE Derived Concentration Guides (DCGs), NPDES limits and other guidelines. The procedures also establish actions to be taken in response to such data. Data received and verified during the fourth quarter were within a permissible range of variability except for those which are detailed.

  4. Biomass power for rural development. Quarterly report, July 3--December 4, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.T.

    1998-03-01

    This paper describes progress in several projects related to biomass power. These include switchgrass conversion development; switchgrass gasification development; production activities including soil studies, carbon studies, switchgrass production economics, watershed impacts, and prairie lands bio-products; information and education; and geographical information system. Attachments describe switchgrass co-firing test; switchgrass production in Iowa; cooperative agreements with ISU; Rathbun Lake watershed project; newspaper articles and information publications; Secretary of Agriculture Glickman`s visit; integration of technical aspects of switchgrass production in Iowa; and evaluation of an integrated biomass gasification/fuel cell power plant.

  5. Isotopic power materials development. Quarterly progress report for period ending December 31, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Schaffhauser, A.C.

    1977-06-01

    Research progress is reported on: (1) high-temperature alloys for space isotopic heat sources; (2) physical and mechanical metallurgy of heat source containment materials; (3) /sup 144/Cm fuel development; (4) terrestrial radioisotope applications; (5) selenide isotope generator system support; (6) isotope Brayton system materials support; and (7) space nuclear flight systems hardware. (TFD)

  6. Developing Effluent Analysis Technologies to Support Nonproliferation Initiatives, Arms Control and Nonproliferation Technologies, Third quarter 1995

    Energy Technology Data Exchange (ETDEWEB)

    Schubert, S A; Staehle, G; Alonzo, G M [eds.

    1995-01-01

    This issue provides an overview of the Effluent Research Program of the DOE Office of Research and Development, highlighting a number of representative projects within this program in support of nonproliferation initiatives. Technologies reported include portable instruments for on-site inspections, standoff detectors, fieldable, real-time instruments, field collection techniques, and ultrasensitive laboratory techniques.

  7. Development of the new Canadian Irradiation-Research Facility

    International Nuclear Information System (INIS)

    Lidstone, R.F.; Lee, A.G.; Bishop, W.E.; Talbot, E.F.; MCilwain, H.

    1995-01-01

    To replace the aging NRU reactor, AECL has developed the concept for a dual-purpose national Irradiation Research Facility (IRF) that tests fuel and materials for CANDU (Canada Deuterium Uranium) reactors and performs materials research using extracted neutron beams. The IRF includes a MAPLE reactor in a containment building, experimental facilities and support facilities. The reactor concept was developed to provide a realistic environment for irradiating up to nine natural- or enriched-uranium CANDU bundles at powers up to 1 MW p to generate fast-neutron fluxes up to 1.4x10 18 n m -2 s -1 in materials-damage and corrosion specimens, and to match the thermal-neutron fluxes available in NRU for a set of eight thermal beam tubes plus two cold sources equipped with neutron guides. (author)

  8. Biomass power for rural development. Quarterly report, September 23, 1996--December 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.T.

    1997-02-01

    Goals for the biomass power for rural development include: expanded feedstock research and demonstration activities to provide soil-specific production costs and yield data, as well as better methods for harvest and transport; four thousand acres of feedstock available for fueling a commercial venture; comparison of the feasibility of gasification and cocombustion; designs for on-site switchgrass handling and feeding system; a detailed assessment of utilizing switchgrass for gasification and cocombustion to generate electricity using turbines and fuel cells.

  9. LLE Review quarterly report, October--December 1992. Volume 53

    Energy Technology Data Exchange (ETDEWEB)

    Meyerhofer, D.D. [ed.

    1992-12-31

    This volume of the LLE Review covers the three-month period October--December 1992. On 18 December, the OMEGA Laser Facility fired its last shot. It will be decommissioned during the next quarter to make room for the OMEGA Upgrade Laser Facility. This volume deals with two areas of interest for the OMEGA Upgrade, the development of advanced x-ray and neutron diagnostics and the development of long-pulse (>1-ns) laser sources. The first three articles discuss the development of time-dependent diagnostics. The development of an x-ray framing camera is described and measurements of the high-voltage pulse propagation in the camera are presented. Time-resolved and time-integrated neutron diagnostics for the OMEGA Upgrade are then discussed. Two schemes for the generation of >1-ns laser pulses are presented. Finally, the activities of the National Laser Users Facility and the GDL and OMEGA laser facilities are summarized.

  10. Development of Facilities Master Plan and Laboratory Renovation Project

    Energy Technology Data Exchange (ETDEWEB)

    Fox, Andrea D

    2011-10-03

    Funding from this grant has allowed Morehouse School of Medicine to complete its first professionally developed, comprehensive campus master plan that is in alignment with the recently completed strategic plan. In addition to master planning activities, funds were used for programming and designing research renovations, and also to supplement other research facility upgrades by providing lighting and equipment. The activities funded by this grant will provide the catalyst for substantial improvement in the School's overall facilities for biomedical education and research, and will also provide much of the information needed to conduct a successful campaign to raise funds for proposed buildings and renovations.

  11. Neutron Imaging Facility Development and Research Trend at NIST

    Science.gov (United States)

    Arif, M.; Hussey, D. S.; Baltic, E. M.; Jacobson, D. L.

    The National Institute of Standards and Technology (NIST)maintains a sustained focus in the development of advanced neutron imaging facilities and hardware components to enable breakthrough research with vastly improved spatial and temporal resolutions, and to identify and employ research practices important to a wide variety of industrial and scientific applications. NIST's main focus is to enable research with broad appeal and commercial impacts. In this article we will give a brief overview of the NIST facility, select examples of current research, and finally comment on emerging technologies including advance manufacturing where neutron imaging has the potential to play an important role.

  12. Accelerator development for a radioactive beam facility based on ATLAS

    International Nuclear Information System (INIS)

    Shepard, K. W.

    1998-01-01

    The existing superconducting linac ATLAS is in many respects an ideal secondary beam accelerator for an ISOL (Isotope separator on-line) type radioactive beam facility. Such a facility would require the addition of two major accelerator elements: a low charge state injector for the existing heavy ion linac, and a primary beam accelerator providing 220 MV of acceleration for protons and light ions. Development work for both of these elements, including the option of superconducting cavities for the primary beam accelerator is discussed

  13. Accelerator development for a radioactive beam facility based on ATLAS.

    Energy Technology Data Exchange (ETDEWEB)

    Shepard, K. W.

    1998-01-08

    The existing superconducting linac ATLAS is in many respects an ideal secondary beam accelerator for an ISOL (Isotope separator on-line) type radioactive beam facility. Such a facility would require the addition of two major accelerator elements: a low charge state injector for the existing heavy ion linac, and a primary beam accelerator providing 220 MV of acceleration for protons and light ions. Development work for both of these elements, including the option of superconducting cavities for the primary beam accelerator is discussed.

  14. Silicon solar cell process development, fabrication and analysis. Third quarterly report, January 1-March 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, H.I.; Iles, P.A.; Tanner, D.P.

    1979-01-01

    The objective of this program is to investigate, develop, and utilize technologies appropriate and necessary for improving the efficiency of solar cells made from various unconventional silicon sheets. Work has progressed in fabrication and characterization of solar cells from cast silicon by heat exchanger method (Crystal Systems), EFG (RH) ribbon (Mobil Tyco) and silicon on ceramic (Honeywell). Silicon blanks (2 x 2 cm) were prepared from the HEM cast silicon and EFG ribbon, using conventional slicing techniques, and fabricated using a standard process typical of those used currently in the silicon solar cell industry. Also a back surface field (BSF) process and other process modifications were included in processing additional slices. Relatively large area (about 15 cm/sup 2/) solar cells were fabricated from silicon on ceramic substrates using a standard process that can be easily adapted to these substrates. Evaluation of the SOC solar cells has not been completed in this reporting period. The performance parameters measured included open circuit voltage, short circuit current, curve fill factor, and conversion efficiency (all taken under AMO illumination). Also measured for typical cells were spectral response, dark I-V characteristics, minority carrier diffusion length, and photoresponse by fine light scanning. The results were compared to the properties of cells made from the conventional single crystalline Czochralski silicon with an emphasis on statistical evaluation. Limited efforts were made to identify defects which will influence solar cell performance.

  15. Trend chart: photovoltaic solar energy. First quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-05-01

    This newsletter presents a quarterly review of the French photovoltaic park situation: evolution of the connected power, new connected facilities, production by power range, ongoing projects and regional statistics (number of facilities, power, distribution, evolution)

  16. Trend chart: photovoltaic solar energy. Second quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-08-01

    This newsletter presents a quarterly review of the French photovoltaic park situation: evolution of the connected power, new connected facilities, production by power range, ongoing projects and regional statistics (number of facilities, power, distribution, evolution)

  17. National Geothermal Academy. Geo-Heat Center Quarterly Bulletin, Vol. 31 No. 2 (Complete Bulletin). A Quarterly Progress and Development Report on the Direct Utilization of Geothermal Resources

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, Tonya [ed.; Maddi, Phillip [ed.

    2012-08-01

    The National Geothermal Academy (NGA) is an intensive 8-week overview of the different aspects involved in developing a geothermal project, hosted at University of Nevada, Reno. The class of 2012 was the second graduating class from the academy and included 21 students from nine states, as well as Saudi Arabia, Dominica, India, Trinidad, Mexico. The class consisted of people from a wide range of scholastic abilities from students pursuing a Bachelor’s or Master’s degrees, to entrepreneurs and professionals looking to improve their knowledge in the geothermal field. Students earned 6 credits, either undergraduate or graduate, in engineering or geology. Overall, the students of the NGA, although having diverse backgrounds in engineering, geology, finance, and other sciences, came together with a common passion to learn more about geothermal.

  18. M-Area and Metallurgical Laboratory Hazardous Waste Management Facilities groundwater monitoring and corrective-action report (U). Third and fourth quarters 1996, Vol. I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This report describes the groundwater monitoring and corrective-action program at the M-Area Hazardous Waste Management Facility (HWMF) and the Metallurgical Laboratory (Met Lab) HWMF at the Savannah River Site (SRS) during 1996.

  19. Trend chart: biogas for electricity production. First quarter 2017

    International Nuclear Information System (INIS)

    2017-05-01

    This publication presents the situation of biogas-fueled power plants in continental France and overseas territories during the first quarter 2017: total connected load, new connected facilities, power range distribution of facilities, evolution of park facilities and projection, distribution by type of facilities, regional distribution of facilities, total connected load by region, overall national power generation from biogas, evolution of newly connected methanation facilities for power generation, power range distribution of methanation facilities, regional distribution of methanation facilities, methodology used

  20. Trend chart: biogas for electricity production. Fourth quarter 2017

    International Nuclear Information System (INIS)

    Moreau, Sylvain

    2018-02-01

    This publication presents the situation of biogas-fueled power plants in continental France and overseas territories during the fourth quarter 2017: total connected load, new connected facilities, power range distribution of facilities, evolution of park facilities and projection, distribution by type of facilities, regional distribution of facilities, total connected load by region, overall national power generation from biogas, evolution of newly connected methanation facilities for power generation, power range distribution of methanation facilities, regional distribution of methanation facilities

  1. Trend chart: biogas for electricity production. Second quarter 2017

    International Nuclear Information System (INIS)

    2017-08-01

    This publication presents the situation of biogas-fueled power plants in continental France and overseas territories during the second quarter 2017: total connected load, new connected facilities, power range distribution of facilities, evolution of park facilities and projection, distribution by type of facilities, regional distribution of facilities, total connected load by region, overall national power generation from biogas, evolution of newly connected methanation facilities for power generation, power range distribution of methanation facilities, regional distribution of methanation facilities

  2. Trend chart: biogas for electricity production. Third quarter 2017

    International Nuclear Information System (INIS)

    Moreau, Sylvain

    2017-11-01

    This publication presents the situation of biogas-fueled power plants in continental France and overseas territories during the third quarter 2017: total connected load, new connected facilities, power range distribution of facilities, evolution of park facilities and projection, distribution by type of facilities, regional distribution of facilities, total connected load by region, overall national power generation from biogas, evolution of newly connected methanation facilities for power generation, power range distribution of methanation facilities, regional distribution of methanation facilities

  3. Research and test facilities for development of technologies and experiments with commercial applications

    Science.gov (United States)

    1989-01-01

    One of NASA'S agency-wide goals is the commercial development of space. To further this goal NASA is implementing a policy whereby U.S. firms are encouraged to utilize NASA facilities to develop and test concepts having commercial potential. Goddard, in keeping with this policy, will make the facilities and capabilities described in this document available to private entities at a reduced cost and on a noninterference basis with internal NASA programs. Some of these facilities include: (1) the Vibration Test Facility; (2) the Battery Test Facility; (3) the Large Area Pulsed Solar Simulator Facility; (4) the High Voltage Testing Facility; (5) the Magnetic Field Component Test Facility; (6) the Spacecraft Magnetic Test Facility; (7) the High Capacity Centrifuge Facility; (8) the Acoustic Test Facility; (9) the Electromagnetic Interference Test Facility; (10) the Space Simulation Test Facility; (11) the Static/Dynamic Balance Facility; (12) the High Speed Centrifuge Facility; (13) the Optical Thin Film Deposition Facility; (14) the Gold Plating Facility; (15) the Paint Formulation and Application Laboratory; (16) the Propulsion Research Laboratory; (17) the Wallops Range Facility; (18) the Optical Instrument Assembly and Test Facility; (19) the Massively Parallel Processor Facility; (20) the X-Ray Diffraction and Scanning Auger Microscopy/Spectroscopy Laboratory; (21) the Parts Analysis Laboratory; (22) the Radiation Test Facility; (23) the Ainsworth Vacuum Balance Facility; (24) the Metallography Laboratory; (25) the Scanning Electron Microscope Laboratory; (26) the Organic Analysis Laboratory; (27) the Outgassing Test Facility; and (28) the Fatigue, Fracture Mechanics and Mechanical Testing Laboratory.

  4. Construction and engineering report for advanced nuclear fuel development facility

    Energy Technology Data Exchange (ETDEWEB)

    Cho, S. W.; Park, J. S.; Kwon, S.J.; Lee, K. W.; Kim, I. J.; Yu, C. H

    2003-09-01

    The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m{sup 2}, basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc.

  5. Third quarter 2005 sales figures

    International Nuclear Information System (INIS)

    2005-01-01

    With manufacturing facilities in over 40 countries and a sales network in over 100, AREVA offers customers technological solutions for nuclear power generation and electricity transmission and distribution. The group also provides interconnect systems to the telecommunications, computer and automotive markets. This document presents the sales figures of the group for the third quarter of 2005: sales revenues in the front end division, in the reactor and services division, in the back end division and in the transmission and distribution division

  6. Human resource development in rural health care facilities.

    Science.gov (United States)

    Johnson, L

    1991-01-01

    In this paper, human resource development problems facing rural health care facilities are identified and it is recognised that, particularly in the face of escalating demands for training arising from environmental pressures such as implementation of the structural efficiency principle, a coordinated approach to meet these problems is desirable. Such coordination is often sought via a regional staff development service. Accordingly, using the organisational life cycle as a conceptual framework, staff development services in five NSW health regions are examined. Ranging from a cafeteria style to a results-orientation, a diversity of strategic approaches to staff development is reflected.

  7. Hardware development process for Human Research facility applications

    Science.gov (United States)

    Bauer, Liz

    2000-01-01

    The simple goal of the Human Research Facility (HRF) is to conduct human research experiments on the International Space Station (ISS) astronauts during long-duration missions. This is accomplished by providing integration and operation of the necessary hardware and software capabilities. A typical hardware development flow consists of five stages: functional inputs and requirements definition, market research, design life cycle through hardware delivery, crew training, and mission support. The purpose of this presentation is to guide the audience through the early hardware development process: requirement definition through selecting a development path. Specific HRF equipment is used to illustrate the hardware development paths. .

  8. Technical Division quarterly progress report, October 1--December 31, 1977. [Fuel cycle research and development; special materials production

    Energy Technology Data Exchange (ETDEWEB)

    Slansky, C.M. (ed.)

    1978-02-01

    Results are presented on the fluidized-bed calcination of simulated radioactive waste from the reprocessing of spent commercial nuclear fuel and on the removal of actinide elements from the waste prior to calcination. Other programs include the development of storage technology for /sup 85/Kr waste; and the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel. The long-term management of defense waste from the ICPP covers post-calcination treatment of ICPP calcined waste; the removal of actinide elements from first-cycle raffinate; the retrieval and handling of calcined waste from ICPP storage vaults; and the preparation of the Programmatic Environmental Impact Statement on ICPP waste. Process improvements are reported on the Fluorinel headend process for Zircaloy-clad fuels and on uranium accountability measurements. Other development results cover the process for recovering spent Rover fuel, buried pipeline transfer systems, support to the Waste Management Program, Waste Calcining Facility support, New Waste Calcining Facility support, and effluent monitoring methods evaluation and development. In this category are studies on nuclear materials security, application of a liquid-solid fluidized-bed heat exchanger to the recovery of geothermal heat, inplant reactor source term measurements, burnup methods for fast breeder reactor fuels, absolute thermal fission yield measurements, analytical support to light water breeder reactor development, research on analytical methods, and the behavior of environmental species of iodine.

  9. Conceptual development of a test facility for spent fuel management

    International Nuclear Information System (INIS)

    Park, S.W.; Lee, H.H.; Lee, J.Y.; Lee, J.S.; Ro, S.G.

    1997-01-01

    Spent fuel management is an important issue for nuclear power program, requiring careful planning and implementation. With the wait-and-see policy on spent fuel management in Korea, research efforts are directed at KAERI to develop advanced technologies for safer and more efficient management of the accumulating spent fuels. In support of these research perspectives, a test facility of pilot scale is being developed with provisions for integral demonstration of a multitude of technical functions required for spent fuel management. The facility, baptized SMART (Spent fuel MAnagement technology Research and Test facility), is to be capable of handling full size assembly of spent PWR fuel (as well as CANDU fuel) with a maximum capacity of 10 MTU/y (about 24 assemblies of PWR type). Major functions of the facility are consolidation of spent PWR fuel assembly into a half-volume package and optionally transformation of the fuel rod into a fuel of CANDU type (called DUPIC). Objectives of these functions are to demonstrate volume reduction of spent fuel (for either longer-term dry storage or direct disposal ) in the former case and direct refabrication of the spent PWR fuel into CANDU-type DUPIC fuel for reuse in CANDU reactors in the latter case, respectively. In addition to these major functions, there are other associated technologies to be demonstrated : such as waste treatment, remote maintenance, safeguards, etc. As the facility is to demonstrate not only the functional processes but also the safety and efficiency of the test operations, engineering criteria equivalent to industrial standards are incorporated in the design concept. The hot cell structure enclosing the radioactive materials is configured in such way to maximize costs within the given functional and operational requirements. (author). 3 tabs., 4 figs

  10. Thermal fuel research and development facilities in BNFL

    International Nuclear Information System (INIS)

    Roberts, V.A.; Vickers, J.

    1996-01-01

    BNFL is committed to providing high quality, cost effective nuclear fuel cycle services to customers on a National and International level. BNFL's services, products and expertise span the complete fuel cycle; from fuel manufacture through to fuel reprocessing, transport, waste management and decommissioning and the Company maintains its technical and commercial lead by investment in continued research and development (R and D). This paper discusses BNFL's involvement in R and D and gives an account of the current facilities available together with a description of the advanced R and D facilities constructed or planned at Springfields and Sellafield. It outlines the work being carried out to support the company fuel technology business, to (1) develop more cost effective routes to existing fuel products; (2) maximize the use of recycled uranium, plutonium and tails uranium and (3) support a successful MOX business

  11. Management and Development of the RT Research Facilities and Infrastructures

    International Nuclear Information System (INIS)

    Kim, Won Ho; Nho, Young Chang; Kim, Jae Sung

    2009-01-01

    The purpose of this project are to operate the core facilities of the research for the Radiation Technology in stable and to assist the research activities efficiently in the industry, academic, and research laboratory. By developing the infrastructure of the national radio technology industry, we can activate the researching area of the RT and the related industry, and obtain the primary and original technology. The key point in the study of the RT and the assistance of the industry, academic, and research laboratory for the RT area smoothly, is managing the various of unique radiation facilities in our country. The gamma Phytotron and Gene Bank are essential in the agribiology because these facilities are used to preserve and utilize the genes and to provide an experimental field for the environment and biotechnology. The Radiation Fusion Technology research supporting facilities are the core support facilities, and are used to develop the high-tech fusion areas. In addition, the most advanced analytical instruments, whose costs are very high, should be managed in stable and be utilized in supporting works, and the experimental animal supporting laboratory and Gamma Cell have to be maintained in high level and managed in stable also. The ARTI have been developed the 30MeV cyclotron during 2005∼2006, aimed to produce radioisotopes and to research the beam applications as a result of the project, 'Establishment of the Infrastructure for the Atomic Energy Research Expansion', collaborated with the Korea Institute of Radiological and Medical Sciences. In addition, the ARTI is in the progress of establishing cyclotron integrated complex as a core research facility, using a proton beam to produce radioisotopes and to support a various research areas. The measurement and evaluation of the irradiation dose, and irradiation supporting technology of the Good Irradiation Practice(GIP) are essential in various researching areas. One thing to remember is that the publicity

  12. [The challenges of sustainable development in healthcare facilities].

    Science.gov (United States)

    Mourgues, François; Muret, Jane; Pauchard, Jean-Claude

    2018-03-01

    Healthcare and medical-social facilities have a major responsibility within society, that of the quality of care, but also that of developing a system of sustainable and socially-responsible health. This system must meet the three pillars which constitute such an approach: economic, social and environmental sustainability. Innovation remains central to the sustainable evolution of practices and the first results are now visible. Copyright © 2018 Elsevier Masson SAS. All rights reserved.

  13. Currently developing opportunities in food irradiation and modern irradiation facilities

    International Nuclear Information System (INIS)

    Wanke, R.

    1997-01-01

    I. Factor currently influencing advancing opportunities for food irradiation include: heightened incidence and awareness of food borne illnesses and causes. Concerns about ensuring food safety in international as well as domestic trade. Regulatory actions regarding commonly used fumigants/pesticides e.g. Me Br. II. Modern irradiator design: the SteriGenics M ini Cell . A new design for new opportunities. Faster installation of facility. Operationally and space efficient. Provides local o nsite control . Red meat: a currently developing opportunity. (Author)

  14. Development of an Extreme Environment Materials Research Facility at Princeton

    International Nuclear Information System (INIS)

    Cohen, A.B.; Gentile, C.A.; Tully, C.G.; Austin, R.; Calaprice, F.; McDonald, K.; Ascione, G.; Baker, G.; Davidson, R.; Dudek, L.; Grisham, L.; Kugel, H.; Pagdon, K.; Stevenson, T.; Woolley, R.; Zwicker, A.

    2010-01-01

    The need for a fundamental understanding of material response to a neutron and/or high heat flux environment can yield development of improved materials and operations with existing materials. Such understanding has numerous applications in fields such as nuclear power (for the current fleet and future fission and fusion reactors), aerospace, and other research fields (e.g., high-intensity proton accelerator facilities for high energy physics research). A proposal has been advanced to develop a facility for testing various materials under extreme heat and neutron exposure conditions at Princeton. The Extreme Environment Materials Research Facility comprises an environmentally controlled chamber (48 m 3 ) capable of high vacuum conditions, with extreme flux beams and probe beams accessing a central, large volume target. The facility will have the capability to expose large surface areas (1 m 2 ) to 14 MeV neutrons at a fluence in excess of 10 13 n/s. Depending on the operating mode. Additionally beam line power on the order of 15-75 MW/m 2 for durations of 1-15 seconds are planned. The multi-second duration of exposure can be repeated every 2-10 minutes for periods of 10-12 hours. The facility will be housed in the test cell that held the Tokamak Fusion Test Reactor (TFTR), which has the desired radiation and safety controls as well as the necessary loading and assembly infrastructure. The facility will allow testing of various materials to their physical limit of thermal endurance and allow for exploring the interplay between radiation-induced embrittlement, swelling and deformation of materials, and the fatigue and fracturing that occur in response to thermal shocks. The combination of high neutron energies and intense fluences will enable accelerated time scale studies. The results will make contributions for refining predictive failure modes (modeling) in extreme environments, as well as providing a technical platform for the development of new alloys, new

  15. Development of an Extreme Environment Materials Research Facility at Princeton

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, A B; Tully, C G; Austin, R; Calaprice, F; McDonald, K; Ascione, G; Baker, G; Davidson, R; Dudek, L; Grisham, L; Kugel, H; Pagdon, K; Stevenson, T; Woolley, R

    2010-11-17

    The need for a fundamental understanding of material response to a neutron and/or high heat flux environment can yield development of improved materials and operations with existing materials. Such understanding has numerous applications in fields such as nuclear power (for the current fleet and future fission and fusion reactors), aerospace, and other research fields (e.g., high-intensity proton accelerator facilities for high energy physics research). A proposal has been advanced to develop a facility for testing various materials under extreme heat and neutron exposure conditions at Princeton. The Extreme Environment Materials Research Facility comprises an environmentally controlled chamber (48 m^3) capable of high vacuum conditions, with extreme flux beams and probe beams accessing a central, large volume target. The facility will have the capability to expose large surface areas (1 m^2) to 14 MeV neutrons at a fluence in excess of 10^13 n/s. Depending on the operating mode. Additionally beam line power on the order of 15-75 MW/m2 for durations of 1-15 seconds are planned... The multi-second duration of exposure can be repeated every 2-10 minutes for periods of 10-12 hours. The facility will be housed in the test cell that held the Tokamak Fusion Test Reactor (TFTR), which has the desired radiation and safety controls as well as the necessary loading and assembly infrastructure. The facility will allow testing of various materials to their physical limit of thermal endurance and allow for exploring the interplay between radiation-induced embrittlement, swelling and deformation of materials, and the fatigue and fracturing that occur in response to thermal shocks. The combination of high neutron energies and intense fluences will enable accelerated time scale studies. The results will make contributions for refining predictive failure modes (modeling) in extreme environments, as well as providing a technical platform for the development of new alloys, new

  16. US/FRG umbrella agreement for cooperation in GCR Development. Fuel, fission products, and graphite subprogram. Quarterly status report, July 1, 1982-September 30, 1982

    International Nuclear Information System (INIS)

    Turner, R.F.

    1982-10-01

    This report describes the status of the cooperative work being performed in the Fuel, Fission Product, and Graphite Subprogram under the HTR-Implementing Agreement of the United States/Federal Republic of Germany Umbrella Agreement for Cooperation in GCR Development. The status is described relative to the commitments in the Subprogram Plan for Fuel, Fission Products, and Graphite, Revision 5, April 1982. The work described was performed during the period July 1, 1982 through September 30, 1982 in the HTGR Base Technology Program at Oak Ridge National Laboratory, the HTGR Fuel and Plant Technology Programs at General Atomic Company (GA), and the Project HTR-Brennstoffkreislauf of the Entwicklungsgemeinschaft HTR at KFA Julich, HRB Mannheim, HOBEG Hanau, and SIGRI Meitingen. The requirement for and format of this quarterly status report are specified in the HTR Implementing Agreement procedures for cooperation. Responsibility for preparation of the quarterly report alternates between GA and KFA

  17. Development of decommissioning technology for nuclear fuel facility

    International Nuclear Information System (INIS)

    Tanimoto, Ken-ichi

    1998-01-01

    There are many kinds of objects for decommissioning and their properties are greatly different in respects of morphology, constituent materials, contamination history, etc. Therefore, the techniques for decontamination and dismantlement are required to have a great applicability. In addition, most of contamination nuclides have long half-life and so, it is desirable to rapidly take measures to stop or close a contaminated facility. In consideration of these characteristics developments of elementary techniques for decontamination have been attempted. This report summarized the present states of decommissioning technology for nuclear fuel facility. The function and performance of each elementary technique were examined through test operation and simulation was made for the important techniques of them aiming at generalization and optimization. For remote handling technology, two operation tools; 'metal splitting saw cutting tool' and 'plasma cutting tool' were produced and utilizations of these tools in combination with a robot for conveyance are under investigation now. (M.N.)

  18. Development of decommissioning technology for nuclear fuel facility

    Energy Technology Data Exchange (ETDEWEB)

    Tanimoto, Ken-ichi [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1998-01-01

    There are many kinds of objects for decommissioning and their properties are greatly different in respects of morphology, constituent materials, contamination history, etc. Therefore, the techniques for decontamination and dismantlement are required to have a great applicability. In addition, most of contamination nuclides have long half-life and so, it is desirable to rapidly take measures to stop or close a contaminated facility. In consideration of these characteristics developments of elementary techniques for decontamination have been attempted. This report summarized the present states of decommissioning technology for nuclear fuel facility. The function and performance of each elementary technique were examined through test operation and simulation was made for the important techniques of them aiming at generalization and optimization. For remote handling technology, two operation tools; `metal splitting saw cutting tool` and `plasma cutting tool` were produced and utilizations of these tools in combination with a robot for conveyance are under investigation now. (M.N.)

  19. Diagnostic development and support of MHD (magnetohydrodynamics) test facilities

    Energy Technology Data Exchange (ETDEWEB)

    1989-07-01

    Mississippi State University (MSU) is developing diagnostic instruments for Magnetohydrodynamics (MHD) power train data acquisition and for support of MHD component development test facilities. Microprocessor-controlled optical instruments, initially developed for HRSR support, are being refined, and new systems to measure temperatures and gas-seed-slag stream characteristics are being developed. To further data acquisition and analysis capabilities, the diagnostic systems are being interfaced with MHD Energy Center computers. Technical support for the diagnostic needs of the national MHD research effort is being provided. MSU personnel will also cooperate with government agencies and private industries to improve the transformation of research and development results into processes, products and services applicable to their needs.

  20. 3Q/4Q99 F-Area Hazardous Waste Management Facility Corrective Action Report - Third and Fourth Quarter 1999, Volumes I and II

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.

    2000-05-12

    Savannah River Site (SRS) monitors groundwater quality at the F-Area Hazardous Waste management Facility (HWMF) and provides results of this monitoring to the South Carolina Department of Health and Environmental Control (SCDHEC) semiannually as required by the Resource Conservation and Recovery Act (RCRA) permit. SRS also performs monthly sampling of the Wastewater Treatment Unit (WTU) effluent in accordance with Section C of the Underground Injection Control (UIC) application.

  1. Trend chart: bio-methane injected in gas distribution systems. First quarter 2017

    International Nuclear Information System (INIS)

    2017-05-01

    This publication presents the bio-methane industry situation of continental France and overseas territories during the first quarter 2017: bio-methane production facilities, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus capacity and type, evolution forecasts of bio-methane production, detailed regional results, methodology used

  2. Trend chart: bio-methane injected in gas distribution systems. Third quarter 2017

    International Nuclear Information System (INIS)

    Moreau, Sylvain

    2017-11-01

    This publication presents the bio-methane industry situation of continental France and overseas territories during the third quarter 2017: bio-methane production facilities, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus capacity and type, evolution forecasts of bio-methane production, detailed regional results

  3. Trend chart: bio-methane injected in gas distribution systems. Fourth quarter 2017

    International Nuclear Information System (INIS)

    Moreau, Sylvain

    2018-02-01

    This publication presents the bio-methane industry situation of continental France and overseas territories during the fourth quarter 2017: bio-methane production facilities, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus capacity and type, evolution forecasts of bio-methane production, detailed regional results

  4. Trend chart: bio-methane injected in gas distribution systems. Second quarter 2017

    International Nuclear Information System (INIS)

    2017-08-01

    This publication presents the bio-methane industry situation of continental France and overseas territories during the first quarter 2017: bio-methane production facilities, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus capacity and type, evolution forecasts of bio-methane production, detailed regional results

  5. Development of a quality system for a contract irradiation facility

    International Nuclear Information System (INIS)

    Siyakus, G.

    2002-01-01

    The use of Industrial Irradiation Systems, in order to process medical supplies and food commodities, has almost 50 years experiences in the world. The food irradiation process has been approved by more than 40 countries around the world and it has been endorsed or supported by numerous national and international organizations and professional groups. Today, radiation sterilization of medical supplies is the most preferred technology in almost every developed country. Other applications: such as waste and flue gas treatment, polymer processing are also put into practice in wider range than before. Higher capital cost compared to the operation cost, the nature of continuous decay of the radiation sources used to obtain gamma rays, obligate the owners of gamma facilities to operate systems based on the 24 hours a day and 7 days per week. On the other hand, higher throughput capacity and economical brake point for profitability, force irradiation companies to offer service for the varied products of the companies. Industrial irradiation facilities providing services for varied companies by irradiating different kind of commodities so called contract irradiator or multipurpose irradiator and most of the irradiation facilities, particularly gamma irradiators running in different locations of the World, operates as contract irradiators. The radiation facilities are considered as a part of the manufacturing process, and must conform to the pertinent general Code of Good Manufacturing Practice (GMP) which has been declared by the principal producer. Customers of these facilities may have petitions, such as irradiation temperature, dose rate, minimal and maximal doses; storage conditions before and after irradiation. Design parameters related to the dose rate, product size, density and weight, irradiation and storage temperatures are the main limitations. Varied process conditions can be easily applied in the laboratory may set forth difficulties in industrial processes

  6. The development of a combined effects space simulation facility

    Energy Technology Data Exchange (ETDEWEB)

    Maldonado, Carlos A.; Lilly, Taylor C.; Ketsdever, Andrew D. [University of Colorado, Colorado Springs, Department of Mechanical and Aerospace Engineering, Colorado Springs, CO 80918 (United States)

    2012-11-27

    An overview of the development of a facility to study the combined effects of the space environment on spacecraft is presented. The characterization of a magnetic filter plasma source and a low energy electron flood source for the simulation of the low Earth orbit plasma environment is discussed. Plasma diagnostics show that the magnetic filter plasma source provides streaming ion energies of approximately 5eV and can supply the appropriate density for LEO simulation. Additionally the low energy flood gun is shown to provide the appropriate density for LEO simulation as a function of altitude and solar activity.

  7. Currently developing opportunities in food irradiation and modern irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Wanke, R. [Director Business Development. SteriGenics International Inc. 17901 East Warren Avenue No. 4, Detroit, Michigan 48224-1333 (United States)

    1997-12-31

    I. Factor currently influencing advancing opportunities for food irradiation include: heightened incidence and awareness of food borne illnesses and causes. Concerns about ensuring food safety in international as well as domestic trade. Regulatory actions regarding commonly used fumigants/pesticides e.g. Me Br. II. Modern irradiator design: the SteriGenics {sup M}ini Cell{sup .} A new design for new opportunities. Faster installation of facility. Operationally and space efficient. Provides local {sup o}nsite control{sup .} Red meat: a currently developing opportunity. (Author)

  8. Ion implantation in Thailand (I) - development of ion implantation facilities

    International Nuclear Information System (INIS)

    Vilaithong, T.; Suwannakachorn, D.; Yotsombat, B.; Boonyawan, D.; Charoennugul, R.; Vichaisirimongkol, P.; Aumkaew, S.; A-No, V.

    1997-01-01

    Ion implantation with its many advantages has been widely and rapidly developed in the world to be a novel material treatment technique, which holds significance in both academic research and technical application. In order to develop and apply the ion implantation technique in the country, Thailand has launched a program to establish an ion beam center at Chiang Mai University. By efforts made during the past six years, the University has completed construction and installation of a 150-kV, research-purpose ion implantation facility, which consists of two beam lines - a 00 non-analyzed line and a 450 analyzed line, and which is being put into regular operation, and a 20-kV, high-current ion implanter based on a duoplasmatron ion source for non-analyzed N-ion beam implantation, and a high-intensity, multi cusp ion source for special implantation purposes. The facilities have formed powerful tools for research, teaching and engineering application, and have played an indispensable role in promoting development of novel techniques in the country

  9. Mitigating project development and facility operation risks with systems engineering

    Science.gov (United States)

    Ansorge, Wolfgang R.

    2004-09-01

    The presentation illustrates the standard life cycles and project phases of a typical large scale astronomical facility acqui-sition and development project and explains the role of Systems Engineering (SE) during the entire project life cycle. The basic SE philosophy and systematic SE approach are described and a road map identifying the main activities of SE during the individual project phases - from the requirement definition to the eventual validation of the erected system- is developed. In addition the presentation describes the methodologies and processes SE can offer to analyse the risks asso-ciated with the definition, development and implementation of large complex scientific infrastructure projects. Risk control methods and approaches which are necessary to systematically reduce the technical, financial and schedule risks to a level acceptable to the scientific / technical project management and to the funding agencies are explained.

  10. Upgrade of the BATMAN test facility for H- source development

    Science.gov (United States)

    Heinemann, B.; Fröschle, M.; Falter, H.-D.; Fantz, U.; Franzen, P.; Kraus, W.; Nocentini, R.; Riedl, R.; Ruf, B.

    2015-04-01

    The development of a radio frequency (RF) driven source for negative hydrogen ions for the neutral beam heating devices of fusion experiments has been successfully carried out at IPP since 1996 on the test facility BATMAN. The required ITER parameters have been achieved with the prototype source consisting of a cylindrical driver on the back side of a racetrack like expansion chamber. The extraction system, called "Large Area Grid" (LAG) was derived from a positive ion accelerator from ASDEX Upgrade (AUG) using its aperture size (ø 8 mm) and pattern but replacing the first two electrodes and masking down the extraction area to 70 cm2. BATMAN is a well diagnosed and highly flexible test facility which will be kept operational in parallel to the half size ITER source test facility ELISE for further developments to improve the RF efficiency and the beam properties. It is therefore planned to upgrade BATMAN with a new ITER-like grid system (ILG) representing almost one ITER beamlet group, namely 5 × 14 apertures (ø 14 mm). Additionally to the standard three grid extraction system a repeller electrode upstream of the grounded grid can optionally be installed which is positively charged against it by 2 kV. This is designated to affect the onset of the space charge compensation downstream of the grounded grid and to reduce the backstreaming of positive ions from the drift space backwards into the ion source. For magnetic filter field studies a plasma grid current up to 3 kA will be available as well as permanent magnets embedded into a diagnostic flange or in an external magnet frame. Furthermore different source vessels and source configurations are under discussion for BATMAN, e.g. using the AUG type racetrack RF source as driver instead of the circular one or modifying the expansion chamber for a more flexible position of the external magnet frame.

  11. Development of PSA procedure for a criticality in reprocessing facilities

    International Nuclear Information System (INIS)

    Endo, Shigeki; Takanashi, Mitsuhiro; Ueda, Yoshinori

    2012-08-01

    Utilization of risk information for the nuclear safety regulation is being discussed in Japan. The development of probabilistic safety assessment (PSA) procedure is indispensable for the utilization of risk information. The Japan Nuclear Energy Safety Organization (JNES) has been conducting trial PSA to a model plant for major events, i.e. hydrogen explosion, solution boiling, rapid decomposition of TBP complexes, criticality, solvent fire, leakage of molten glass, leakage of high active concentrated liquid waste, loss of all AC electricity, drop of a fuel assembly, for the purpose of developing the PSA procedure for reprocessing facilities. For criticality events results of trial PSA were summarized as a report in which how to evaluate an amount of radioactive materials released from a facility and a health effect on the public were emphasized. Therefore, for criticality events the results of trial PSA were summarized in this report to emphasize procedures from making event progression scenarios to quantifying event sequences, which were not handled in the previous report, in a style of a document describing PSA procedures. (author)

  12. Research and Development Program for the PALS Facility

    International Nuclear Information System (INIS)

    Jungwirth, K.

    2001-01-01

    Status of the PALS laser system is given and its upgrades implemented up to now as well as those under preparation are also described. During the first year run the PALS facility has proved to be a reliable tool for generating plasmas by using infrared (1315 nm) 0,4-ns laser pulses, with the energy adjustable over two orders of magnitude ( 10 J - 1 kJ). The current PALS research program concentrates along the following two main lines: development and application of (1) laser driven x-ray sources, including the x-ray lasers, and (2) of laser driven ion sources. Simultaneously, new methods of x-ray diagnostics, of soft x-ray detection and x-ray spectroscopy in particular, are being developed and implemented. During the period September 2000 - June 2001, most of the experiments at PALS have been performed within the EC th FP. Towards the end of this period an x-ray laser on Zn (λ =21.2 nm) has been successfully put into operation and used for interferometric measurements in cooperation with the French colleagues. More detailed information about some of the results briefly summarized in the paper is presented at the Symposium via separate oral papers and posters, too. Experience of the first year of operation is essential also for further upgrading of the PALS facility towards higher power outputs. (author)

  13. The current status of ASTRO-H/HXT development facility

    Science.gov (United States)

    Furuzawa, Akihiro; Ogasaka, Yasushi; Kunieda, Hideyo; Miyazawa, Takuya; Sakai, Masato; Kinoshita, Yosuke; Makinae, Youta; Sasaya, Shiori; Kanou, Yasufumi; Niki, Daisuke; Ohgi, Takuya; Oishi, Nodoka; Yamane, Koudai; Yamane, Nobuyuki; Ishida, Yosuke; Haba, Yoshito; Tawara, Yuzuru; Yamashita, Koujun; Ishida, Manabu; Maeda, Yoshitomo; Mori, Hideyuki; Tamura, Keisuke; Awaki, Hisamitsu; Okajima, Takashi

    2009-08-01

    We present the current state of the development system of the hard ray telescope onboard ASTRO-H satellite. Japan's 6th X-ray satellite mission ASTRO-H, which is planed to be launched in fiscal year 2013, will carry four X-ray telescopes (XRT). Two of four XRTs are hard X-ray telescopes (HXT) using depth-graded multilayer reflector which provide us the capability of hard X-ray imaging observation up to 80 keV. ASTRO-H/HXT is the light-weight hard X-ray telescope using Pt/C depth-graded multilayer and high-throughput thin-foil optics. The basic technology for fabricating the ASTRO-H/HXT has been established through the balloon borne experiments, "InFOCμS" (US-Japan international joint experiment) and "SUMIT" missions. (Nagoya University, Osaka University and JAXA). Major changes from XRTs onboard InFOCμS and SUMIT missions are large aperture size of 45 cm in diameter, the length of reflectors of 20 cm and the focal length of 12 m (XRTs onboard the balloon missions above have the aperture size of 40 cm in diameter, 13 cm long reflectors and 8 m focal length). Now we have almost finished to establish the mirror production facility dedicated to the ASTRO-H/HXT and are starting to produce foil reflectors for performance verification of 200 mm long reflector. We report the current status of the development facilities and test foil production.

  14. Nigerian Quarterly Journal of Hospital Medicine

    African Journals Online (AJOL)

    Nigerian Quarterly Journal of Hospital Medicine is published quarterly and the contents include articles in Medicine, Dentistry, Pharmaceutical and Basic Medical Sciences with emphasis on health problems and solutions relating to developing countries. The readership are in - Libraries, Teaching Hospitals, Universities, ...

  15. Geoscience Workforce Development at UNAVCO: Leveraging the NSF GAGE Facility

    Science.gov (United States)

    Morris, A. R.; Charlevoix, D. J.; Miller, M.

    2013-12-01

    Global economic development demands that the United States remain competitive in the STEM fields, and developing a forward-looking and well-trained geoscience workforce is imperative. According to the Bureau of Labor Statistics, the geosciences will experience a growth of 19% by 2016. Fifty percent of the current geoscience workforce is within 10-15 years of retirement, and as a result, the U.S. is facing a gap between the supply of prepared geoscientists and the demand for well-trained labor. Barring aggressive intervention, the imbalance in the geoscience workforce will continue to grow, leaving the increased demand unmet. UNAVCO, Inc. is well situated to prepare undergraduate students for placement in geoscience technical positions and advanced graduate study. UNAVCO is a university-governed consortium facilitating research and education in the geosciences and in addition UNAVCO manages the NSF Geodesy Advancing Geosciences and EarthScope (GAGE) facility. The GAGE facility supports many facets of geoscience research including instrumentation and infrastructure, data analysis, cyberinfrastructure, and broader impacts. UNAVCO supports the Research Experiences in the Solid Earth Sciences for Students (RESESS), an NSF-funded multiyear geoscience research internship, community support, and professional development program. The primary goal of the RESESS program is to increase the number of historically underrepresented students entering graduate school in the geosciences. RESESS has met with high success in the first 9 years of the program, as more than 75% of RESESS alumni are currently in Master's and PhD programs across the U.S. Building upon the successes of RESESS, UNAVCO is launching a comprehensive workforce development program that will network underrepresented groups in the geosciences to research and opportunities throughout the geosciences. This presentation will focus on the successes of the RESESS program and plans to expand on this success with broader

  16. Quarterly coal report

    Energy Technology Data Exchange (ETDEWEB)

    Young, P.

    1996-05-01

    The Quarterly Coal Report (QCR) provides comprehensive information about U.S. coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. The data presented in the QCR are collected and published by the Energy Information Administration (EIA) to fulfill data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275), as amended. This report presents detailed quarterly data for October through December 1995 and aggregated quarterly historical data for 1987 through the third quarter of 1995. Appendix A displays, from 1987 on, detailed quarterly historical coal imports data, as specified in Section 202 of the Energy Policy and Conservation Amendments Act of 1985 (Public Law 99-58). Appendix B gives selected quarterly tables converted to metric tons.

  17. The technical development on recycled aggregate concrete for nuclear facility

    International Nuclear Information System (INIS)

    Sukekiyo, M.; Saishu, S.; Ishikura, T.; Ishigure, K.

    2000-01-01

    The large amount of non-radioactive concrete waste generated by decommissioning has a very big impact on the final disposal site. Therefore, NUPEC has been developing technology which recovers at a high ratio the aggregate from the dismantling concrete with a quality which can be used to construct a new nuclear power plant. The developed high-quality recycled aggregate meets the quality standards of the natural aggregate stipulated by the Japanese architectural standard specifications for nuclear power plant facilities. As a result of these experiments, it was confirmed that the recycled concrete which used this high-quality recycled aggregate had a performance equal or better than ordinary concrete which used natural aggregate. (authors)

  18. Implementation study for the NRC Application and Development Facility

    International Nuclear Information System (INIS)

    Sherwood, R.J.; Ross, D.J.; Sasser, D.W.

    1979-01-01

    The Nuclear Regulatory Commission (NRC) has expressed the desire to establish an Application and Development Facility (ADF) for NRC Headquarters. The ADF is a computer system which will provide safeguards analysts access to safeguards analysis computer software. This report analyzes the issues, requirements and options available in the establishment of an ADF. The purpose and goals of the ADF are presented, along with some general issues to be considered in the implementation of such a system. A phased approach for ADF implementation, which will allow for the earliest possible access to existing codes and also allow for future expansion, is outlined. Several options for central computers are discussed, along with the characteristics and approximate costs for each. The report concludes with recommended actions proposed to start the development of the ADF

  19. The development of functional requirement for integrated test facility

    International Nuclear Information System (INIS)

    Sim, B.S.; Oh, I.S.; Cha, K.H.; Lee, H.C.

    1994-01-01

    An Integrated Test Facility (ITF) is a human factors experimental environment comprised of a nuclear power plant function simulator, man-machine interfaces (MMI), human performance recording systems, and signal control and data analysis systems. In this study, we are going to describe how the functional requirements are developed by identification of both the characteristics of generic advanced control rooms and the research topics of world-wide research interest in human factors community. The functional requirements of user interface developed in this paper together with those of the other elements will be used for the design and implementation of the ITF which will serve as the basis for experimental research on a line of human factors topics. (author). 15 refs, 1 fig

  20. Development of an advanced, continuous mild gasification process for the production of co-products. Quarterly report, July 1, 1992--September 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    O`Neal, G.W.

    1992-12-31

    The coke reactivity test furnace was installed and checked. Design of a long lasting reaction vessel is underway with emphasis on material of construction for elevated temperatures. Development of a formed coke formula is continuing in preparation of a 70 pound sample for evaluation by a major conventional coke producer. Ten CMGU test runs were made. Most of the quarter was used to replace the pyrolyzer screws, check-out the screws` pulse burners, and replace the screws` stub shafts. The objective of the determination of the pyrolyzer maximum capacity with the internal screws` heaters should be achieved in October 1992.

  1. 1st quarterly report 1977

    International Nuclear Information System (INIS)

    1977-06-01

    The present report describes the activities carried out in the 1st quarter of 1977 at the Gesellschaft fuer Kernforschung in Karlsruhe or on its behalf in the framework of the fast breeder project (PSB). The problems and main results of the partial projects fuel rod development, materials testing, reactor physics, reactor safety and reactor technology are presented. (RW) [de

  2. NST Quarterly - issue October 2001

    International Nuclear Information System (INIS)

    2001-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it reviews GM technology and GMOs - genetically modified organisms. The topics discussed includes the implication of GM in practice, the controversy and the prospect of GM technology. Radioactive pig - something like a ball or plug which cleanses the inner walls of the pipeline, also briefly presented

  3. NST Quarterly - April 2000 issue

    International Nuclear Information System (INIS)

    1999-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in genetic engineering. The articles summarized the improvement of orchids and tulips through genetic engineering and generating new varieties for the floriculture industry. It also reported, MINT won gold and silver at the International Invention 2000, 12-16 April 2000, Geneva

  4. The development of a Space Shuttle Research Animal Holding Facility

    Science.gov (United States)

    Jagow, R. B.

    1980-01-01

    The ability to maintain the well being of experiment animals is of primary importance to the successful attainment of life sciences flight experiment goals. To assist scientists in the conduct of life sciences flight experiments, a highly versatile Research Animal Holding Facility (RAHF) is being developed for use on Space Shuttle/Spacelab missions. This paper describes the design of the RAHF system, which in addition to providing general housing for various animal species, approximating the environment found in ground based facilities, is designed to minimize disturbances of the specimens by vehicle and mission operations. Life-sustaining capabilities such as metabolic support and environmental control are provided. RAHF is reusable and is a modular concept to accommodate animals of different sizes. The basic RAHF system will accommodate a combination of 24 500-g rats or 144 mice or a mixed number of rats and mice. An alternative design accommodates four squirrel monkeys. The entire RAHF system is housed in a single ESA rack. The animal cages are in drawers which are removable for easy access to the animals. Each cage contains a waste management system, a feeding system and a watering system all of which will operate in zero or one gravity.

  5. Offline Ion Source Developments for the BECOLA Facility at NSCL

    Science.gov (United States)

    Klose, Andrew; Mantica, Paul; Minamisono, Kei

    2013-04-01

    Singly-charged beams of the stable isotope(s) of K, Ca, Mn, and Fe have been produced using either a commercial plasma ion source or a home-built electron ionization source for the BEam COoler and LAser spectroscopy (BECOLA) facility at the National Superconducting Cyclotron Laboratory (NSCL) at Michigan State University. For each element, collinear laser spectroscopy was performed to confirm the presence of the respective element. Production of stable ion beams for a given element is necessary to obtain reference hyperfine spectra of species with known electromagnetic moments before such nuclear properties can be deduced from the laser hyperfine-structure measurements of rare isotopes that are planned at NSCL. The results from the commissioning tests of the plasma and electron ionization sources will be presented, and development of a new Penning Ion Gauge (PIG) ion source will be discussed.

  6. Development of the Decommissioning Technology for Nuclear Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kim, G. N.; Kim, S. G.

    2010-04-01

    The evaluation technology of decommissioning process must be developed and will be used for the ALARA planning tool of decommissioning process and demonstrated for tools of decommissioning equipment. Also, this technology can be used for tools workplaces with high work difficulty such as large-scale chemical plant, under water and space. The monitoring system for high alpha radioactive contamination measurement will be use in the high radioactivity decommissioning sites such as hot-cell or glove box. Also, it will be use in the general nuclear facilities as the radiation monitoring unit. The preparation technology of the radiation sensor for high radioactive contamination measurement will be transferred to the company for the industrialization. The remote monitoring system can prevent the workers exposure using the optical fiber to separate the sensor and electronics

  7. Scenario Development for Trgovska Gora Shallow Land Facility

    International Nuclear Information System (INIS)

    Skanata, D.; Medakovic, S.; Lokner, V.; Levanat, I.

    2002-01-01

    Safety assessments, either preliminary or final, consist of a qualitative and a quantitative part. The qualitative part of the assessment implies a selection of relevant scenarios to be analyzed, while the quantitative part of the assessment consists of their mathematical modeling. This work is dealing with the qualitative part of safety assessment concerning a specific radioactive waste disposal system, i.e., the shallow land facility situated on the macrolocation Trgovska gora. This article has as its purpose a brief presentation of the ISAM methodology application results (Improvement of Safety Assessment Methodologies for Near Surface Radioactive Waste Facilities;), a methodology developed within the framework of a project of the same name, organized by the IAEA. The above mentioned methodology is based on the development of the so-called FEP list (Features, Events, Process), on selection procedure of the FEP list, specifically regarding particular criteria defined in advance, and on application of systematic methods of selecting relevant scenarios (in this case the matrix of interactions method has been applied). The main aim and purpose of a methodology based on the analysis of FEPs (identification, classification, selection, construction of the matrix of interactions) consists of observing and documenting all the features, events and processes due to be taken into consideration while assessing safety of a particular radioactive waste disposal system. In this connection, by radioactive waste disposal system we mean a system consisting of radioactive waste and engineer features (barriers), geological environment within which the disposal site is located, surface-environment (soil, sediments, vegetation, etc.) and human population near the disposal site. The final step of the application of this methodology consists of generating the scenario using the matrix of interactions. So, for shallow land facility situated on the macrolocation Trgovska gora, applying

  8. Development of holdup monitor system (HMOS) during facility maintenance

    International Nuclear Information System (INIS)

    Nakamura, Hironobu; Hosoma, Takashi; Tanaka, Izumi

    1999-01-01

    Holdup MOnitor System (HMOS) was developed for the purpose of verifying the constant holdup during facility maintenance in Plutonium Conversion Development Facility (PCDF). The glove box assay system (GBAS; big slab) has been used by inspectors, measures the holdup periodically (i.e. IIV) using coincidence counting. The GBAS couldn't be used for inspection during maintenance period. Because many glove boxes (GB) set in process area had been occupied by large vinyl green-houses due to maintenance. We aimed that the holdup except for the maintenance GB should be constant during maintenance period, the HMOSs were set to 3 GBs. The system had been used from June '98 to July '99 for verification. The HMOS detector is located top/bottom of the GB, counts total neutron variation in the GB continuously. Detector efficiencies are 1.2%(top) and 0.12%(bottom), respectively. The measurement variation is observed up to 1.5%(3σ). The HMOS has high sensitivity 8 to 90g Pu (3σ; In case of 1kg Pu holdup, the sensitivity depends on position in the GB). The movement of equipment or nuclear material from/in the GB can be detected effectively. Though the HMOS observes measurement variation related to humidity in the GB, hygroscopic effect of denitration MOX powder, material/equipment movement and mainly 241 Pu nuclear decay, this system can verify that the holdup is constant qualitatively. As a result, in PCDF, safeguard related to the inventory verification during maintenance period (more than 1 year) were successfully performed using holdup monitor system. (author)

  9. Module Experimental Process System Development Unit (MEPSDU). Quarterly report No. 1, November 26, 1980-February 28, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Rose, C. M.

    1981-01-01

    Technical work during the first quarter of the program was directed toward completing all design and documentation tasks associated with the MEPSDU Preliminary Design Review Data Package submittal. Highlights of this effort consisted of: (1) preparation of a preliminary specification for MEPSDU input sheet material (dendritic web silicon); (2) preparation of a MEPSDU module preliminary design layout drawing and all associated detail drawings; (3) analysis of the performance of the MEPSDU module over a range of operating conditions; (4) definition of all steps in the baseline process sequence; (5) initiation of equipment specifications for all long lead time items in the MEPSDU; (6) initiation of preliminary design work on the cassette unload element and interconnect feed element of the automated cell interconnect station; and (7) preparation of the preliminary quality assurance plan. (WHK)

  10. The development of robot application technology in nuclear facilities

    International Nuclear Information System (INIS)

    Kim, Seung Ho; Lee, Jong Min; Kim, Chang Hoe; Kim, Byung Soo; Sohn, Surg Won; Hwoang, Suk Yeoung; Lee, Yong Bum; Kim, Woong Ki

    1992-12-01

    The objective of this project is to establish the basic technologies for advanced robotic systems operated in unstructured environment. The developed robotic system, which is remotely controlled, is expected to reduce the radiation dosage for workers who do the maintenance, inspection, and repairing work in nuclear facilities. The two major work scopes of this project in this year are to study the control scheme of advanced robotic system and develop a mobile robot. An inverse kinematic algorithm of 7 degrees of freedom anthropomorphic manipulator is investigated for dexterous control. Extended closed-loop schemes for solving the inverse kinematics of the redundant manipulator have been proposed and decentralized adaptive controller was designed by utilizing a new cartesian space controller. Control architecture of neural network has been developed, which has a strong capability on solving the kinematics of manipulator. The planetary wheel assembly has been implemented in the design to be suitable for plant. The design of manipulator has been implemented to operate with the battery power in the mobile system. This project will continue to be a major technical driver, with nuclear plant maintenance and waste management applications in conjunction with 'Long-term nuclear development program' over the next decade. (Author)

  11. Joyo, the irradiation and demonstration test facility of FBR development

    International Nuclear Information System (INIS)

    Aoyama, T.; Sekine, T.; Nakai, S.; Suzuki, S.

    2006-01-01

    Full text: Full text: The experimental fast reactor JOYO at the O-arai Research and Development Center of the Japan Atomic Energy Agency is the first liquid sodium fast reactor in JAPAN. The purpose of constructing JOYO was to obtain technical information about liquid metal fast breeder reactors (LMFBR) through experience with its design, construction and operation, and to use the reactor as a fast neutron irradiation facility for the development of fuels, materials, and other components required for the LMFBR program. Through design, construction, testing, operation and maintenance experience, JOYO has contributed much to the LMFBR development program. In addition to providing operating experience, many kinds of irradiation tests have been conducted for the development of fuels and materials under the conditions of higher fast neutron flux and temperature than those in LWRs. JOYO has been operated successfully since its criticality was first achieved in 1977 without any serious problem, and this operation demonstrated the safety and reliability of the sodium cooled fast reactor. Continual facility improvements have been punctuated by major enhancements, the latest of which is MK-III. Milestones in the MK-III upgrade project included: basic design studies, replacement of major heat transport components and the entire reactor core, and, finally, functional testing and performance testing. Compared to MK-II, MK-UI has a four times larger irradiation capability, improved irradiation test vehicles and improved irradiation characterization. The applications of this enhanced capability include testing fuels and safety features for future FBRs, exploring use of fast reactors for transmutation of radioactive waste, and developing advanced materials for fusion power. The utilization plan for JOYO after the MK-III modification is scheduled as follows: Oxide dispersion strengthened ferritic steel (ODS), which is the most promising candidate for fuel cladding of future long

  12. Developing operating procedures for a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G.

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures

  13. Developing operating procedures for a low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

  14. Development and operation of a mobile test facility for education

    Science.gov (United States)

    Davis, Christopher T.

    The automotive industry saw a large shift towards vehicle electrification after the turn of the century. It became necessary to ensure that new and existing engineers were qualified to design and calibrate these new systems. To ensure this training, Michigan Tech received a grant to develop a curriculum based around vehicle electrification. As part of this agenda, the Michigan Tech Mobile Laboratory was developed to provide hands-on training for professional engineers and technicians in hybrid electric vehicles and vehicle electrification. The Mobile Lab has since then increased the scope of the delivered curriculum to include other automotive areas and even customizable course content to meet specific needs. This thesis outlines the development of the Mobile Laboratory and its powertrain test facilities. The focus of this thesis is to discuss the different hardware and software systems within the lab and test cells. Detailed instructions on the operation and maintenance of each of the systems are discussed. In addition, this thesis outlines the setup and operation of the necessary equipment for several of the experiments for the on and off campus courses and seminars.

  15. Power Systems Development Facility Gasification Test Campaing TC18

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2005-08-31

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device (PCD), advanced syngas cleanup systems, and high pressure solids handling systems. This report details Test Campaign TC18 of the PSDF gasification process. Test campaign TC18 began on June 23, 2005, and ended on August 22, 2005, with the gasifier train accumulating 1,342 hours of operation using Powder River Basin (PRB) subbituminous coal. Some of the testing conducted included commissioning of a new recycle syngas compressor for gasifier aeration, evaluation of PCD filter elements and failsafes, testing of gas cleanup technologies, and further evaluation of solids handling equipment. At the conclusion of TC18, the PSDF gasification process had been operated for more than 7,750 hours.

  16. Anatomy Education in Namibia: Balancing Facility Design and Curriculum Development

    Science.gov (United States)

    Wessels, Quenton; Vorster, Willie; Jacobson, Christian

    2012-01-01

    The anatomy curriculum at Namibia's first, and currently only, medical school is clinically oriented, outcome-based, and includes all of the components of modern anatomical sciences i.e., histology, embryology, neuroanatomy, gross, and clinical anatomy. The design of the facilities and the equipment incorporated into these facilities were directed…

  17. Room temperature quarter wave resonator re-buncher development for a high power heavy-ion linear accelerator

    Science.gov (United States)

    Kim, Hye-Jin; Choi, B. H.; Han, Jaeeun; Hyun, Myung Ook; Park, Bum-Sik; Choi, Ohryoung; Lee, Doyoon; Son, Kitaek

    2018-03-01

    In the medium energy beam transport (MEBT) line system of the RAON which consists of several quadrupole magnets, three normal-conducting re-bunchers, and several diagnostic devices, a quarter wave resonator type re-buncher was chosen for minimizing longitudinal emittance growth and manipulating a longitudinal phase ellipse into the longitudinal acceptance of the low energy linac. The re-buncher has a resonant frequency of 81.25 MHz, geometrical beta (βg) of 0.049, and physical length of 24 cm. Based on the result of numerical calculations of electromagnetic field using CST-MWS and mechanical analysis of the heat distribution and deformation, an internal structure of the re-buncher was optimized to increase the effective voltage and to reduce power losses in the wall. The criteria of the multipacting effect was estimated and it was confirmed by the experiment. The position and specification of cooling channels are designed to recover a heat load up to 15 kW with reasonable margin of 25%. The coaxial and loop type RF power coupler are positioned on the high magnetic field region and two slug tuners are installed perpendicularly to the beam axis. The frequency sensitivity as a function of the tuner depth and cooling water temperature is measured and the frequency shift is in all cases within the provided tuner range. The test with a high power of 10 kW and the continuous wave is performed and the reflection power is observed less than 450 W.

  18. Hardware Development Process for Human Research Facility Applications

    Science.gov (United States)

    Bauer, Liz

    2000-01-01

    The simple goal of the Human Research Facility (HRF) is to conduct human research experiments on the International Space Station (ISS) astronauts during long-duration missions. This is accomplished by providing integration and operation of the necessary hardware and software capabilities. A typical hardware development flow consists of five stages: functional inputs and requirements definition, market research, design life cycle through hardware delivery, crew training, and mission support. The purpose of this presentation is to guide the audience through the early hardware development process: requirement definition through selecting a development path. Specific HRF equipment is used to illustrate the hardware development paths. The source of hardware requirements is the science community and HRF program. The HRF Science Working Group, consisting of SCientists from various medical disciplines, defined a basic set of equipment with functional requirements. This established the performance requirements of the hardware. HRF program requirements focus on making the hardware safe and operational in a space environment. This includes structural, thermal, human factors, and material requirements. Science and HRF program requirements are defined in a hardware requirements document which includes verification methods. Once the hardware is fabricated, requirements are verified by inspection, test, analysis, or demonstration. All data is compiled and reviewed to certify the hardware for flight. Obviously, the basis for all hardware development activities is requirement definition. Full and complete requirement definition is ideal prior to initiating the hardware development. However, this is generally not the case, but the hardware team typically has functional inputs as a guide. The first step is for engineers to conduct market research based on the functional inputs provided by scientists. CommerCially available products are evaluated against the science requirements as

  19. Nuclear Rocket Program quarterly progress report: Fourth quarter

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1965-12-31

    This document summarizes the progress of the ANL Nuclear Rocket Study during the fourth quarter of Calendar Year 1965. It is intended as a report of the status of the rocket program in the period following the publication of ANL-7111 (December 1965). The present document is one of a series of program reports which are issued on a regular quarterly basis. During the period of time encompassed by the present document, a major portion of the ANL nuclear rocket effort, as well as primary program emphasis, was placed upon the development of fuel elements and fuel-element systems. Concentration on these aspects of the rocket development effort reflects a general recognition on the part of ANL and the sponsoring agency that the solution of the problem of fuel-element fabrication constitutes the most critical phase of the program.

  20. Consolidated Quarterly Report: Number of potential release sites subject to corrective action

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John R.; Cochran, John R.

    2017-04-01

    This Sandia National Laboratories, New Mexico Environmental Restoration Operations (ER) Consolidated Quarterly Report (ER Quarterly Report) fulfills all quarterly reporting requirements set forth in the Resource Conservation and Recovery Act Facility Operating Permit and the Compliance Order on Consent. The 12 sites in the corrective action process are listed in Table I-1.

  1. Developing of the protocol for electron beam food irradiation facility

    International Nuclear Information System (INIS)

    Petreska, Svetlana

    2012-01-01

    By establishing the needs for institution of new technologies in the process of food processing, in this case a randomized choice of electron beam accelerator facility, arises the need for designing a protocol for safe and secure performance of the facility. The protocol encompasses safety and security measures for protection from ionizing radiation of the individuals who work at the facility, as well as, the population and the environment in the immediate neighborhood of the facility. Thus, the adopted approach is the establishment of appropriate systems responding to the protocol. Dosimetry system, which includes appropriate procedures for accurate measure and recording of the absorbed dose values, according to the provisions for protection from ionizing radiation. Ionizing radiation protection system and providing the safety and security of the facility for food processing by means of ionizing radiation. System for providing quality and safety control of the facility for food processing by means of ionizing radiation. Pursuant to the designed a protocol for safe and secure performance of the facility for electron beam food processing, contributes to protection against ionizing radiation as occupationally exposed persons as well the population. (Author)

  2. Development of the RRR cold neutron beam facility

    International Nuclear Information System (INIS)

    Lovotti, Osvaldo; Masriera, Nestor; Lecot, Carlos; Hergenreder, Daniel

    2002-01-01

    This paper describes some general design issues on the neutron beam facilities (cold neutron source and neutron beam transport system) of the Replacement Research Reactor (RRR) for the Australian Nuclear Science and Technology Organisation (ANSTO). The description covers different aspect of the design: the requirements that lead to an innovative design, the overall design itself, the definition of a technical approach in order to develop the necessary design solutions, and finally the organizational framework by which international expertise from five different institutions is integrated. From the technical viewpoint, the RRR-CNS is a liquid Deuterium (LD2) moderator, sub-cooled to ensure maximum moderation efficiency, flowing within a closed natural circulation thermosyphon loop. The thermosyphon is surrounded by a zirconium alloy CNS vacuum containment that provides thermal insulation and a multiple barriers scheme to prevent Deuterium from mixing with water or air. Consistent with international practice, this vessel is designed to withstand any hypothetical energy reaction should Deuterium and air mix in its interior. The 'cold' neutrons are then taken by the NBTS and transported by the neutron guide system into the reactor beam hall and neutron guide hall, where neutron scattering instruments are located. From the management viewpoint, the adopted distributed scheme is successful to manage the complex interfacing between highly specialized technologies, allowing a smooth integration within the project. (author)

  3. Development of a test facility for analyzing supercritical fluid blowdown

    Energy Technology Data Exchange (ETDEWEB)

    Roberto, Thiago D.; Alvim, Antonio C.M., E-mail: thiagodbtr@gmail.com [Coordenacao dos Programas de Pos-Graduacao em Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Silva, Mario A.B. da, E-mail: mabs500@gmail.com [Universidade Federal de Pernambuco (CTG/UFPE), Recife, PE (Brazil). Departamento de Energia Nuclear; Lapa, Celso M.F., E-mail: lapa@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    The generation IV nuclear reactors under development mostly use supercritical fluids as the working fluid because higher temperatures improve the thermal efficiency. Supercritical fluids are used by modern nuclear power plants to achieve thermal efficiencies of around 45%. With water as the supercritical working fluid, these plants operate at a high temperature and pressure. However, experiments on supercritical water are limited by technical and financial difficulties. These difficulties can be overcome by using model fluids, which have more feasible supercritical conditions and exhibit a lower critical pressure and temperature. Experimental research is normally used to determine the conditions under which model fluids represent supercritical fluids under steady-state conditions. A fluid-to-fluid scaling approach has been proposed to determine model fluids that can represent supercritical fluids in a transient state. This paper presents an application of fractional scale analysis to determine the simulation parameters for a depressurization test facility. Carbon dioxide (CO{sub 2}) and R134a gas were considered as the model fluids because their critical point conditions are more feasible than those of water. The similarities of water (prototype), CO{sub 2} (model) and R134a (model) for depressurization in a pressure vessel were analyzed. (author)

  4. Power Systems Development Facility Gasification Test Run TC09

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-09-30

    This report discusses Test Campaign TC09 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode of operation using a particulate control device (PCD). The Transport Gasifier was operated as a pressurized gasifier during TC09 in air- and oxygen-blown modes. Test Run TC09 was started on September 3, 2002, and completed on September 26, 2002. Both gasifier and PCD operations were stable during the test run, with a stable baseline pressure drop. The oxygen feed supply system worked well and the transition from air to oxygen was smooth. The gasifier temperature varied between 1,725 and 1,825 F at pressures from 125 to 270 psig. The gasifier operates at lower pressure during oxygen-blown mode due to the supply pressure of the oxygen system. In TC09, 414 hours of solid circulation and over 300 hours of coal feed were attained with almost 80 hours of pure oxygen feed.

  5. Power Systems Development Facility Gasification Test Run TC11

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2003-04-30

    This report discusses Test Campaign TC11 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode of operation using a particulate control device (PCD). Test run TC11 began on April 7, 2003, with startup of the main air compressor and the lighting of the gasifier start-up burner. The Transport Gasifier operated until April 18, 2003, when a gasifier upset forced the termination of the test run. Over the course of the entire test run, gasifier temperatures varied between 1,650 and 1,800 F at pressures from 160 to 200 psig during air-blown operations and around 135 psig during enriched-air operations. Due to a restriction in the oxygen-fed lower mixing zone (LMZ), the majority of the test run featured air-blown operations.

  6. Development of a test facility for analyzing supercritical fluid blowdown

    International Nuclear Information System (INIS)

    Roberto, Thiago D.; Alvim, Antonio C.M.

    2015-01-01

    The generation IV nuclear reactors under development mostly use supercritical fluids as the working fluid because higher temperatures improve the thermal efficiency. Supercritical fluids are used by modern nuclear power plants to achieve thermal efficiencies of around 45%. With water as the supercritical working fluid, these plants operate at a high temperature and pressure. However, experiments on supercritical water are limited by technical and financial difficulties. These difficulties can be overcome by using model fluids, which have more feasible supercritical conditions and exhibit a lower critical pressure and temperature. Experimental research is normally used to determine the conditions under which model fluids represent supercritical fluids under steady-state conditions. A fluid-to-fluid scaling approach has been proposed to determine model fluids that can represent supercritical fluids in a transient state. This paper presents an application of fractional scale analysis to determine the simulation parameters for a depressurization test facility. Carbon dioxide (CO 2 ) and R134a gas were considered as the model fluids because their critical point conditions are more feasible than those of water. The similarities of water (prototype), CO 2 (model) and R134a (model) for depressurization in a pressure vessel were analyzed. (author)

  7. Development of magnets for agricultural radiation processing facility at RRCAT

    International Nuclear Information System (INIS)

    Malik, R.; Sreeramulu, K.; Ruwali, K.

    2015-01-01

    A 10 MeV, 5 kW electron Linac based Agricultural Radiation Processing Facility is being set-up near DABH Vegetable and Fruit Market, Indore. In this paper the design and development of a set of solenoid and scanning magnets required for the Linac is presented. The solenoid magnets include small aperture (22 mm diameter) beam collimator magnet and other water cooled solenoid magnets of peak fields of 1200 Gauss and 500 Gauss to be placed around the Linac assembly between the RF couplers to improve beam transmission. The beam collimator magnet has been designed for an axial peak magnetic field of 410 Gauss and will be placed after the electron gun and before the Linac. The scanning magnet has been designed for maximum field strength of 436 Gauss for wider scanning of the electron beam. The cross-section of all the solenoid magnets were determined by computing the field distribution with the 2D magneto static POISSON code and 3D calculations were performed using OPERA 3D Code. The forces between the water cooled solenoids are also estimated since all the solenoid magnets are placed near to each other around the Linac assembly structure. The water cooled solenoids were made from hollow copper conductors and shielded around them with low carbon steel sheets. The magnet cores of collimators were manufactured from low carbon steel and coils from enameled copper wires. The scanning magnet core cross-section is of C-type, fabricated from 0.5 mm silicon steel laminations and coils from enameled copper wires. All the wound magnet coils were epoxy resin impregnated under vacuum and assembled with magnet cores. The magnetic field measurements of all the magnets were carried out using Hall probe. After field measurements, all the magnetic elements have been installed in the Linac assembly. The details of magnetic design, magnet development and the magnetic measurements will be discussed in this paper. (author)

  8. Power Systems Development Facility Gasification Test Campaign TC24

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2008-03-30

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This report summarizes the results of TC24, the first test campaign using a bituminous coal as the feedstock in the modified Transport Gasifier configuration. TC24 was conducted from February 16, 2008, through March 19, 2008. The PSDF gasification process operated for about 230 hours in air-blown gasification mode with about 225 tons of Utah bituminous coal feed. Operational challenges in gasifier operation were related to particle agglomeration, a large percentage of oversize coal particles, low overall gasifier solids collection efficiency, and refractory degradation in the gasifier solids collection unit. The carbon conversion and syngas heating values varied widely, with low values obtained during periods of low gasifier operating temperature. Despite the operating difficulties, several periods of steady state operation were achieved, which provided useful data for future testing. TC24 operation afforded the opportunity for testing of various types of technologies, including dry coal feeding with a developmental feeder, the Pressure Decoupled Advanced Coal (PDAC) feeder; evaluating a new hot gas filter element media configuration; and enhancing syngas cleanup with water-gas shift catalysts. During TC24, the PSDF site was also made available for testing of the National Energy Technology Laboratory's fuel cell module and Media Process Technology's hydrogen selective membrane.

  9. NST Quarterly - January 1997 issue

    International Nuclear Information System (INIS)

    1997-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in local heat shrinkable copolymer and electron beam technology for purification of flue gases. It announces an International Nuclear Conference themed ' a new era in nuclear science and technology - the challenge of the 21 century ' will be held in Kuala Lumpur, Malaysia from 29 to 30 Sept 1997

  10. Power Systems Development Facility Gasification Test Run TC08

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-06-30

    This report discusses Test Campaign TC08 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode using a particulate control device (PCD). The Transport Gasifier was operated as a pressurized gasifier in air- and oxygen-blown modes during TC08. Test Run TC08 was started on June 9, 2002 and completed on June 29. Both gasifier and PCD operations were stable during the test run with a stable baseline pressure drop. The oxygen feed supply system worked well and the transition from air to oxygen blown was smooth. The gasifier temperature was varied between 1,710 and 1,770 F at pressures from 125 to 240 psig. The gasifier operates at lower pressure during oxygen-blown mode due to the supply pressure of the oxygen system. In TC08, 476 hours of solid circulation and 364 hours of coal feed were attained with 153 hours of pure oxygen feed. The gasifier and PCD operations were stable in both enriched air and 100 percent oxygen blown modes. The oxygen concentration was slowly increased during the first transition to full oxygen-blown operations. Subsequent transitions from air to oxygen blown could be completed in less than 15 minutes. Oxygen-blown operations produced the highest synthesis gas heating value to date, with a projected synthesis gas heating value averaging 175 Btu/scf. Carbon conversions averaged 93 percent, slightly lower than carbon conversions achieved during air-blown gasification.

  11. Power Systems Development Facility Gasification Test Run TC07

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-04-05

    This report discusses Test Campaign TC07 of the Kellogg Brown & Root, Inc. (KBR) Transport Reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). The Transport Reactor was operated as a pressurized gasifier during TC07. Prior to TC07, the Transport Reactor was modified to allow operations as an oxygen-blown gasifier. Test Run TC07 was started on December 11, 2001, and the sand circulation tests (TC07A) were completed on December 14, 2001. The coal-feed tests (TC07B-D) were started on January 17, 2002 and completed on April 5, 2002. Due to operational difficulties with the reactor, the unit was taken offline several times. The reactor temperature was varied between 1,700 and 1,780 F at pressures from 200 to 240 psig. In TC07, 679 hours of solid circulation and 442 hours of coal feed, 398 hours with PRB coal and 44 hours with coal from the Calumet mine, and 33 hours of coke breeze feed were attained. Reactor operations were problematic due to instrumentation problems in the LMZ resulting in much higher than desired operating temperatures in the reactor. Both reactor and PCD operations were stable and the modifications to the lower part of the gasifier performed well while testing the gasifier with PRB coal feed.

  12. Silicon-on ceramic process. Silicon sheet growth and device development for the large-area silicon sheet and cell development tasks of the low-cost solar array project. Quarterly report No. 12, April 2, 1979-June 29, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, P.W.; Zook, J.D.; Heaps, J.D.; Grung, B.L.; Koepke, B.; Schuldt, S.B.

    1979-07-31

    The objective of this research program is to investigate the technical and economic feasibility of producing solar-cell-quality sheet silicon. We plan to do this by coating one surface of carbonized ceramic substrates with a thin layer of large-grain polycrystalline silicon from the melt. During the quarter, significant progress was demonstrated in several areas: (1) a 10-cm/sup 2/ cell having 9.9 percent conversion efficiency (AM1, AR) was fabricated; (2) the Honeywall-sponsored SCIM coating development succeeded in producing a 225-cm/sup 2/ layer of sheet silicon (18 inches x 2 inches); and (3) 100 ..mu..m-thick coatings at pull speed of 0.15 cm/sec wer$obta9ned, although apoproximately 50 percent of the layer exhibited dendritic growth. Other results and accomplishments during the quarter are reported in detail. (WHK)

  13. Facilities for radiotherapy with ion beams status and worldwide developments

    CERN Document Server

    Wolf, B H

    1999-01-01

    Forty-five years after the first ion beam therapy in Berkeley around 25,000 cancer patients worldwide have been treated successfully. Ion accelerators, designed for nuclear research, delivered most of this treatment. The first hospital-based facility started operation in 1998 at Loma Linda California, the first for heavier ions at Chiba, Japan in 1994 and the first commercially delivered facilities started operation in 1998 at Kashiwa, Japan. In 2000, the Harvard Medical Centre, Boston, US, will commence operation and several new facilities are planned or under construction worldwide, although none in Australia. This paper will discuss the physical and biological advantages of ion beams over x-rays and electrons. In the treatment of cancer patients ion beam therapy is especially suited for localised tumours in radiation sensitive areas like skull or spine. Heavier ions are also effective in anoxic tumour cells (found around the normally oxygenated cell population). An additional advantage of the heavier carbo...

  14. Developing a safety report for an existing conversion facility

    International Nuclear Information System (INIS)

    Carisse, Hess

    2013-01-01

    A review of the process used to meet the regulatory requirements for a Safety Report at an existing conversion facility is described. This paper will cover the establishment of the regulatory criteria, selection of appropriate methodologies, identification of events and modeling of credible events. Once established there is on-going maintenance to deal with design changes and the need for periodic reviews will also be discussed. Challenges in dealing with the various phases, including incorporation of historical licensing documents, and lessons learned are presented. Of specific interest is the failure of the selected methodology to deal with infrastructure issues. One aspect of lessons learned that will be explored is the lack of an available mechanism for sharing information with similar fuel cycle facilities which is compounded by the fact that there are a small number of fuel cycle facilities compared to nuclear power plants. Possible approaches to dealing with this issue are also discussed. (authors)

  15. Research and development activities of a neutron generator facility

    International Nuclear Information System (INIS)

    Darsono Sudjatmoko; Pramudita Anggraita; Sukarman Aminjoyo

    2000-01-01

    The neutron generator facility at YNRC is used for elemental analysis, nuclear data measurement and education. In nuclear data measurement the focus is on re-evaluating the existing scattered nuclear activation cross-section to obtain systematic data for nuclear reactions such as (n,p), (n,α), and (n,2n). In elemental analysis it is used for analyzing the Nitrogen (N), Phosphor (P) and Potassium (K) contents in chemical and natural fertilizers (compost), protein in rice, soybean, and corn and pollution level in rivers. The neutron generator is also used for education and training of BATAN staff and university students. The facility can also produce neutron generator components. (author)

  16. Summary on experimental facilities and future developments at SINQ

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, G.S. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-11-01

    With 13 experimental facilities under construction to become available during the first year of SINQ operation, a nearly complete suite of options for users will be made available to carry out research with neutrons at PSI. Three more facilities are under design and will come on line somewhat later. To complete the suite, three more specialized instruments are being evaluated. SINQ being a novel neutron source concept, significant scope for improvement is also seen on the source side. It is a major goal of PSI to exploit these opportunities and to make - among others - use of neutron instruments to carry out the necessary research. (author) 9 figs., 1 tab., 11 refs.

  17. Development of new irradiation facility for BWR safety research

    International Nuclear Information System (INIS)

    Okada, Yuji; Magome, Hirokatsu; Iida, Kazuhiro; Hanawa, Hiroshi; Ohmi, Masao

    2013-01-01

    In JAEA (Japan Atomic Energy Agency), about the irradiation embrittlement of the reactor pressure vessel and the stress corrosion cracking of reactor core composition apparatus concerning the long-term use of the light water reactor (BWR), in order to check the influence of the temperature, pressure, and water quality, etc on BWR condition. The water environmental control facility which performs irradiation assisted stress corrosion-cracking (IASCC) evaluation under BWR irradiation environment was fabricated in JMTR (Japan Materials Testing Reactor). This report is described the outline of manufacture of the water environmental control facility for doing an irradiation test using the saturation temperature capsule after JMTR re-operation. (author)

  18. Development of a EUV Test Facility at the Marshall Space Flight Center

    Science.gov (United States)

    West, Edward; Pavelitz, Steve; Kobayashi, Ken; Robinson, Brian; Cirtain, Johnathan; Gaskin, Jessica; Winebarger, Amy

    2011-01-01

    This paper will describe a new EUV test facility that is being developed at the Marshall Space Flight Center (MSFC) to test EUV telescopes. Two flight programs, HiC - high resolution coronal imager (sounding rocket) and SUVI - Solar Ultraviolet Imager (GOES-R), set the requirements for this new facility. This paper will discuss those requirements, the EUV source characteristics, the wavelength resolution that is expected and the vacuum chambers (Stray Light Facility, Xray Calibration Facility and the EUV test chamber) where this facility will be used.

  19. Development techniques of computerized maintenance management system for nuclear fuel cycle examination facilities

    International Nuclear Information System (INIS)

    Oh, Yon Woo; Kim, S. D.; Soong, W. S.; Kim, G. H.; Oh, W. H.; Kim, Y. G.

    2000-12-01

    Normal operation of the facility is one of the key factors in the accomplishments of research goals. As confirmed by a case study of the influence of the facility operation condition on the research results, emphasis should be put on the facility preserve management. Facilities should be maintained in solid operational condition and their malfunctions should be repaired as soon as possible. The purpose of this project is to make propositions on the development of the facility Preserve management system which is to maximize the efficiency of the budget execution, manpower organization and maintenance planning, and is to minimize the duration of the operational pause due to malfunctions with the least disbursement

  20. Development techniques of computerized maintenance management system for nuclear fuel cycle examination facilities

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Yon Woo; Kim, S. D.; Soong, W. S.; Kim, G. H.; Oh, W. H.; Kim, Y. G

    2000-12-01

    Normal operation of the facility is one of the key factors in the accomplishments of research goals. As confirmed by a case study of the influence of the facility operation condition on the research results, emphasis should be put on the facility preserve management. Facilities should be maintained in solid operational condition and their malfunctions should be repaired as soon as possible. The purpose of this project is to make propositions on the development of the facility Preserve management system which is to maximize the efficiency of the budget execution, manpower organization and maintenance planning, and is to minimize the duration of the operational pause due to malfunctions with the least disbursement.

  1. Development of a collinear laser spectrometer facility at VECC: First ...

    Indian Academy of Sciences (India)

    Md Sabir Ali

    2018-02-28

    Feb 28, 2018 ... and transported to the charge exchange cell using the ion sources, extractor and the beam-line magnets of the. ISOL facility. ... Collinear laser spectrometer; isotope separator online; charge exchange; ellipsoid reflector; photon counting. .... flow rate (∼≤5 l/min) is so adjusted that the temper- ature at the ...

  2. Development of a Commonwealth Radioactive Waste Management Facility in Australia

    International Nuclear Information System (INIS)

    Hesterman, R.

    2006-01-01

    Full text: The Australian Government has commenced a process to build a Commonwealth Radioactive Waste Management Facility in the Northern Territory for management of radioactive wastes produced by Australian Government agencies. The Government is committed to safely managing its relatively small volume of low level radioactive waste (approximately 3800 cubic metres) and even smaller volume of intermediate level waste (around 400 cubic metres) that have been generated since the early 1950s from the research, medical and industrial use of radioactive materials. Australia has no high level radioactive waste as it does not have any nuclear power reactors. Australian states and territories are responsible for the safe and secure management of low level and intermediate level waste generated within their jurisdictions. They have jointly generated approximately 200 cubic metres of low level radioactive waste and under 100 cubic metres of intermediate level for the same period. In July 2004, the Prime Minister announced that the Australian Government would examine the suitability of Commonwealth land holdings, both onshore and offshore, for establishing the Facility. An initial assessment of offshore territories by the Department of Education, Science and Training (DEST) did not find any sufficiently suitable sites for hosting the Facility. This was due to the low elevation of most territories, inadequate infrastructure and incompatibility with existing land uses. In July 2005, Dr Nelson, then the Minister for Education, Science and Training, announced that three Department of Defence properties in the Northern Territory would be investigated for siting the Facility. The three properties are Fishers Ridge, about 43 kilometres southeast of Katherine; Harts Range, 100 kilometres directly northeast of Alice Springs; and Mt Everard, about 27 kilometres directly northwest of Alice Springs. In addition, the Commonwealth Radioactive Waste Management Act 2005, enacted in December

  3. Development of a distributed control system for the JAERI tandem accelerator facility

    International Nuclear Information System (INIS)

    Hanashima, Susumu

    2005-01-01

    In the JAERI tandem accelerator facility, we are building accelerator complex aiming generation and acceleration of radio nuclear beam. Several accelerators, ion sources and a charge breeder are installed in the facility. We are developing a distributed control system enabling smooth operation of the facility. We report basic concepts of the control system in this article. We also describe about a control hardware using plastic optical fiber, which is developed for the control system. (author)

  4. Power Systems Development Facility Gasification Test Run TC10

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-12-30

    This report discusses Test Campaign TC10 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode of operation using a particulate control device (PCD). The Transport Gasifier was operated as a pressurized gasifier during TC10 in air- (mainly for transitions and problematic operations) and oxygen-blown mode. Test Run TC10 was started on November 16, 2002, and completed on December 18, 2002. During oxygen-blown operations, gasifier temperatures varied between 1,675 and 1,825 F at pressures from 150 to 180 psig. After initial adjustments were made to reduce the feed rate, operations with the new fluidized coal feeder were stable with about half of the total coalfeed rate through the new feeder. However, the new fluidized-bed coal feeder proved to be difficult to control at low feed rates. Later the coal mills and original coal feeder experienced difficulties due to a high moisture content in the coal from heavy rains. Additional operational difficulties were experienced when several of the pressure sensing taps in the gasifier plugged. As the run progressed, modifications to the mills (to address processing the wet coal) resulted in a much larger feed size. This eventually resulted in the accumulation of large particles in the circulating solids causing operational instabilities in the standpipe and loop seal. Despite problems with the coal mills, coal feeder, pressure tap nozzles and the standpipe, the gasifier did experience short periods of stability during oxygenblown operations. During these periods, the syngas quality was high. During TC10, the gasifier gasified over 609 tons of Powder River Basin subbituminous coal and

  5. Spatial development of sports facilities in Hungarian cities of county rank

    Directory of Open Access Journals (Sweden)

    Kozma Gábor

    2016-03-01

    Full Text Available Nowadays more and more attention is devoted to the spatial development of the location of sports facilities within cities. The main aim of our paper is to observe the most important spatial characteristics of their development in Hungarian cities of county rank. In these cities three main periods of development of sports facilities can be observed. Larger sports facilities were constructed especially on the edge of cities or in the suburbs, while in the case of smaller facilities a bigger role was played by locations within the city boundaries. As regards the factors influencing the location of sports facilities, the most important role was played by the location of available land areas, besides accessibility and from the mid-1960s links to existing facilities can be mentioned as well.

  6. The development of the advanced cryogenic radiometer facility at NRC

    Science.gov (United States)

    Gamouras, A.; Todd, A. D. W.; Côté, É.; Rowell, N. L.

    2018-02-01

    The National Research Council (NRC) of Canada has established a next generation facility for the primary realization of optical radiant power. The main feature of this facility is a new cryogenic electrical substitution radiometer with a closed-cycle helium cryocooler. A monochromator-based approach allows for detector calibrations at any desired wavelength. A custom-designed motion apparatus includes two transfer standard radiometer mounting ports which has increased our measurement capability by allowing the calibration of two photodetectors in one measurement cycle. Measurement uncertainties have been improved through several upgrades, including newly designed and constructed transimpedance amplifiers for the transfer standard radiometers, and a higher power broadband light source. The most significant improvements in uncertainty arise from the enhanced characteristics of the new cryogenic radiometer including its higher cavity absorptance and reduced non-equivalence effects.

  7. Diagnostic development at LLNL for the National Ignition Facility

    International Nuclear Information System (INIS)

    Sangster, T.C.; Cable, M.D.; Kilkenny, J.D.; Lerche, R.A.

    1996-01-01

    ICF implosions at the NIF will produce core plasma temperatures in excess of 10-keV and densities of order 100 g/cm 3 . Properties of these plasmas can be measured using a variety of optical, x-ray and nuclear techniques similar to those now in use at facilities such as Nova and Omega. Some of these techniques will be directly applicable on NIF while others, particularly the nuclear-based techniques, will change significantly

  8. Recent developments at the ISOL facility of GSI Darmstadt

    CERN Document Server

    Roeckl, E; Burkard, K; Döring, J; Grawe, H; Hüller, W; Kirchner, R; Mazzocchi, C; Mukha, I; Plettner, C

    2003-01-01

    The research programme pursued at the ISOL facility of GSI Darmstadt focuses on the study of decay properties of nuclei along the N congruent with Z line between the double shell closures at sup 5 sup 6 Ni and sup 1 sup 0 sup 0 Sn. In this report, the major scientific achievements obtained in the past two years are reviewed, with particular emphasis being put on the detection techniques.

  9. Engineering development of advanced coal-fired low-emissions boiler systems. Quarterly report, October 1994--December 1994; January 1995--March 1995; April 1995--June 1995; July 1995--September 1995; October 1995--December 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This report covers five quarters of work on the engineering development of a coal-fired low -emissions boiler systems. Contents include summaries of activities and key accomplishments for the following: project management; NO{sub x} subsystem; SO{sub 2}/particulate/air toxics/solid by-product subsystems; controls and sensors subsystems; boiler subsystem; and balance of plant subsystem.

  10. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  11. Development of construction specifications to attain clean rooms for the NOVA laser facility

    International Nuclear Information System (INIS)

    Benedix, C.P.

    1980-02-01

    This paper describes the process of defining technical requirements for a major Department of Energy Research and Development Facility and subsequent development of construction specifications for the clean spaces in that facility. The organizational interactions between technical client, Engineering and Construction elements are described. The importance of an interdisciplinary team approach is stressed. A brief description of the SHIVA Laser and NOVA Laser Clean Spaces is included to indicate the scope of the facility undertaking. A number of potential pitfalls are discussed that may be helpful to designers of new facilities

  12. Occupants' satisfaction on building maintenance of government quarters

    Science.gov (United States)

    Ismail, Nur'Ain; Ali, Siti Noor Asmiza Md; Othman, Nor A'aini; Jaffar, Nooraidawati

    2017-10-01

    The satisfaction level of occupants toward the maintenance is very important to know the occupants comfortable with maintenance that was provided at the government quarters. The objective of the research is to determine the level of occupants satisfaction perceived of the maintenance in government quarter and also the level of quality of the maintenance of the government quarters. Data have been collected by using questionnaire in order to achieve the objective of the research. The questionnaires distributed among the occupants government quarters at Hospital Kota Bharu Kelantan. In the end of the research, the result are expected that to show the results on this satisfaction level of the occupants toward the maintenance at government quarters can be solve and the occupants can live more comfortable and get the good quality for maintenance and facilities in their houses.

  13. EMSL Quarterly Highlights Report: 1st Quarter, FY08

    Energy Technology Data Exchange (ETDEWEB)

    Showalter, Mary Ann

    2008-01-28

    The EMSL Quarterly Highlights Report covers the science, staff and user recognition, and publication activities that occurred during the 1st quarter (October 2007 - December 2007) of Fiscal Year 2008.

  14. EMSL Quarterly Highlights Report: 1st Quarter, Fiscal Year 2009

    Energy Technology Data Exchange (ETDEWEB)

    Showalter, Mary Ann; Kathmann, Loel E.; Manke, Kristin L.

    2009-02-02

    The EMSL Quarterly Highlights Report covers the science, staff and user recognition, and publication activities that occurred during the 1st quarter (October 2008 - December 2008) of Fiscal Year 2009.

  15. EMSL Quarterly Highlights Report: FY 2008, 3rd Quarter

    Energy Technology Data Exchange (ETDEWEB)

    Showalter, Mary Ann

    2008-09-16

    The EMSL Quarterly Highlights Report covers the science, staff and user recognition, and publication activities that occurred during the 1st quarter (October 2007 - December 2007) of Fiscal Year 2008.

  16. Establishing a cultural quarter in Abu Dhabi, UAE

    OpenAIRE

    Al Hamed, Hamed

    2013-01-01

    The main argument driving the thesis; namely the fact that the literature is treating cultural quarter development as mainly originating from the supply side with limited attention to the demand side (e.g., consumers’/visitors’ preferences and tastes for prospective developments in the cultural scene). Thus, the analysis argues that more attention should be placed upon cultural quarter establishment, as opposed to cultural quarter production. For this purpose, the thesis engages into a quest ...

  17. Quarterly environmental radiological survey summary - second quarter 1997 100, 200, 300, and 600 areas

    International Nuclear Information System (INIS)

    McKinney, S.M.; Marks, B.M.

    1997-01-01

    This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The Second Quarter 1997 survey results and the status of actions required are summarized below: All of the routine environmental radiological surveys scheduled during April, May, and June 1997, were performed as planned with the exception of UN-216-E-9. This site was not surveyed as stabilization activities were in progress. The sites scheduled for the Environmental Restorations Contractor (ERC) team were switched with those identified for the third quarter as there was a conflict with vegetation management activities

  18. Environmental Restoration Operations: Consolidated Quarterly Report January -March 2017

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-07-01

    This Environmental Restoration Operations (ER) Consolidated Quarterly Report (ER Quarterly Report) provides the status of ongoing corrective action activities being implemented at Sandia National Laboratories, New Mexico (SNL/NM) during the January, February, and March 2017 quarterly reporting period. Table I-1 lists the Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) identified for corrective action at SNL/NM. Sections I.2.1 and I.2.2 summarize the work completed during this quarter. Section I.2.1 summarizes the quarterly activities at sites undergoing corrective action field activities. Field activities are conducted at the three groundwater AOCs (Burn Site Groundwater [BSG AOC], Technical Area [TA]-V Groundwater [TAVG AOC], and Tijeras Arroyo Groundwater [TAG AOC]). Section I.2.2 summarizes quarterly activities at sites where the New Mexico Environment Department (NMED) Hazardous Waste Bureau (HWB) issued a certificate of completion and the sites are in the corrective action complete (CAC) regulatory process. Currently, SWMUs 8 and 58, 68, 149, 154, and 502 are in the CAC regulatory process. Corrective action activities are deferred at the Long Sled Track (SWMU 83), the Gun Facilities (SWMU 84), and the Short Sled Track (SWMU 240) because these three sites are active mission facilities. These three active mission sites are located in TA-III. This Sandia National Laboratories, New Mexico Environmental Restoration Operations (ER) Consolidated Quarterly Report (ER Quarterly Report) fulfills all quarterly reporting requirements set forth in the Resource Conservation and Recovery Act Facility Operating Permit and the Compliance Order on Consent.

  19. South African Crime Quarterly

    African Journals Online (AJOL)

    South African Crime Quarterly is an inter-disciplinary peer-reviewed journal that promotes professional discourse and the publication of research on the subjects of crime, criminal justice, crime prevention, and related matters including state and non-state responses to crime and violence. South Africa is the primary focus for ...

  20. English Leadership Quarterly, 1993.

    Science.gov (United States)

    Strickland, James, Ed.

    1993-01-01

    These four issues of the English Leadership Quarterly represent those published during 1993. Articles in number 1 deal with parent involvement and participation, and include: "Opening the Doors to Open House" (Jolene A. Borgese); "Parent/Teacher Conferences: Avoiding the Collision Course" (Robert Perrin); "Expanding Human…

  1. Quarterly fiscal policy

    NARCIS (Netherlands)

    Kendrick, D.A.; Amman, H.M.

    2014-01-01

    Monetary policy is altered once a month. Fiscal policy is altered once a year. As a potential improvement this article examines the use of feedback control rules for fiscal policy that is altered quarterly. Following the work of Blinder and Orszag, modifications are discussed in Congressional

  2. Development of an auditable safety analysis in support of a radiological facility classification

    International Nuclear Information System (INIS)

    Kinney, M.D.; Young, B.

    1995-01-01

    In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23

  3. Applied Meteorology Unit (AMU) Quarterly Report - Fourth Quarter FY-09

    Science.gov (United States)

    Bauman, William; Crawford, Winifred; Barrett, Joe; Watson, Leela; Wheeler, Mark

    2009-01-01

    This report summarizes the Applied Meteorology Unit (AMU) activities for the fourth quarter of Fiscal Year 2009 (July - September 2009). Tasks reports include: (1) Peak Wind Tool for User Launch Commit Criteria (LCC), (2) Objective Lightning Probability Tool. Phase III, (3) Peak Wind Tool for General Forecasting. Phase II, (4) Update and Maintain Advanced Regional Prediction System (ARPS) Data Analysis System (ADAS), (5) Verify MesoNAM Performance (6) develop a Graphical User Interface to update selected parameters for the Hybrid Single-Particle Lagrangian Integrated Trajectory (HYSPLlT)

  4. The Development of the Code Safety Valve Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chang Hyun; Kim, Young Ae; Park, Jong Woon [Korea Hydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of)

    2007-07-01

    The Pressurizer Safety Valves (PSV) in Pressurized Water Reactors (PWRs) are required to provide the overpressure protection for the Reactor Coolant System (RCS) during the overpressure transients. According to the ASME OM code, all safety valves should be tested every 5 years with the acceptance tolerance of 1%. If one valve failed to meet this criterion, other two additional valves should be tested and if these valves don't meet the requirement, all valves should be tested. These frequent tests may make the valves decrepit and become a cause of leak. Therefore, increase of the acceptance tolerance is vital for the safe operation of the plant. In the United States, the acceptance tolerances are enlarged up to about 3% in most plants. This requires re-analysis of relevant accidents in FSAR. Also, the technical background data for the valve pop-up characteristics and the loop seal dynamics (if the plant has the loop seal in the upstream of PSV) are needed for the new safety analysis. Korea Hydro and Nuclear Power Company (KHNP) plans to build the PSV test facility for the purpose of providing the background data. This paper describes the preliminary design of the facility and studies on the system dynamics using GOTHIC-7.2a code to verify the pressure vessel capacities and to find the best operating condition.

  5. Development of the Jyväskylä microbeam facility

    Science.gov (United States)

    Norarat, Rattanaporn; Sajavaara, Timo; Laitinen, Mikko; Heikkinen, Pauli; Ranttila, Kimmo; Ylikorkala, Kari; Hänninen, Väinö; Rossi, Mikko; Jones, Pete; Marjomäki, Varpu; Gilbert, Leona; Whitlow, Harry J.

    2012-02-01

    A new microbeam facility is being constructed at the 1.7 MV Pelletron Accelerator in Jyväskylä. The facility is designed for easy upgrading and incorporates a number of innovative features. Initially, it is based on a Heidelberg doublet with a design capability of a 3 × 5 μm beamspot at PIXE intensities and later upgraded to nanobeam performance. A thermal-expansion compensated rigid frame mounted on a mechanically isolated floor section is used to support the ion optical components. A compact-post focusing electrostatic deflector is used for high linearity beam scanning. This together with a novel time-stamped data collection (TDC) allows dynamic effects in IBIC, fluorescence bleaching to be studied as well as facilitating multi-resolution image support for low-fluence imaging of cells. The target chamber is fitted with a novel low-cost large working distance optical microscope, extremely compact large solid angle photon detectors as well as conventional secondary electron, PIXE and Scanning Transmission Ion Microscopy (STIM) detectors.

  6. Development of molten carbonate fuel cell power plant. Quarterly technical progress report, May 1-July 31, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, J. R.

    1980-09-04

    The major objective of this program for development of a molten carbonate fuel cell power plant is to establish and demonstrate readiness for fabrication and test of full-scale prototype stacks. This will be accomplished by a heavy emphasis upon resolution of remaining technology problems, including materials, processes and contaminant effects research, development and testing of cell components to 10,000 hours endurance life and scaleup of laboratory hardware to commercial size. A detailed design for a prototype stack will be defined and a tenth-size of full-scale cells will be tested. Component and manufacturing processes will be developed based upon commercial cost goals. Coal-fired utility central station and industrial cogeneration power plant requirements will be defined and plant options evaluated, leading to selection of a single reference design. Cell and stack design and development will be guided by requirements based upon the reference plant design. The specific program objectives derived from the contract work statement are as follows: (1) to define a reference power plant design for a coal-fired molten carbonate power plant; (2) to develop and verify cell and stack design based upon the requirements of the reference power plant design; (3) to establish and demonstrate readiness to fabricate and test full-length stacks of full-scale cells, hereafter called prototype stacks; and (4) to quantify contaminant effects and establish a program to verify performance of molten carbonate fuel cells operating on products of coal gasification. Progress is reported.

  7. Development, characterization and evaluation of materials for open cycle MHD. Quarterly report for the period ending June 1978

    Energy Technology Data Exchange (ETDEWEB)

    Bates, J.L.; Marchant, D.D.; Daniel, J.L.

    1978-10-01

    The objectives of this program are directed toward the development and characterization of high temperature ceramics for open-cycle, coal-fired MHD power generators. The current activities are directed to electrode and insulator materials, and include (1) determination of the effects of alkali seed on the behavior of ceramics in a dc electric field; (2) development and testing of improved high temperature ceramic electrodes and insulators with controlled composition, microstructure, and properties; and (3) characterization and evaluation of materials utilized in channels being tested for MHD power generator development. Research is reported on (1) evaluation of metal electrodes from 250 hour MHD test, (2) characterization and properties of USSR MgO insulating wall material, (3) thermal diffusivity/thermal conductivity of electrode and insulator materials, (4) coprecipitation of ceramic powders, (5) properties of yttria chromites, and (6) rare earth hafnates. (WHK)

  8. Metallurgical Laboratory (HWMF) Groundwater Monitoring Report, Fourth Quarter 1994

    International Nuclear Information System (INIS)

    Chase, J.A.

    1995-03-01

    Groundwater flow direction and rate in the M-Area Aquifer Zone were similar to previous quarters. Conditions affecting determination of groundwater flow directions and rates in the Upper Lost Lake Aquifer Zone, Lower Lost Lake Aquifer Zone, and the Middle Sand Aquifer Zone of the Crouch Branch Confining Units were also similar to previous quarters. During second quarter 1994, SRS received South Carolina Department of Health and Environmental Control approval for constructing five point-of-compliance wells and two plume definition wells near the Met Lab Hazardous Waste Management Facility. This project began in July 1994 and is complete; however, analytical data from these wells are not yet available

  9. Thorium utilization program. Quarterly progress report for the period ending February 28, 1977. [Fuel element crushing, burning; particle classification; solvent extraction; dry solids handling; plant management; HET fuel shipping; HTGR recycle demonstration facility

    Energy Technology Data Exchange (ETDEWEB)

    1977-03-01

    General Atomic Thorium Utilization Program activities progressed on schedule during the quarter, with continuation of the head-end reprocessing equipment testing program. Individual testing of the tertiary, oversize crushers and the screener was completed. Preparation of the equipment for testing as a system is under way. Tests on the tertiary crusher revealed no operating problems. No material holdup areas or bypass of the crushing cavity were detected. The initial issue of a functional level diagram for the Fuel Element Size Reduction System has been prepared for preliminary review. Heat transfer coefficients were calculated from data obtained in six 0.40-m primary burner heatup runs. Six runs were made on the 0.20-m primary burner. Other significant 0.20-m burner work included fabrication and initial testing of an electrical resistance probe bed level sensor and preliminary heat transfer design calculations for determining the cooling requirements to maintain the recycling fines cyclone exit temperature at approximately 500/sup 0/C. The conceptual design of the engineering-scale dissolver-centrifuge for incorporation into the head-end line was completed. Three solvent extraction feed adjustment runs were completed. Two of the runs were representative of the continuous intercycle concentration step. The other run was a continuous operation which utilized leacher product as feed. Progress with dry solids handling component and system testing continues. Efforts were focused on completion of the HET fuel shipping conceptual design report, development of detailed costs, and identification of all system interfaces. The Reprocessing Flowsheet Review and Materials Balance Study of reprocessing head-end and off-gas treatment systems is in technical review.

  10. Preliminary analysis of West Valley Waste Removal System equipment development and mock demonstration facilities

    International Nuclear Information System (INIS)

    Janicek, G.P.

    1981-06-01

    This report defines seven areas requiring further investigation to develop and demonstrate a safe and viable West Valley Waste Removal System. These areas of endeavor are discussed in terms of their minimum facility requirements. It is concluded that utilizing separated specific facilities at different points in time is of a greater advantage than an exact duplication of the West Valley tanks. Savannah River Plant's full-scale, full-circle and half-circle tanks, and their twelfth scale model tank would all be useful to varying degrees but would require modifications. Hanford's proposed full-size mock tank would be useful, but is not seriously considered because its construction may not coincide with West Valley needs. Costs of modifying existing facilities and/or constructing new facilities are assessed in terms of their benefit to the equipment development and mock demonstration. Six facilities were identified for further analysis which would benefit development of waste removal equipment

  11. Building Blocks of Contemporary HRD Research: A Citation Analysis on Human Resource Development Quarterly between 2007 and 2013

    Science.gov (United States)

    Mehdiabadi, Amir Hedayati; Seo, Gaeun; Huang, Wenhao David; Han, Seung-hyun Caleb

    2017-01-01

    Human resource development is known to encapsulate a collection of social science disciplines including communications, psychology, and economics. Since these and other similar areas are the cornerstones of HRD, the changing nature of HRD demands constant reflections on the value and building blocks of contemporary HRD inquiries. This article…

  12. Development of a plasma ion source for next-generation facilities

    International Nuclear Information System (INIS)

    Cheikh Mhamed, M.; Lau, C.; Essabaa, S.; Arianer, J.; Bajeat, O.; Croizet, H.; Ducourtieux, M.; Lefort, H.

    2006-01-01

    The ionization by radial electron neat adaptation (IRENA) ion source has been designed to operate under unprecedented radiation conditions generated by next-generation facilities such as SPIRAL-2 and EURISOL. The design and development of this next-generation-facility ion source will be presented and discussed

  13. Analysis of Early Childhood Development (ECD) facilities within the city of Cape Town

    CSIR Research Space (South Africa)

    Mokgalaka, H

    2011-10-01

    Full Text Available The accessibility mapping of Early Childhood Development (ECD) facilities within the City of Cape Town is part of a larger accessibility audit and facility planning exercise for a range of community social services undertaken by CSIR for the City...

  14. Professional Development through Organizational Assessment: Using APPA's Facilities Management Evaluation Program

    Science.gov (United States)

    Medlin, E. Lander; Judd, R. Holly

    2013-01-01

    APPA's Facilities Management Evaluation Program (FMEP) provides an integrated system to optimize organizational performance. The criteria for evaluation not only provide a tool for organizational continuous improvement, they serve as a compelling leadership development tool essential for today's facilities management professional. The senior…

  15. Design and Development of a New Facility for Teaching and Research in Clinical Anatomy

    Science.gov (United States)

    Greene, John Richard T.

    2009-01-01

    This article discusses factors in the design, commissioning, project management, and intellectual property protection of developments within a new clinical anatomy facility in the United Kingdom. The project was aimed at creating cost-effective facilities that would address widespread concerns over anatomy teaching, and support other activities…

  16. The UNISOR facility: recent developments and future directions

    International Nuclear Information System (INIS)

    Spejewski, E.M.; Mlekodaj, R.L.

    1980-01-01

    UNISOR is a consortium formed in the early 1970's to place an isotope separator on-line to the Oak Ridge Isochronous Cyclotron (ORIC). The heavy-ion beams available at ORIC were recognized as an excellent means to produce nuclei far from β-stability, predominantly via the (HI, xn) and (HI, pxn) reactions. Mass separation of the products of these reactions then could produce radioactive sources for a single A-chain for nuclear spectroscopy in a time scale suitable for the short half lives involved. The initial on-line experiments were carried out in September 1972 when Ag isotopes were detected. Improvements in the number of elements available for study, in source strengths and in detection systems have been significant since that time. The authors give a detailed description of the UNISOR facility. (Auth.)

  17. Advanced Turbine Systems (ATS) program conceptual design and product development. Quarterly progress report, December 1, 1995--February 29, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    This report describes the overall program status of the General Electric Advanced Gas Turbine Development program, and reports progress on three main task areas. The program is focused on two specific products: (1) a 70-MW class industrial gas turbine based on the GE90 core technology, utilizing a new air cooling methodology; and (2) a 200-MW class utility gas turbine based on an advanced GE heavy-duty machine, utilizing advanced cooling and enhancement in component efficiency. The emphasis for the industrial system is placed on cycle design and low emission combustion. For the utility system, the focus is on developing a technology base for advanced turbine cooling while achieving low emission combustion. The three tasks included in this progress report are on: conversion to a coal-fueled advanced turbine system, integrated program plan, and design and test of critical components. 13 figs., 1 tab.

  18. 3-D turbulent particle dispersion submodel development. Quarterly progress report No. 1, 5 April--5 July 1991

    Energy Technology Data Exchange (ETDEWEB)

    Smith, P.J.

    1991-12-31

    The lack of a mathematical description of the interactions of fluid turbulence with other physics-chemical processes is a major obstacle in modeling many industrial program. Turbulent two-phase flow is a phenomenon that is of significant practical importance to coal combustion as well as other disciplines. The interactions of fluid turbulence with the particulate phase has yet to be accurately and efficiently modeled for these industrial applications. On 15 May 1991 work was initiated to cover four major tasks toward the development of a computational submodel for turbulent particle dispersion that would be applicable to coal combustion simulations. Those four tasks are: 1. A critical evaluation of the 2-D Lagrangian particle dispersion submodel, 2. Development of a 3-D submodel for turbulent particle dispersion, 3. Evaluation of the 3-D submodel for turbulent particle dispersion, 4.Exploration of extensions of the Lagrangian dispersion theory to other applications including chemistry-turbulence interactions.

  19. Design and development of a continuously variable ratio transmission for an automotive vehicle. Phase IV. Quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-05-31

    Progress in the design and development of a continuously variable ratio transmission for an automotive vehicle is reported. The Major automotive hydromechanical transmission development problem continues to be the reduction of hydrostatic noise and the project plan, therefore, concentrated on the new hydrostatic module. The potential for achieving acceptably low noise levels in the second generation hydromechanical transmission is to be assessed by comparing the noise levels of the hydrostatic modules for the first and second generation transmissions. A set of twelve test points was selected comprising of road load steady state and wide-open-throttle acceleration at 10, 20, 30, 40, 50 and 60 mph. The module operating conditions for the two transmissions at each of these twelve points were calculated. Baseline noise data was measured on the first generation module. The results are given testing of co-axial hydrostatic module for second generation hydromechanical transmission will be emphasized. (LCL)

  20. Development of a solid absorption process for removal of sulfur from fuel gas. Second quarterly technical report

    Energy Technology Data Exchange (ETDEWEB)

    Stegen, G.E.

    1980-05-01

    Progress on development of the Solid Supported Molten Salt (SSMS) Process is reported. Absorption and regeneration reaction rate data were obtained using a gravimetric technique. Durability and salt impregnation tests were also performed on a number of commercially available and custom fabricated ceramic samples. Results to date indicate that lithium aluminate, magnesium oxide, and zirconium oxide may all be suitable ceramic support materials. Gravimetric reaction rate data has been developed which gives an estimate of reaction rates expected with the solid supported molten salt sorbent. Soaking the ceramic in a bath of the molten salt has been shown to be effective in filling the pores with salt. With some materials it is necessary to draw a vacuum on the bath during soaking in order to remove trapped gases.

  1. High resolution, low cost solar cell contact development. Quarterly technical progress and schedule report, September 28, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Mardesich, N.

    1980-01-01

    The scope of the contract covers the development and evaluation of forming solar cell collector grid contacts by the MIDFILM process. This is a proprietary process developed by the Ferro Corporation which is a subcontractor for the program. The MIDFILM process attains line resolution characteristics of photoresist methods with processing related to screen printing. The surface to be processed is first coated with a thin layer of photoresist material. Upon exposure to ultraviolet light through a suitable mask, the resist in the non-pattern area cross-links and becomes hard. The unexposed pattern areas remain tacky. The conductor material is applied in the form of a dry mixture of metal and frit particles which adhere to the tacky pattern area. The assemblage is then fired to ash the photopolymer and sinter the fritted conductor powder. Effort was concentrated during this period on the establishment, optimization and identification of problem areas of the MIDFILM process. Progress is reported. (WHK)

  2. Process development for automated solar cell and module production. Task 4. Automated array assembly. Quarterly report No. 1

    Energy Technology Data Exchange (ETDEWEB)

    Hagerty, J. J.

    1980-10-15

    Work has been divided into five phases. The first phase is to modify existing hardware and controlling computer software to: (1) improve cell-to-cell placement accuracy, (2) improve the solder joint while reducing the amount of solder and flux smear on the cell's surface, and (3) reduce the system cycle time to 10 seconds. The second phase involves expanding the existing system's capabilities to be able to reject broken cells and make post-solder electrical tests. Phase 3 involves developing new hardware to allow for the automated encapsulation of solar modules. This involves three discrete pieces of hardware: (1) a vacuum platen end effector for the robot which allows it to pick up the 1' x 4' array of 35 inter-connected cells. With this, it can also pick up the cover glass and completed module, (2) a lamination preparation station which cuts the various encapsulation components from roll storage and positions them for encapsulation, and (3) an automated encapsulation chamber which interfaces with the above two and applies the heat and vacuum to cure the encapsulants. Phase 4 involves the final assembly of the encapsulated array into a framed, edge-sealed module completed for installation. For this we are using MBA's Glass Reinforced Concrete (GRC) in panels such as those developed by MBA for JPL under contract No. 955281. The GRC panel plays the multiple role of edge frame, substrate and mounting structure. An automated method of applying the edge seal will also be developed. The final phase (5) is the fabrication of six 1' x 4' electrically active solar modules using the above developed equipment. Progress is reported. (WHK)

  3. Development program for a 200 kW, CW gyrotron. Quarterly report No. 16, April-June 1983

    Energy Technology Data Exchange (ETDEWEB)

    DeHope, W.J.; Ferguson, P.E.; Hart, S.L.; Matranga, V.A.; Sandoval, J.J.; Schmitt, M.J.; Tancredi, J.J.

    1983-01-01

    The objective of this program is the design and development of a millimeter-wave device to produce 200 kW of continuous wave power at 60 GHz. The device, a gyrotron oscillator, will be compatible with power delivery to an electron-cyclotron heated plasma. Smooth control of rf power over a 17 dB range is required, and the device should be capable of operation into a severely time-varying load mismatch. Progress is presented in the testing, analyses and understanding of S/N 1B behavior and in preparing S/N 3 for test in the coming report period.

  4. Instrumentation and process control development for in situ coal gasification. Fourth quarterly report, September--November 1975

    Energy Technology Data Exchange (ETDEWEB)

    Northrop, D.A. (ed.)

    1976-01-01

    The instrumentation effort for Phases 2 and 3 of the Second Hanna In Situ Coal Gasification Experiment was fielded and background data obtained prior to the initiation of Phase 2 on November 25, 1975. A total of over 600 channels of instrumentation in 15 instrumentation wells and two surface arrays was fielded for the instrumentation techniques under evaluation. The feasibility of the passive acoustic technique to locate the source of process-related noises has been demonstrated; its utility is presently hampered by the inexact definition of signal arrivals and the lack of automated signal monitoring and analysis systems. A revised mathematical model for the electrical techniques has been developed which demonstrates the potential for remote monitoring. (auth)

  5. Development of high efficiency (14%) solar cell array module. Third quarterly report, July 15, 1979-November 15, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Iles, P.A.; Khemthong, S.; Olah, S.; Sampson, W.J.; Ling, K.S.

    1980-01-01

    Most effort was concentrated on development of procedures to provide large area (3'' diameter) high efficiency (approx. 15.5% AM1, 28/sup 0/C) P/N solar cells. These efficiencies had been obtained for 2 x 2 cm area cells, but tests showed that the problem was not reduced silicon quality near the edges of the larger slices. The problems were in optimizing the back-surface field (BSF) process, and its possible interaction with the shallow P+ layer formation. Towards the end of this reporting period a promising process sequence had been identified and is being tested. The module design has been finalized. One hundred and twenty (120) cells will be connected eight (8) in parallel and fifteen (15) in series. The designs and tooling phases have been completed and are awaiting completion of the cells.

  6. Development program for a 200 kW, cw gyrotron. Quarterly report No. 11, January-March 1982

    International Nuclear Information System (INIS)

    Tancredi, J.J.; Caplan, M.; Sandoval, J.J.; Matranga, V.A.

    1982-01-01

    The objective of this program is the design and development of a millimeter wave device to produce 200 kW of continuous-wave power at 60 GHz. The device, a gyrotron oscillator, will be compatible with power delivery to an electron-cyclotron plasma. Smooth control of RF power output over a 17 dB range is required, and the device should be capable of operation into a severe time-varying load mismatch. During this report period, the beam instability problem which plagued S/N 1 testing was evaluated in more detail. Separate tests were conducted on the gun tester and the lossy drift section, as well as both of these combined, and the results were compared to gyrotron tests on S/N 1. The instability problem now appears to be associated with RF leakage from the cavity

  7. Develop silicone encapsulation systems for terrestrial silicon solar arrays. First quarterly progress report, February 15, 1978--June 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-07-10

    This study is directed toward the development of a cost effective encapsulation system for photovoltaic modules using silicone based materials. This is a cooperative effort between Dow Corning, the major supplier of silicones and silicone intermediates, and Spectrolab a leading photovoltaic array manufacturer. The total contract effort has been divided into four tasks: technology review, generation of screening concepts, assessment of encapsulation concepts, and evaluation of encapsulation concepts. A review of technology pertinent to the use and weatherability of silicone based materials and a plan for screening encapsulation concepts are presented. The technology review covered: the performance of clear silicones in weathering and stress environments, photovoltaic industry experience with silicone materials used in photovoltaic systems, and silicones used in the protection of electronic devices.

  8. Baseline Gas Turbine Development Program. Twenty-third combined quarterly progress report, May 1, 1978--January 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Pampreen, R C; Wagner, C E [comps.

    1978-12-31

    Progress is reported for a program whose goals are to demonstrate an experimental Upgraded gas turbine-powered automobile which meets the 1978 Federal Emissions Standards, has significantly improved fuel economy, and is competitive in performance, reliability, and potential manufacturing cost with the conventional piston engine-powered, compact-size American automobile. This is the concluding progress report for this program; it covers the period from May 1, 1978 to January 31, 1979. The next formal report will be the final report, which is currently in process. Activity during this reporting period has continued to emphasize development towards correcting a power deficiency in the Upgraded Engine. Efforts are also being directed towards reducing fuel usage through improved heat recovery and towards improving the mechanical reliability and control of the engine.

  9. Development of a model and computer code to describe solar grade silicon production processes. Fifth quarterly report

    Energy Technology Data Exchange (ETDEWEB)

    Srivastava, R.; Gould, R.K.

    1979-02-01

    This program aims at developing mathematical models, and computer codes based on these models, which will allow prediction of the product distribution in chemical reactors in which gaseous silicon compounds are converted to condensed-phase silicon. The reactors to be modeled are flow reactors in which silane or one of the halogenated silanes is thermally decomposed or reacted with an alkali metal, H/sub 2/ or H atoms. Because the product of interest is particulate silicon, processes which must be modeled, in addition to mixing and reaction of gas-phase reactants, include the nucleation and growth of condensed Si via coagulation, condensation, and heterogeneous reaction. During this report period computer codes were developed and used to calculate: (1) coefficients for Si vapor and Si particles describing transport due to concentration and temperature gradients (i.e., Fick and Soret diffusion, respectively), and (2) estimates of thermochemical properties of Si n-mers. The former are needed to allow the mass flux of Si to reactor walls to be calculated. Because of the extremely large temperature gradients that exist in some of the reactors to be used in producing Si (particularly the Westinghouse reactor), it was found that thermal (Soret) diffusion can be the dominant transport mechanism for certain sizes of Si particles. The thermochemical estimates are required to allow computation of the formation rate of Si droplets. With the completion of these calculations the information and coding of the particle routines in the modified LAPP code is at the point where debugging can be done and that is now in progress.

  10. Quarterly report for the electricity market. 2. quarter of 2012; Kvartalsrapport for kraftmarknaden. 2. kvartal 2012

    Energy Technology Data Exchange (ETDEWEB)

    Eliston, Anton Jaynand; Holmqvist, Erik; Lund, Per Tore Jensen; Magnussen, Ingrid; Viggen, Kjerstin Dahl; Willumsen, Mats Oeivind; Guren, Ingrid; Ulriksen, Margit Iren

    2012-07-01

    Fourth quarter of 2011 was unusually mild and wet, resulting in high energy inflow to the Norwegian reservoirs. Total inflow for the year was 149.2 TWh, 26.7 TWh more than normal. This ensured record-high 80.3 percent load factor at the end of the quarter.The stored energy amount in the reservoirs was thus 29.5 TWh greater than at the end of 2010/2011. Norway had a power consumption of 34.1 TWh in the fourth quarter. Compared with the same quarter of 2010, a decrease of 4.2 TWh, which can be connected to the mild weather development. The total Norwegian electricity consumption in 2011 was 125.1 TWh, or 6.9 TWh less than in 2010. Electricity production in the fourth quarter of 2011 was 38.3 GWh, an increase of 3.7 TWh from the same quarter the year before. The production increase were a result of the large volume of water in the system. Power production for the year 2011 was 128.1 TWh, an increase of 3.7 TWh from 2010. Kraft surplus was therefore large, and it was Norwegian net export of 4.2 TWh in the fourth quarter, and 3.0 TWh total for the year. In comparison, in the fourth quarter of 2010 Norwegian net import of 0.8 TWh and 7.5 TWh annually. The good resource combined with the low consumption gave a unusually low price levels in the wholesale market for electricity. On average for fourth quarter, the price of power in the East and South-East Norway Nok 264 / MWh, in western Norway Nok 260 / MWh, in Central Norway Nok 270 / MWh (eb)

  11. Development, application, and validation of a survey for infectious disease control practices at equine boarding facilities.

    Science.gov (United States)

    Kirby, Alanna T; Traub-Dargatz, Josie L; Hill, Ashley E; Kogan, Lori R; Morley, Paul S; Heird, James C

    2010-11-15

    To develop a questionnaire for self-assessment of biosecurity practices at equine boarding facilities and to evaluate infectious disease control practices in these facilities in Colorado. Cross-sectional study. 64 equine boarding facilities in Colorado. Survey questions were rated according to importance for prevention and containment of equine infectious diseases. Point values (range, 0 to 20) were assigned for possible responses, with greater values given for optimal infection control methods. Questionnaires were mailed to equine boarding facilities in Colorado advertised on the World Wide Web. Survey responses were compared with assessments made by a member of the research team during visits to 30 randomly selected facilities. Agreement among results was analyzed via a kappa test and rated as poor, fair, moderate, substantial, or nearly perfect. Survey responses were received for 64 of 163 (39%) equine boarding facilities. Scores ranged from 106 to 402 points (maximum possible score, 418). Most facilities received better scores for movement and housing of equids than for other sections of the survey. Respondents at 24 of 48 (50%) facilities that routinely received new equids reported isolation of new arrivals. Agreement between self-assessment by survey respondents and evaluation by a member of the research team was determined to be fair to substantial. Most equine boarding facilities have opportunities to improve measures for prevention or containment of contagious diseases (eg, isolation of newly arrived equids and use of written health management protocols). Most self-assessments of infection control practices were accurate.

  12. Advanced Turbine Systems (ATS) program conceptual design and product development. Quarterly report, August 25--November 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    GE has achieved a leadership position in the worldwide gas turbine industry in both industrial/utility markets and in aircraft engines. This design and manufacturing base plus our close contact with the users provides the technology for creation of the next generation advanced power generation systems for both the industrial and utility industries. GE has been active in the definition of advanced turbine systems for several years. These systems will leverage the technology from the latest developments in the entire GE gas turbine product line. These products will be USA based in engineering and manufacturing and are marketed through the GE Industrial and Power Systems. Achieving the advanced turbine system goals of 60% efficiency, 8 ppmvd NOx and 10% electric power cost reduction imposes competing characteristics on the gas turbine system. Two basic technical issues arise from this. The turbine inlet temperature of the gas turbine must increase to achieve both efficiency and cost goals. However, higher temperatures move in the direction of increased NOx emission. Improved coating and materials technologies along with creative combustor design can result in solutions to achieve the ultimate goal.

  13. Advanced Turbine Systems (ATS) program conceptual design and product development. Quarterly report, December 1, 1993--February 28, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    GE has achieved a leadership position in the worldwide gas turbine industry in both industrial/utility markets and in aircraft engines. This design and manufacturing base plus our close contact with the users provides the technology for creation of the next generation advanced power generation systems for both the industrial and utility industries. GE has been active in the definition of advanced turbine systems for several years. These systems will leverage the technology from the latest developments in the entire GE gas turbine product line. These products will be USA based in engineering and manufacturing and are marketed through the GE Industrial and Power Systems. Achieving the advanced turbine system goals of 60% efficiency, 8 ppmvd NOx and 10% electric power cost reduction imposes competing characteristics on the gas turbine system. Two basic technical issues arise from this. The turbine inlet temperature of the gas turbine must increase to achieve both efficiency and cost goals. However, higher temperatures move in the direction of increased NOx emission. Improved coating and materials technologies along with creative combustor design can result in solutions to achieve the ultimate goal.

  14. Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    This report presents the results of Run 260 performed at the Advanced Coal Liquefaction R D Facility in Wilsonville. The run was started on July 17, 1990 and continued until November 14, 1990, operating in the Close-Coupled Integrated Two-Stage Liquefaction mode processing Black Thunder mine subbituminous coal (Wyodak-Anderson seam from Wyoming Powder River Basin). Both thermal/catalytic and catalytic/thermal tests were performed to determine the methods for reducing solids buildup in a subbituminous coal operation, and to improve product yields. A new, smaller interstage separator was tested to reduce solids buildup by increasing the slurry space velocity in the separator. In order to obtain improved coal and resid conversions (compared to Run 258) full-volume thermal reactor and 3/4-volume catalytic reactor were used. Shell 324 catalyst, 1/16 in. cylindrical extrudate, at a replacement rate of 3 lb/ton of MF coal was used in the catalytic stage. Iron oxide was used as slurry catalyst at a rate of 2 wt % MF coal throughout the run. (TNPS was the sulfiding agent.)

  15. Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-01

    This report presents the results of Run 261 performed at the Advanced Coal Liquefaction R D Facility in Wilsonville, Alabama. The run started on January 12, 1991 and continued until May 31, 1991, operating in the Close-Coupled Integrated Two-Stage Liquefaction mode processing Illinois No. 6 seam bituminous coal (from Burning star No. 2 mine). In the first part of Run 261, a new bimodal catalyst, EXP-AO-60, was tested for its performance and attrition characteristics in the catalytic/catalytic mode of the CC-ITSL process. The main objective of this part of the run was to obtain good process performance in the low/high temperature mode of operation along with well-defined distillation product end boiling points. In the second part of Run 261, Criterion (Shell) 324 catalyst was tested. The objective of this test was to evaluate the operational stability and catalyst and process performance while processing the high ash Illinois No. 6 coal. Increasing viscosity and preasphaltenes made it difficult to operate at conditions similar to EXP-AO-60 catalyst operation, especially at lower catalyst replacement rates.

  16. EDF - Quarterly Financial Information

    International Nuclear Information System (INIS)

    Trivi, Carole; Boissezon, Carine de; Hidra, Kader

    2014-01-01

    EDF's sales in the first quarter of 2014 were euro 21.2 billion, down 3.9% from the first quarter of 2013. At constant scope and exchange rates, sales were down 4.2% due to mild weather conditions, which impacted sales of electricity in France, gas sales abroad and trading activities in Europe. UK sales were nonetheless sustained by B2B sales due to higher realised wholesale market prices. In Italy, sales growth was driven by an increase in electricity volumes sold. The first quarter of 2014 also saw the strengthening of the Group's financial structure with the second phase of its multi-annual hybrid funding programme (nearly euro 4 billion equivalent) as well as the issue of two 100-year bonds in dollars and sterling aimed at significantly lengthening average debt maturity. 2014 outlook and 2014-2018 vision: - EDF Group has confirmed its financial objectives for 2014; - Group EBITDA excluding Edison: organic growth of at least 3%; - Edison EBITDA: recurring EBITDA target of euro 1 billion and at least euro 600 million in 2014 before effects of gas contract re-negotiations; - Net financial debt / EBITDA: between 2x and 2.5x; - Pay-out ratio of net income excluding non-recurring items post-hybrid: 55% to 65%. The Group has reaffirmed its goal of achieving positive cash flow after dividends, excluding Linky, in 2018

  17. Development of radiation safety monitoring system at gamma greenhouse gamma facility

    International Nuclear Information System (INIS)

    Hairul Nizam Idris; Azimawati Ahmad, Ahmad Zaki Hussain; Ahmad Fairuz Mohd Nasir

    2009-01-01

    This paper is discussing about installation of radiation safety monitoring system at Gamma Greenhouse Gamma facility, Agrotechnology and Bioscience Division (BAB). This facility actually is an outdoor type irradiation facility, which first in Nuclear Malaysia and the only one in Malaysia. Source Cs-137 (801 Curie) was use as radiation source and it located at the centre of 30 metres diameter size of open irradiation area. The radiation measurement and monitoring system to be equipped in this facility were required the proper equipment and devices, specially purpose for application at outside of building. Research review, literature study and discussion with the equipment manufacturers was being carried out, in effort to identify the best system should be developed. Factors such as tropical climate, environment surrounding and security were considered during selecting the proper system. Since this facility involving with panoramic radiation type, several critical and strategic locations have been fixed with radiation detectors, up to the distance at 200 meter from the radiation source. Apart from that, this developed system also was built for capable to provide the online real-time reading (using internet). In general, it can be summarized that the radiation safety monitoring system for outdoor type irradiation facility was found much different and complex compared to the system for indoor type facility. Keyword: radiation monitoring, radiation safety, Gamma Greenhouse, outdoor irradiation facility, panoramic radiation. (Author)

  18. Development of CFD Approaches for Modeling Advanced Concepts of Nuclear Thermal Propulsion Test Facilities Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The project will be developing a CFD approach that can handle the additional complexities needed in a NTP testing facility when modeling the combustion processes in...

  19. Development of an engineered safeguards system concept for a mixed-oxide fuel fabrication facility

    International Nuclear Information System (INIS)

    Chapman, L.D.; de Montmollin, J.M.; Deveney, J.E.; Fienning, W.C.; Hickman, J.W.; Watkins, L.D.; Winblad, A.E.

    1976-08-01

    An initial concept of an Engineered Safeguards System for a representative commercial mixed-oxide fuel fabrication facility is presented. Computer simulation techniques for evaluation and further development of the concept are described. An outline of future activity is included

  20. Development and Commissioning of a Small/Mid-Size Wind Turbine Test Facility: Preprint

    Energy Technology Data Exchange (ETDEWEB)

    Valyou, D.; Arsenault, T.; Janoyan, K.; Marzocca, P.; Post, N.; Grappasonni, G.; Arras, M.; Coppotelli, G.; Cardenas, D.; Elizalde, H.; Probst, O.

    2015-01-01

    This paper describes the development and commissioning tests of the new Clarkson University/Center for Evaluation of Clean Energy Technology Blade Test Facility. The facility is a result of the collaboration between the New York State Energy Research and Development Authority and Intertek, and is supported by national and international partners. This paper discusses important aspects associated with blade testing and includes results associated with modal, static, and fatigue testing performed on the Sandia National Laboratories' Blade Systems Design Studies blade. An overview of the test capabilities of the Blade Test Facility are also provided.

  1. Development of a spent fuel management technology research and test facility

    International Nuclear Information System (INIS)

    Park, S. W.; Noh, S. K.; Lee, J. S. and others

    1997-12-01

    This study was intended to develop concept for a pilot-scale remote operation facility for longer term management of spent fuel and therefrom to provide technical requirement for later basic design of the facility. Main scope of work for the study was to revise the past (1990) conceptual design in functions, scale, hot cell layout, etc. based on user requirements. Technical reference was made to the PKA facility in Germany, through collaboration with appropriate partner, to elaborate the design and requirements. A simulator of the conceptual design was also developed by use of virtual reality technique by 3-D computer graphics for equipment and building. (author). 18 tabs., 39 figs

  2. Design, fabrication, and mockup testing in the Remote Maintenance Development Facility

    International Nuclear Information System (INIS)

    Carter, J.A.; Jacobs, R.T.; Bingham, G.E.

    1978-01-01

    The Remote Maintenance Development Facility (RMDF) at the Idaho National Engineering Laboratory (INEL) was installed and used extensively for full-scale development, mockup and testing of remote maintenance requirements for the New Waste Calcining Facility (NWCF). By performing remote handling tests, the NWCF handling concepts, techniques and remote capabilities were proven workable prior to construction. Presented in this paper is a description of the RMDF and its purpose, functions, and handling capabilities as they were used in support of the NWCF

  3. Design, fabrication, and mockup testing in the remote maintenance development facility

    International Nuclear Information System (INIS)

    Carter, J.A.; Jacobs, R.T.; Bingham, G.E.

    1978-01-01

    The Remote Maintenance Development Facility at the Idaho National Engineering Laboratory was installed and used extensively for full-scale development, mockup, and testing of remote maintenance requirements for the New Waste Calcining Facility (NWCF). By performing remote handling tests, the NWCF handling concepts, techniques, and remote capabilities were proven workable prior to construction. A description of the RMDF and its purpose, functions, and handling capabilities as they were used in support of the NWCF is presented

  4. The development of radiation hardened robot for nuclear facility

    International Nuclear Information System (INIS)

    Kim, Seung Ho; Jung, Seung Ho; Kim, Byung Soo and others

    2000-04-01

    The work conducted in this stage covers development of core technology of tele-robot system including monitoring technique in high-level radioactive area, tele-sensing technology and radiation-hardened technology for the non-destructive tele-inspection system which monitors the primary coolant system during the normal operations of PHWR(Pressurized Heavy Water Reactor) NPPs and measures the decrease of bending part of feeder pipe during overall. Based on the developed core technology, the monitoring mobile robot system of the primary coolant system and the feeder pipe inspecting robot system are developed

  5. The development of radiation hardened robot for nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Ho; Jung, Seung Ho; Kim, Byung Soo and others

    2000-04-01

    The work conducted in this stage covers development of core technology of tele-robot system including monitoring technique in high-level radioactive area, tele-sensing technology and radiation-hardened technology for the non-destructive tele-inspection system which monitors the primary coolant system during the normal operations of PHWR(Pressurized Heavy Water Reactor) NPPs and measures the decrease of bending part of feeder pipe during overall. Based on the developed core technology, the monitoring mobile robot system of the primary coolant system and the feeder pipe inspecting robot system are developed.

  6. Development of ISA procedure for uranium fuel fabrication and enrichment facilities

    International Nuclear Information System (INIS)

    Yamate, Kazuki; Arakawa, Tomoyuki; Yamashita, Masahiro; Sasaki, Noriaki; Hirano, Mitsumasa

    2011-01-01

    The integrated safety analysis (ISA) procedure has been developed to apply risk-informed regulation to uranium fuel fabrication and enrichment facilities. The major development efforts are as follows: (a) preparing the risk level matrix as an index for items-relied-on-for-safety (IROFS) identification, (b) defining requirements of IROFS, and (c) determining methods of IROFS importance based on the results of risk- and scenario-based analyses. For the risk level matrix, the consequence and likelihood categories have been defined by taking into account the Japanese regulatory laws, rules, and safety standards. The trial analyses using the developed procedure have been performed for several representative processes of the reference uranium fuel fabrication and enrichment facilities. This paper presents the results of the ISA for the sintering process of the reference fabrication facility. The results of the trial analyses have demonstrated the applicability of the procedure to the risk-informed regulation of these facilities. (author)

  7. "Research in Natural Historical Value of East Region of Russia and Siberia": a Role of Society of Scientists at the Kazan University in Development of Ethnography in the First Quarter of the XX Century

    Directory of Open Access Journals (Sweden)

    Tatiana А. Titova

    2015-09-01

    Full Text Available In article on the basis of archival material the role of Society of scientists at Imperial Kazan university in development of ethnography in the first quarter of the XX century as science and a subject matter reveals. The special place is allocated for three expeditions of the students specializing on department of geography and ethnography of physical and mathematical office of Imperial Kazan university, sent to means of Society of scientists to field ethnographic expeditions. S. A. Teploukhov, V. M. Novitsky and V. I. Podgorbunsky under the leadership of outstanding scientific professor Bruno Fridrikhovich Adler studied, comprehended bases of scientific researches, made expeditions and acquired a basis of further career that allowed them to become the talented scientists who made a powerful contribution to development of ethnology, archeology, anthropology and history in the first quarter of the XX century.

  8. Diagnostic development for the Atlas pulsed power facility

    CERN Document Server

    Taylor, A J; Fulton, R D; Oro, D M; McCuistian, B T; Clark, D A; Roberts, J P; Holtkamp, D B; Watt, R G; Bartsch, R R; Trainor, R J

    1999-01-01

    Atlas will be a 23 MJ capacitor bank capable of delivering greater than 30 MA to a liner target with a nominal 4 microsecond risetime. We describe here our ongoing diagnostic development efforts in this extreme Atlas environment. Included in this discussion are development efforts in X-ray radiography, shock physics diagnostics, and temperature and pressure diagnostics. X-ray radiography is the key diagnostic for visualizing the shock-induced fluid flows characteristic of the proposed Atlas experiments. Due to the large area densities needed for Atlas targets, a number of radiographic systems are under investigation. Diagnostics that address shock physics issues on Atlas include VISAR (velocity interferometer for a surface of any reflector), shock breakout, optical pins, and dark- field shadowgraphy. Temperature diagnostics include infrared pyrometry. As pressure diagnostics we are developing probes based on the pressure dependence of the frequency of fluorescence lines from ruby and the Raman shift in diamon...

  9. Development of beam instruments at JAERI cyclotron facility

    Energy Technology Data Exchange (ETDEWEB)

    Okumura, Susumu; Fukuda, Mitsuhiro; Ishibori, Ikuo; Agematsu, Takashi; Yokota, Watalu; Nara, Takayuki; Nakamura, Yoshiteru; Arakawa, Kazuo [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment

    1997-03-01

    A beam phase monitor and two kinds of fluence distribution monitors have been developed for measuring characteristics of cyclotron beams. The beam phase monitor provides a beam phase signal for tuning a beam chopping system and a beam phase selection system. A two-dimensional fluence distribution on a large area is measured with fluence distribution monitors. (author)

  10. Environmental Restoration Operations Consolidated Quarterly Report: July-September 2016

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-01-01

    This Environmental Restoration Operations (ER) Consolidated Quarterly Report (ER Quarterly Report) provides the status of ongoing corrective action activities being implemented at Sandia National Laboratories, New Mexico (SNL/NM) during the July, August, and September 2016 quarterly reporting period. The Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) identified for corrective action at SNL/NM are listed in Table I-1. Sections I.2.1 and I.2.2 summarize the work completed during this quarter. Section I.2.1 summarizes the quarterly activities at sites undergoing corrective action field activities. Field activities are conducted at the three groundwater AOCs (Burn Site Groundwater [BSG AOC], Technical Area [TA]-V Groundwater [TAVG AOC], and Tijeras Arroyo Groundwater [TAG AOC]). Section I.2.2 summarizes quarterly activities at sites where the New Mexico Environment Department (NMED) issued a certificate of completion and the sites are in the corrective action complete (CAC) regulatory process. Currently, SWMUs 8 and 58, 68, 149, 154, and 502 are in the CAC regulatory process. Corrective action activities are deferred at the Long Sled Track (SWMU 83), the Gun Facilities (SWMU 84), and the Short Sled Track (SWMU 240) because these three sites are active mission facilities. These three active sites are located in TA-III.

  11. Progress towards developing consistent design and evaluation guidelines for DOE facilities subjected to natural phenomena hazards

    International Nuclear Information System (INIS)

    Kennedy, R.P.; Short, S.A.; McDonald, J.R.; McCann, M.W. Jr.; Reed, J.W.

    1985-01-01

    Probabilistic definitions of earthquake, wind and tornado natural phenomena hazards for many Department of Energy (DOE) facilities throughout the United States have been developed. In addition, definitions of the flood hazards which might affect these locations are currently being developed. The Department of Energy Natural Phenomena Hazards Panel is now preparing a document to provide guidance and criteria for DOE facility managers to assure that DOE facilities are adequately constructed to resist the effects of natural phenomena such as earthquake, strong wind and flood. The intent of this document is to provide instruction on how to utilize the hazard definitions to evaluate existing facilities and design new facilities in a manner such that the risk of adverse consequences is consistent with the cost, function, and danger to the public or environment of the facility. Potential effects on facilities of natural phenomena hazards are emphasized in this paper. The philosophy for mitigating these effects to be employed in the design and evaluation guidelines is also presented

  12. Intergenerational Facilities: Designing Intergenerational Space through a Human Development Lens

    OpenAIRE

    Norouzi, Neda

    2016-01-01

    ABSTRACT The built environment can be structured to encourage or discourage social interaction and can have effects on children's cognitive, social, and emotional development as well as effects on elder's health and well-being. Knowing the profound influence of the built environment on elders (Garin, et al., 2014) and children (Bradford, 2012), the design of intergenerational spaces therefore has the potential to influence the interaction between elders and children engaged in intergenerat...

  13. Review of Facility Technology Options and their Development Status

    Science.gov (United States)

    1989-06-01

    Nickel-hydrogen Gates Nickel-cadmium Eagle-Picher Industries Nickel-cadmium Eagle-Picher Industries Nickel-hydrogen Yardney Nickel-hydrogen Yardney ...Silver-zinc Yardney Silver-cadmium SAFT America Nickel-cadmium 85 Table 31 Organizations Developing Advanced Secondary Battery Systems Advanced Lead...Acid Nickel-Hydrogen Johnson Controls Eagle-Picher Exide Johnson Controls C&D Batteries Gates Yardney Energy Research Corp. Nickel-Zinc Sodium-Sulfur GM

  14. Calorimetry exchange program. Quarterly data report, 2nd quarter 1992

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, T.M.

    1996-07-01

    The goals of the Calorimetry Sample Exchange Program are: (1) Discuss measurement differences, (2) Review and improve analytical measurements and methods, (3) Discuss new measurement capabilities, (4) Provide data to DOE on measurement capabilities to evaluate shipper-receiver differences, (5) Provide characterized or standard materials as necessary for exchange participants, (6) Provide a measurement control program for plutonium analysis. A sample of PuO{sub 2} powder is available at each participating site for NDA measurement, including either or both calorimetry and high-resolution gamma-ray spectroscopy, the elements which are typically combined to provide a calorimetric assay of plutonium. The facilities measure the sample as frequently and to the level of precision which they desire, and then submit the data to the Exchange for analysis. Statistical tests are used to evaluate the data and to determine if there are significant differences from accepted values for the exchange sample or from data previously reported by that facility. This information is presented, in the form of a quarterly report, intended for use by Exchange participants in measurement control programs, or to indicate when bias corrections may be appropriate. No, attempt, however, has been made to standardize methods or frequency of data collection, calibration, or operating procedures. Direct comparisons between laboratories may, therefore, be misleading since data have not been collected to the same precision or for the same time periods. A meeting of the participants of the Calorimetry Exchange is held annually at EG&G Mound Applied Technologies. The purposes of this meeting are to discuss measurement differences, problems, and new measurement capabilities, and to determine the additional activities needed to fulfill the goals of the Exchange.

  15. Environmental consequences of hydroelectric development: the role of facility size and type

    International Nuclear Information System (INIS)

    Gleick, P.H.

    1992-01-01

    The development of hydroelectric power throughout the world is receiving renewed attention as the economic, political, and environmental costs of conventional energy production rise. There is currently a perception that hydroelectricity has environmental and economic advantages over electricity produced by conventional energy technologies, but there is a paucity of information about the environmental impacts of hydroelectric facilities as a function of size and type. We characterize the environmental impacts of hydroelectric developments and quantify these impacts as a function of the size and type of project. Several unexpected conclusions arise from our analysis. For most hydroelectric facilities, size, as measured by installed capacity, is not necessarily a good indicator or the severity of environmental costs. For impacts such as land flooded and evaporative water lost, smaller facilities cause greater environmental disruptions per unit of energy produced than do larger facilities. (Author)

  16. Development of a standardized transfusion ratio as a metric for evaluating dialysis facility anemia management practices.

    Science.gov (United States)

    Liu, Jiannong; Li, Suying; Gilbertson, David T; Monda, Keri L; Bradbury, Brian D; Collins, Allan J

    2014-10-01

    Because transfusion avoidance has been the cornerstone of anemia treatment for patients with kidney disease, direct measurement of red blood cell transfusion use to assess dialysis facility anemia management performance is reasonable. We aimed to explore methods for estimating facility-level standardized transfusion ratios (STfRs) to assess provider anemia treatment practices. Retrospective cohort study. Point prevalent US hemodialysis patients on January 1, 2009, with Medicare as primary payer and dialysis duration of 90 days or longer were included (n = 223,901). All dialysis facilities with eligible patients were included (n = 5,345). Dialysis facility assignment. Receiving a red blood cell transfusion in the inpatient or outpatient setting. We evaluated 3 approaches for estimating STfR: ratio of observed to expected numbers of transfusions (STfR(obs)), a Bayesian approach (STfR(Bayes)), and a modified version of the Bayesian approach (STfR(modBayes)). The overall national transfusion rate in 2009 was 23.2 per 100 patient-years. Our model for predicting the expected number of transfusions performed well. For large facilities, all 3 STfRs worked well. However, for small facilities, while the STfR(modBayes) worked well, STfR(obs) values demonstrated instability and the STfR(Bayes) may produce more bias. Administration of transfusions to dialysis patients reflects medical practice both within and outside the dialysis unit. Some transfusions may be deemed unavoidable and transfusion practices are subject to considerable regional variation. Development of an STfR metric is feasible and reasonable for assessing anemia treatment at dialysis facilities. The STfR(obs) is simple to calculate and works well for larger dialysis facilities. The STfR(modBayes) is more analytically complex, but facilitates comparisons across all dialysis facilities, including small facilities. Copyright © 2014 National Kidney Foundation, Inc. Published by Elsevier Inc. All rights reserved.

  17. Fusion Power Program. Quarterly progress report, January-March 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-08-01

    This quarterly report summarizes the Argonne National Laboratory work performed for the Office of Fusion Energy during the January-March 1979 quarter in the following research and development areas: materials; energy storage and transfer; tritium containment, recovery and control; advanced reactor design; atomic data; reactor safety; fusion-fission hybrid systems; alternate applications of fusion energy; and other work related to fusion power.

  18. Future aerospace ground test facility requirements for the Arnold Engineering Development Center

    Science.gov (United States)

    Kirchner, Mark E.; Baron, Judson R.; Bogdonoff, Seymour M.; Carter, Donald I.; Couch, Lana M.; Fanning, Arthur E.; Heiser, William H.; Koff, Bernard L.; Melnik, Robert E.; Mercer, Stephen C.

    1992-01-01

    Arnold Engineering Development Center (AEDC) was conceived at the close of World War II, when major new developments in flight technology were presaged by new aerodynamic and propulsion concepts. During the past 40 years, AEDC has played a significant part in the development of many aerospace systems. The original plans were extended through the years by some additional facilities, particularly in the area of propulsion testing. AEDC now has undertaken development of a master plan in an attempt to project requirements and to plan for ground test and computational facilities over the coming 20 to 30 years. This report was prepared in response to an AEDC request that the National Research Council (NRC) assemble a committee to prepare guidance for planning and modernizing AEDC facilities for the development and testing of future classes of aerospace systems as envisaged by the U.S. Air Force.

  19. Environmental Assessment for Developing Renewable Energy Enhanced Use Lease Facilities at Robins Air Force Base

    Science.gov (United States)

    2013-12-15

    PV facilities would have insignificant adverse cumulative impacts on topography, surface waters, soils , air quality, noise, Final ‐ Environmental...development of the solar PV array. Final ‐ Environmental Assessment  Renewable  Energy  EUL Facilities at Robins AFB  December 2013 iv CONTENTS... shading .  Land Availability - The renewable energy site considered must be comprised of at least 50 acres of contiguous, non-excess, Air Force

  20. DEVELOPMENT OF BIM/GIS INTEROPERABLE PLATFORM FOR FACILITY MANAGEMENT IN KOREA

    OpenAIRE

    Chunjoo Yoon; Changhee Hong

    2017-01-01

    South Korea is making facility design using Building Information Modeling (BIM) mandatory and expanding the use of BIM. However, BIM technology has been used limitedly only from the design to construction phases but it has rarely been applied to the maintenance phase in Korea. To overcome this problem, data management and related technologies are needed during the entire life cycle of the facility construction process. This study developed a platform by which BIM data at the constru...

  1. Development of technological software for NPP training facilities using the principle of resource minimization

    International Nuclear Information System (INIS)

    Okhotin, V.V.; Plyutinskij, V.I.

    1990-01-01

    Possibilities of developing technological software for full-scale and functional NPP training facilities using the principle of computer resource minimization, are considered. It is proved that application of a regime approach to simulation and creation of technological software systems for reconstructable training facilities allow one to provide for a possibility of optimal combination of fully variable simulation and situation calculation for software moduli necessary at the moment with the problems of organizing the training process at the training facilty

  2. Development of oilfield facilities on a nature reserve

    International Nuclear Information System (INIS)

    Long, P.J.; Long, V.L.

    1991-01-01

    This paper reports on Airlie Island which is a small (26 hectare) sand cay, located 35km north of Onslow in Western Australia. In common with other islands in the region, Airlie is a nesting site for seabirds and turtles, but its two primary conservation resources are the large Wedge-tailed Shearwater rookery which covers 64% of the island and an endemic skink species. Its conservation values have prompted the Western Australian State Government to declare the entire island a nature reserve set apart for the preservation of flora and fauna. In 1987 Western Mining Corporation Pty Ltd. developed the South Pepper and North herald oilfields and part of this development included the siting of an oil terminal on Airlie Island. It may be expected that the conservation resources of the island and the Company's requirements for land would be incompatible. However, a careful study of the local environment and the creation of a detailed plan to manage this environment resulted in an acceptable compromise

  3. Status of electro-nuclear facilities development in ITEP

    International Nuclear Information System (INIS)

    The concept of plutonium management, both weapon-grade and power, should be developed taking into account the history of previous stages of the nuclear industry and ideas which guided the process of their implementation. Theoretical studies of several versions of a neutron multiplying subcritical system based on thermal and epithermal neutrons are conducted in ITEP. Systems with several neutron multiplying subcritical sections are considered connected by neutron flux propagation from a previous section to subsequent one. This could be implemented by the use of neutron valves separating these sections that permits to decrease the requirements imposed upon proton beam power significantly. Heterogeneous and homogeneous approaches to implementation of such systems are studied. There are many problems associated with nuclear constants and their classification. Measurements are performed of thermal effects in various materials under proton beam irradiation. Problems associated with materials are in the process of investigation too. Joint programs and division of labour should be organized

  4. Status of electro-nuclear facilities development in ITEP

    Energy Technology Data Exchange (ETDEWEB)

    Chuvilo, I.V. [ITEP, Moscow (Russian Federation)

    1995-10-01

    The concept of plutonium management, both weapon-grade and power, should be developed taking into account the history of previous stages of the nuclear industry and ideas which guided the process of their implementation. Theoretical studies of several versions of a neutron multiplying subcritical system based on thermal and epithermal neutrons are conducted in ITEP. Systems with several neutron multiplying subcritical sections are considered connected by neutron flux propagation from a previous section to subsequent one. This could be implemented by the use of neutron valves separating these sections that permits to decrease the requirements imposed upon proton beam power significantly. Heterogeneous and homogeneous approaches to implementation of such systems are studied. There are many problems associated with nuclear constants and their classification. Measurements are performed of thermal effects in various materials under proton beam irradiation. Problems associated with materials are in the process of investigation too. Joint programs and division of labour should be organized.

  5. Developing tourism facilities based on geotourism in Silalahi Village, Geopark Toba Caldera

    Science.gov (United States)

    Ginting, Nurlisa; Sasmita, Anggun

    2018-03-01

    Toba Caldera is one of the biggest lakes in Indonesia with supervolcano geology phenomenon, and its result amazing natural resources. It makes Toba Lake become the number one tourism in North Sumatera. However, tourism in Toba Lake is still needed development. Geotourism is one of the concept that suitable for this case. It is because geotourism is a new development tourism concept that focuses on the natural and geological phenomenon. Silalahi Village is one of the areas in Toba Caldera that still needs development, especially in tourism facilities sector. This research aims to investigation the facilities concept based on geotourism in Silalahi Village that would be analyzed by three element of tourism facilities namely, accommodation, support facilities and tourism auxiliary facilities. The method used for this research is mixed methods by distributing 100 questionnaires, observations directly to the area and interviews with three informants related parties interested in tourism, such as local people, government, and academics. The data would be processed and analyzed with techniques of exploration. The result shows that the three elements of tourism facilities are still lacking and needs to improve to increase the economy and tourism in the area.

  6. Mirror fusion. Quarterly report, April-June 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-09-11

    The information in each Quarterly is presented in the same sequence as in the Field Work Package Proposal and Authorization System (WPAS) submissions prepared for the U.S. Department of Energy; the main sections are Applied Plasma Physics, Confinement Systems, Development and Technology, and Mirror Fusion Test Facility (Planning and Projects). On occasion, we shall include information pertaining to the LLNL role as Lead Laboratory for the Open Systems Mirror Fusion Program. Each of these sections is introduced by an overall statement of the goals and purposes of the groups reporting in it. As appropriate within each section, statements of the goals of individual programs and projects are followed by articles containing summaries of significant recent activity and descriptive text.

  7. RESEARCH AND DEVELOPMENT ACTIVITIES AT SAVANNAH RIVER SITE'S H CANYON FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Sexton, Lindsay; Fuller, Kenneth

    2013-07-09

    The Savannah River Site's (SRS) H Canyon Facility is the only large scale, heavily shielded, nuclear chemical separations plant still in operation in the U.S. The facility's operations historically recovered uranium-235 (U-235) and neptunium-237 (Np-237) from aluminum-clad, enriched-uranium fuel tubes from Site nuclear reactors and other domestic and foreign research reactors. Today the facility, in conjunction with HB Line, is working to provide the initial feed material to the Mixed Oxide Facility also located on SRS. Many additional campaigns are also in the planning process. Furthermore, the facility has started to integrate collaborative research and development (R&D) projects into its schedule. H Canyon can serve as the appropriate testing location for many technologies focused on monitoring the back end of the fuel cycle, due to the nature of the facility and continued operation. H Canyon, in collaboration with the Savannah River National Laboratory (SRNL), has been working with several groups in the DOE complex to conduct testing demonstrations of novel technologies at the facility. The purpose of conducting these demonstrations at H Canyon will be to demonstrate the capabilities of the emerging technologies in an operational environment. This paper will summarize R&D testing activities currently taking place in H Canyon and discuss the possibilities for future collaborations.

  8. Development and performances of a high statistics PMT test facility

    Directory of Open Access Journals (Sweden)

    Mollo Carlos Maximiliano

    2016-01-01

    Full Text Available Since almost a century photomultipliers have been the main sensors for photon detection in nuclear and astro-particle physics experiments. In recent years the search for cosmic neutrinos gave birth to enormous size experiments (Antares, Kamiokande, Super-Kamiokande, etc. and even kilometric scale experiments as ICECUBE and the future KM3NeT. A very large volume neutrino telescope like KM3NeT requires several hundreds of thousands photomultipliers. The performance of the telescope strictly depends on the performance of each PMT. For this reason, it is mandatory to measure the characteristics of each single sensor. The characterization of a PMT normally requires more than 8 hours mostly due to the darkening step. This means that it is not feasible to measure the parameters of each PMT of a neutrino telescope without a system able to test more than one PMT simultaneously. For this application, we have designed, developed and realized a system able to measure the main characteristics of 62 3-inch photomultipliers simultaneously. Two measurement sessions per day are possible. In this work, we describe the design constraints and how they have been satisfied. Finally, we show the performance of the system and the first results coming from the test of few thousand tested PMTs.

  9. The Development of a Radiation Hardened Robot for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Seung Ho; Kim, Chang Hoi; Seo, Yong Chil (and others)

    2007-04-15

    We has been developed two remotely controlled robotic systems. One is a underwater vehicle for inspection of the internal structures of PWRs and retrieving foreign stubs in the reactor pressure vessels and reactor coolant pipes. The other robotic system consists of a articulated-type mobile robot capable of recovering the failure of the fuel exchange machine and a mini modular mobile robot for inspection of feeder pipes with ultrasonic array sensors in PHWRs. The underwater robot has been designed by considering radiation effect, underwater condition, and accessibility to the working area. The size of underwater robot is designed to enter the cold legs. A extendable manipulator is mounted on the mobile robot, which can restore nuclear fuel exchange machine. The mini modular mobile robot is composed of dual inch worm mechanisms, which are constructed by two gripper bodies that can fix the robot body on to the pipe and move along the longitudinal and to rotate in a circumferential direction to access all of the outer surfaces of the pipe.

  10. The Development of a Radiation Hardened Robot for Nuclear Facilities

    International Nuclear Information System (INIS)

    Jung, Seung Ho; Kim, Chang Hoi; Seo, Yong Chil

    2007-04-01

    We has been developed two remotely controlled robotic systems. One is a underwater vehicle for inspection of the internal structures of PWRs and retrieving foreign stubs in the reactor pressure vessels and reactor coolant pipes. The other robotic system consists of a articulated-type mobile robot capable of recovering the failure of the fuel exchange machine and a mini modular mobile robot for inspection of feeder pipes with ultrasonic array sensors in PHWRs. The underwater robot has been designed by considering radiation effect, underwater condition, and accessibility to the working area. The size of underwater robot is designed to enter the cold legs. A extendable manipulator is mounted on the mobile robot, which can restore nuclear fuel exchange machine. The mini modular mobile robot is composed of dual inch worm mechanisms, which are constructed by two gripper bodies that can fix the robot body on to the pipe and move along the longitudinal and to rotate in a circumferential direction to access all of the outer surfaces of the pipe

  11. Development of the RRR Cold Neutron Source facility

    International Nuclear Information System (INIS)

    Masriera, N.; Lecot, C.; Hergenreder, D.; Lovotti, O.; Serebrov, A.; Zakharov, A.; Mityukhlyaev, V.

    2003-01-01

    This paper describes some general design issues on the Cold Neutron Source (CNS) of the Replacement Research Reactor (RRR) for the Australian Nuclear Science and Technology Organisation (ANSTO). The description covers different aspects of the design: the requirements that lead to an innovative design, the overall design itself and the definition of a technical approach in order to develop the necessary design solutions. The RRR-CNS has liquid Deuterium (LD2) moderator, sub-cooled to ensure maximum moderation efficiency, flowing within a closed natural circulation Thermosiphon loop. The Thermosiphon is surrounded by a CNS Vacuum Containment made of zirconium alloy, that provides thermal insulation and a multiple barriers scheme to prevent Deuterium from mixing with water or air. Consistent with international practice, this vessel is designed to withstand any hypothetical energy reaction should Deuterium and air mix in its interior. The applied design approach allows ensuring that the RRR-CNS, in spite of being innovative, will meet all the design, performance and quality requirements. (author)

  12. Development of post-irradiation test facility for domestic production of 99Mo

    International Nuclear Information System (INIS)

    Taguchi, Taketoshi; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Nishikata, Kaori; Ishida, Takuya; Kawamata, Kazuo

    2013-01-01

    JMTR focus on the activation method. By carrying out the preliminary tests using irradiation facilities existing, and verification tests using the irradiation facility that has developed in the cutting-edge research and development strategic strengthening business, as irradiation tests towards the production of 99 Mo, we have been conducting research and development that can contribute to supply about 25% for 99 Mo demand in Japan and the stable supply of radiopharmaceutical. This report describes a summary of the status of the preliminary tests for the production of 99 Mo: Maintenance of test equipment in the facility in JMTR hot laboratory in preparation for research and development for the production of 99 Mo in JMTR and using MoO 3 pellet irradiated at Kyoto University Research Reactor Institute (KUR). (author)

  13. Development and implementation of the internal audit mechanisms to be used in the health care facilities.

    Science.gov (United States)

    Smeyanov, V; Tarasenko, S; Smeyanova, O

    2013-06-01

    Issues concerning the quality of care service improvement have become of national importance in the health-care system for both developed and developing countries. Internal audit is effective and efficient method to improve the quality of care in various health care facilities. Data from 452 outpatient cards of the case patients with arterial hypertension were analyzed, the level of awareness and patient compliance were defined. The stages of internal audit mechanisms implementation in the health care facilities were developed. As a result of medical records audit and awareness monitoring of patients with arterial hypertension ways to improve quality of medical care were defined.

  14. Native American Technical Assistance and Training for Renewable Energy Resource Development and Electrical Generation Facilities Management

    Energy Technology Data Exchange (ETDEWEB)

    A. David Lester

    2008-10-17

    The Council of Energy Resource Tribes (CERT) will facilitate technical expertise and training of Native Americans in renewable energy resource development for electrical generation facilities, and distributed generation options contributing to feasibility studies, strategic planning and visioning. CERT will also provide information to Tribes on energy efficiency and energy management techniques.This project will provide facilitation and coordination of expertise from government agencies and private industries to interact with Native Americans in ways that will result in renewable energy resource development, energy efficiency program development, and electrical generation facilities management by Tribal entities. The intent of this cooperative agreement is to help build capacity within the Tribes to manage these important resources.

  15. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I

    International Nuclear Information System (INIS)

    Abdou, M.

    1984-10-01

    The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios

  16. Stanford Synchrotron Radiation Laboratory 1991 activity report. Facility developments January 1991--March 1992

    International Nuclear Information System (INIS)

    Cantwell, K.; St. Pierre, M.

    1992-01-01

    SSRL is a national facility supported primarily by the Department of Energy for the utilization of synchrotron radiation for basic and applied research in the natural sciences and engineering. It is a user-oriented facility which welcomes proposals for experiments from all researchers. The synchrotron radiation is produced by the 3.5 GeV storage ring, SPEAR, located at the Stanford Linear Accelerator Center (SLAC). SPEAR is a fully dedicated synchrotron radiation facility which operates for user experiments 7 to 9 months per year. SSRL currently has 24 experimental stations on the SPEAR storage ring. There are 145 active proposals for experimental work from 81 institutions involving approximately 500 scientists. There is normally no charge for use of beam time by experimenters. This report summarizes the activity at SSRL for the period January 1, 1991 to December 31, 1991 for research. Facility development through March 1992 is included

  17. Treatment facilities, human resource development, and future prospect of particle beam therapy

    International Nuclear Information System (INIS)

    Tamaki, Tomoaki; Nakano, Takashi

    2015-01-01

    The number of particle beam therapy facilities is increasing globally. Among the countries practicing particle beam therapy, Japan is one of the leading countries in the field with four operating carbon-ion therapy facilities and ten operating proton therapy facilities. With the increasing number of particle beam therapy facilities, the human resource development is becoming extremely important, and there has been many such efforts including the Gunma University Program for Cultivating Global Leaders in Heavy Ion Therapeutics and Engineering, which aimed to educate and train the radiation oncologists, medical physicists, accelerator engineers, and radiation biologists to become global leaders in the field of particle beam therapy. In the future, the benefit and effectiveness of particle beam therapy should be discussed and elucidated objectively in a framework of comprehensive cancer care. (author)

  18. Stanford Synchrotron Radiation Laboratory 1991 activity report. Facility developments January 1991--March 1992

    Energy Technology Data Exchange (ETDEWEB)

    Cantwell, K.; St. Pierre, M. [eds.

    1992-12-31

    SSRL is a national facility supported primarily by the Department of Energy for the utilization of synchrotron radiation for basic and applied research in the natural sciences and engineering. It is a user-oriented facility which welcomes proposals for experiments from all researchers. The synchrotron radiation is produced by the 3.5 GeV storage ring, SPEAR, located at the Stanford Linear Accelerator Center (SLAC). SPEAR is a fully dedicated synchrotron radiation facility which operates for user experiments 7 to 9 months per year. SSRL currently has 24 experimental stations on the SPEAR storage ring. There are 145 active proposals for experimental work from 81 institutions involving approximately 500 scientists. There is normally no charge for use of beam time by experimenters. This report summarizes the activity at SSRL for the period January 1, 1991 to December 31, 1991 for research. Facility development through March 1992 is included.

  19. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    International Nuclear Information System (INIS)

    Warner, C.L.

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described

  20. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Warner, C.L. (comp.)

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described.

  1. Principles of developing the knowledge portal on safety of nuclear facilities

    International Nuclear Information System (INIS)

    Klevtsov, A.; Orlov, V.Yu.; Trubchaninov, S.A.

    2010-01-01

    The general principles of developing the knowledge portal on safety of nuclear facilities are considered in the article. In future, these principles can be used for implementing the project on development of the knowledge portal for the State Nuclear Regulatory Committee of Ukraine.

  2. Information engineering and the Information Engineering Facility verus rapid application development and FOCUS

    OpenAIRE

    Clark, Lucille Charlotte

    1992-01-01

    Approved for public release; distribution is unlimited The Management Information Systems Department of the Naval Postgraduate School (NPS) is considering using the information engineering methodology with Texas Instrument's Information Engineering Facility (IEF), an integrated computer-aided software engineering toolset, for application development. The costs and benefits of introducing information engineering and IEP versus the rapid application development methodology and fourth genera...

  3. Development tendencies of energy facilities in Central and Eastern European countries in transition

    International Nuclear Information System (INIS)

    Riesner, W.; Stuits, I.; Zeltins, N.

    1999-01-01

    The present work considers development problems of energy facilities in Central and Eastern European countries being in transition in the period from 1990 to 1997. It outlines the changes in economical situation during this period. The paper also shows the development dynamics for economic indicators in 11 countries and analyses them for each country taken separately. (author)

  4. Federal Facility Agreement progress report

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    The (SRS) Federal Facility Agreement (FFA) was made effective by the US. Environmental Protection Agency Region IV (EPA) on August 16, 1993. To meet the reporting requirements in Section XXV of the Agreement, the FFA Progress Report was developed. The FFA Progress Report is the first of a series of quarterly progress reports to be prepared by the SRS. As such this report describes the information and action taken to September 30, 1993 on the SRS units identified for investigation and remediation in the Agreement. This includes; rubble pits, runoff basins, retention basin, seepage basin, burning pits, H-Area Tank 16, and spill areas.

  5. Federal Facility Agreement progress report

    International Nuclear Information System (INIS)

    1993-10-01

    The (SRS) Federal Facility Agreement (FFA) was made effective by the US. Environmental Protection Agency Region IV (EPA) on August 16, 1993. To meet the reporting requirements in Section XXV of the Agreement, the FFA Progress Report was developed. The FFA Progress Report is the first of a series of quarterly progress reports to be prepared by the SRS. As such this report describes the information and action taken to September 30, 1993 on the SRS units identified for investigation and remediation in the Agreement. This includes; rubble pits, runoff basins, retention basin, seepage basin, burning pits, H-Area Tank 16, and spill areas

  6. Development and evaluation of fully automated demand response in large facilities

    Energy Technology Data Exchange (ETDEWEB)

    Piette, Mary Ann; Sezgen, Osman; Watson, David S.; Motegi, Naoya; Shockman, Christine; ten Hope, Laurie

    2004-03-30

    This report describes the results of a research project to develop and evaluate the performance of new Automated Demand Response (Auto-DR) hardware and software technology in large facilities. Demand Response (DR) is a set of activities to reduce or shift electricity use to improve electric grid reliability, manage electricity costs, and ensure that customers receive signals that encourage load reduction during times when the electric grid is near its capacity. The two main drivers for widespread demand responsiveness are the prevention of future electricity crises and the reduction of electricity prices. Additional goals for price responsiveness include equity through cost of service pricing, and customer control of electricity usage and bills. The technology developed and evaluated in this report could be used to support numerous forms of DR programs and tariffs. For the purpose of this report, we have defined three levels of Demand Response automation. Manual Demand Response involves manually turning off lights or equipment; this can be a labor-intensive approach. Semi-Automated Response involves the use of building energy management control systems for load shedding, where a preprogrammed load shedding strategy is initiated by facilities staff. Fully-Automated Demand Response is initiated at a building or facility through receipt of an external communications signal--facility staff set up a pre-programmed load shedding strategy which is automatically initiated by the system without the need for human intervention. We have defined this approach to be Auto-DR. An important concept in Auto-DR is that a facility manager is able to ''opt out'' or ''override'' an individual DR event if it occurs at a time when the reduction in end-use services is not desirable. This project sought to improve the feasibility and nature of Auto-DR strategies in large facilities. The research focused on technology development, testing

  7. NRC quarterly [status] report

    International Nuclear Information System (INIS)

    1987-01-01

    This report covers the third quarter of calendar year 1987. The NRC licensing activity during the period of this report included the issuance of a full-power license for Beaver Valley 2 on August 14, 1987, and operating license restricted to five percent power for South Texas Unit 1 on August 21, 1987. Additional licensing delay for Shoreham is projected due to complex litigation. Also, licensing delay may occur for Comanche Peak Unit 1, because the duration of the hearing is uncertain. Although a license authorizing fuel loading and precriticality testing for Seabrook Unit 1 has been issued, there is a projected delay for low-power licensing. Full-power licensing for Seabrook Unit 1 will be delayed due to offsite emergency preparedness issues. The length of the delay is not known at this time. With the exception of Seabrook and Shoreham, regulatory delays in this report are not impacted by the schedules for resolving off-site emergency preparedness issues

  8. Demolition Notification for Quarter Ending March 30, 2014

    Energy Technology Data Exchange (ETDEWEB)

    Juarez, Catherine L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-06

    The National Nuclear Administration (NNSA) and Los Alamos National Security, LLC (LANS), (collectively the Permittees) are submitting notice of demolition activities for quarter ending March 30, 2014 in accordance with Permit Section 1.17.2 of the Los Alamos National Laboratory (LANL) Hazardous Waste Facility Permit to the New Mexico Environment Department Hazardous Waste Bureau (NMED_HWB).

  9. The LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2003-01-01

    The availability of isotope grade, Highly Enriched Uranium (HEU), from the United States for use in the manufacture of targets for molybdenum-99 production in AECL's NRU research reactor has been a key factor to enable MDS Nordion to develop a reliable, secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets is a proven and established method that has reliably produced medical isotopes for several decades. The HEU process provides predictable, consistent yields for our high-volume, molybdenum-99 production. Other medical isotopes such as I-131 and Xe-133, which play an important role in nuclear medicine applications, are also produced from irradiated HEU targets as a by-product of the molybdenum-99 process. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the commissioning of two MAPLE reactors and an associated isotope processing facility (the New Processing Facility). The new MAPLE facilities, which will be dedicated exclusively to medical isotope production, will provide an essential contribution to a secure, robust global healthcare system. Design and construction of these facilities has been based on a life cycle management philosophy for the isotope production process. This includes target irradiation, isotope extraction and waste management. The MAPLE reactors will operate with Low Enriched Uranium (LEU) fuel, a significant contribution to the objectives of the RERTR program. The design of the isotope production process in the MAPLE facilities is based on an established process - extraction of isotopes from HEU target material. This is a proven technology that has been demonstrated over more than three decades of operation. However, in support of the RERTR program and in compliance with U.S. legislation, MDS Nordion has undertaken a LEU Target Development and Conversion Program for the MAPLE facilities. This paper will provide an

  10. Archives: South African Crime Quarterly

    African Journals Online (AJOL)

    Items 1 - 29 of 29 ... Archives: South African Crime Quarterly. Journal Home > Archives: South African Crime Quarterly. Log in or Register to get access to full text downloads. Username, Password, Remember me, or Register · Journal Home · ABOUT THIS JOURNAL · Advanced Search · Current Issue · Archives. 1 - 29 of 29 ...

  11. Ethology in animal quarters.

    Science.gov (United States)

    Meyerson, B J

    1986-01-01

    This contribution will be concerned with the interaction between environment, adaptability optimization and behaviour. Animal laboratory experiments demand repeated measurements under identical environmental conditions. This is a prerequisite for the conventional statistical methodology used in order to clarify causal relationships involved in various biological functions. The understanding of biological functions is a necessary fundament for knowledge to prevent illness and to achieve a palliative or specific therapy. It is reasonable to assume that the routines in the quarters are very artificial, considering an animal's normal living conditions. The experimental situation as well as animal maintenance involves a process of adaptation. Adaptability depends on type of animal, degree of domestification etc. However, even with respect to choice of suitable species, strain and genetic manipulation, the process of adaptation becomes an important variable for ethical and practical points of view. The more emphasis on constancy, the more do we run the risk of increasing the span between normal and laboratory conditions and subsequently increase the factor and problem of adaptation. This vicious circle should be broken rather by finding optimal conditions than by a middle course determined by experimental requirements, economical frames and general notions about what may be good for the animal. Optimization must involve an understanding of how the experiment and the way of maintenance of the animal in the animal quarters influence adaptability. This understanding requires a systematic exploring of what physio-chemical and psychological factors are of importance. We will probably never be able to control the variability in the degree of adaptation.(ABSTRACT TRUNCATED AT 250 WORDS)

  12. US Neutron Facility Development in the Last Half-Century: A Cautionary Tale

    Science.gov (United States)

    Rush, John J.

    2015-06-01

    Large multi-user facilities serve many thousands of researchers in fields from particle physics to fundamental biology. The great expense—up to billions of current-day dollars—and the complexity of such facilities required access to extensive engineering and research infrastructures, most often found at national laboratories and the largest research universities. Although the development of such facilities has been largely successful and the research results unique and often spectacular, the processes for choosing, funding, and locating them were complex and not always productive. In this review, I describe the troubled efforts over the past fifty years to develop neutron research facilities in the United States. During this period, the US has moved from a preeminent position in neutron-based science to a lesser status with respect to Europe. Several major US centers of excellence have been shut down and replaced with more focused capabilities. I compare the US efforts in neutron facilities with parallel developments in Europe and Asia, discuss the reasons for this state of affairs, and make some suggestions to help prevent similar consequences in the future.

  13. Safety report content and development for test loop facility on MARIA reactor

    International Nuclear Information System (INIS)

    Konechko, A.; Shumskij, A.M.; Mikul'ahin, V.E.

    1982-01-01

    A 600 kW test loop facility for investigatin.o safety problems is realized on MARIA reactor in Poland together with USSR organizations. Safety reports have been developed in two steps at the designstage. The 1st report being essentially a preliminary safety analysis was developed within the scope of the feasibility study. At the engineering design stage the preliminary test loop facility safety report had been prepared considering measures excluding the possibility of the MARIA reactor damage. The test loop facility safety report is fulfilled for normal, transient and emergency operation regimes. Separate safety basing for each group of experiments will be prepared. The report presents the test loop facility safety criteria coordinated by the nuclear safety comission. They contains the preliminary reports on the test loop facility safety. At the final stage of construction and at thecommitioning stage the start-up safety report will be developed which after required correction and adding up the putting into operation data will turn into operation safety report [ru

  14. Safeguards systems analysis research and development and the practice of safeguards at DOE facilities

    International Nuclear Information System (INIS)

    Zack, N.R.; Thomas, K.E.; Markin, J.T.; Tape, J.W.

    1991-01-01

    Los Alamos Safeguards Systems Group personnel interact with Department of Energy (DOE) nuclear materials processing facilities in a number of ways. Among them are training courses, formal technical assistance such as developing information management or data analysis software, and informal ad hoc assistance especially in reviewing and commenting on existing facility safeguards technology and procedures. These activities are supported by the DOE Office of Safeguards and Security, DOE Operations Offices, and contractor organizations. Because of the relationships with the Operations Office and facility personnel, the Safeguards Systems Group research and development (R and D) staff have developed an understanding of the needs of the entire complex. Improved safeguards are needed in areas such as materials control activities, accountability procedures and techniques, systems analysis and evaluation methods, and material handling procedures. This paper surveys the generic needs for efficient and cost effective enhancements in safeguards technologies and procedures at DOE facilities, identifies areas where existing safeguards R and D products are being applied or could be applied, and sets a direction for future systems analysis R and D to address practical facility safeguards needs

  15. Development of an integrated facility for processing transuranium solid wastes at the Savannah River Plant

    International Nuclear Information System (INIS)

    Boersma, M.D.; Hootman, H.E.; Permar, P.H.

    1978-01-01

    An integrated facility is being designed for processing solid wastes contaminated with long-lived alpha emitting (TRU) nuclides; this waste has been stored retrievably at the Savannah River Plant since 1965. The stored waste, having a volume of 10 4 m 3 and containing 3x10 5 Ci of transuranics, consists of both mixed combustible trash and failed and obsolete equipment primarily from transuranic production and associated laboratory operations. The facility for processing solid transuranic waste will consist of five processing modules: 1) unpackaging, sorting, and assaying; 2) treatment of combustibles by controlled air incineration; 3) size reduction of noncombustibles by plasma-arc cutting followed by decontamination by electropolishing; 4) fixation of the processed waste in cement; and 5) packaging for shipment to a federal repository. The facility is projected for construction in the mid-1980's. Pilot facilities, sized to manage currently generated wastes, will also demonstrate the key process steps of incineration of combustibles and size reduction/decontamination of noncombustibles; these facilities are projected for 1980-81. Development programs leading to these extensive new facilities are described

  16. Development of an integrated facility for processing TRU solid wastes at the Savannah River Plant

    International Nuclear Information System (INIS)

    Boersma, M.D.; Hootman, H.E.; Permar, P.H.

    1977-01-01

    An integrated facility is being designed for processing solid wastes contaminated with long-lived alpha emitting (TRU) nuclides; this waste has been stored retrievably at the Savannah River Plant since 1965. The stored waste, having a volume of 10 4 m 3 and containing 3 x 10 5 Ci of transuranics, consists of both mixed combustible trash and failed and obsolete equipment primarily from transuranic production and associated laboratory operations. The facility for processing solid transuranic waste will consist of five processing modules: (1) unpackaging, sorting, and assaying; (2) treatment of combustibles by controlled air incineration; (3) size reduction of noncombustibles by plasma-arc cutting followed by decontamination by electropolishing; (4) fixation of the processed waste in cement; and (5) packaging for shipment to a federal repository. The facility is projected for construction in the mid-1980's. Pilot facilities, sized to manage currently generated wastes, will also demonstrate the key process steps of incineration of combustibles and size reduction/decontamination of noncombustibles; these facilities are projected for 1980-81. Development programs leading to these extensive new facilities are described

  17. Development and use of a master health facility list: Haiti's experience during the 2010 earthquake response

    Science.gov (United States)

    Rose-Wood, Alyson; Heard, Nathan; Thermidor, Roody; Chan, Jessica; Joseph, Fanor; Lerebours, Gerald; Zugaldia, Antonio; Konkel, Kimberly; Edwards, Michael; Lang, Bill; Torres, Carmen-Rosa

    2014-01-01

    ABSTRACT Master health facility lists (MHFLs) are gaining attention as a standards-based means to uniquely identify health facilities and to link facility-level data. The ability to reliably communicate information about specific health facilities can support an array of health system functions, such as routine reporting and emergency response operations. MHFLs support the alignment of donor-supported health information systems with county-owned systems. Recent World Health Organization draft guidance promotes the utility of MHFLs and outlines a process for list development and governance. Although the potential benefits of MHFLs are numerous and may seem obvious, there are few documented cases of MHFL construction and use. The international response to the 2010 Haiti earthquake provides an example of how governments, nongovernmental organizations, and others can collaborate within a framework of standards to build a more complete and accurate list of health facilities. Prior to the earthquake, the Haitian Ministry of Health (Ministère de la Santé Publique et de la Population [MSPP]) maintained a list of public-sector health facilities but lacked information on privately managed facilities. Following the earthquake, the MSPP worked with a multinational group to expand the completeness and accuracy of the list of health facilities, including information on post-quake operational status. This list later proved useful in the response to the cholera epidemic and is now incorporated into the MSPP's routine health information system. Haiti's experience demonstrates the utility of MHFL formation and use in crisis as well as in the routine function of the health information system. PMID:25276595

  18. DOE performance indicators for 2nd quarter CY 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    The Department of Energy (DOE) has established a Department-wide Performance Indicator (PI) Program for trending and analysis of operational data as directed by DOE Order 5480.26. The PI Program was established to provide a means for monitoring the environment, safety, and health (ES&H) performance of the DOE at the Secretary and other management levels. This is the tenth in a series of quarterly reports generated for the Department of Energy Idaho Operations Office (DOE-ID) by EG&G Idaho, Inc. to meet the requirements of the PI Program as directed by the DOE Standard (DOE-STD-1048-92). The information in this tenth quarterly report, while contributing to a historical database for supporting future trending analysis, does not at this time provide a sound basis for developing trend-related conclusions. In the future, it is expected that trending and analysis of operational data will enhance the safety culture in both DOE and contractor organizations by providing an early warning of deteriorating environment, safety, and health conditions. DOE-STD-1048-92 identifies four general areas of PIs. They are: Personnel Safety, Operational Incidents, Environment, and Management. These four areas have been subdivided into 26 performance indicators. Approximately 115 performance indicator control and distribution charts comprise the body of this report. A brief summary of PIs contained in each of these general areas is provided. The four EG&G facilities whose performance is charted herein are as follows: (1) The Advanced Test Reactor (ATR), (2) The Radioactive Waste Management Complex (RWMC), (3) The Waste Experimental Reduction Facility (WERF), and (4) The Test Reactor Area (TRA) Hot Cells.

  19. Supplement to the Central Bank of Malta Quarterly Review : 2013 : 2

    OpenAIRE

    2013-01-01

    The supplement includes information on developments in GDP in the second quarter of the year, based on data which became available after the Review had been prepared. These data show that the economy expanded at an annual rate of 1.7% in the second quarter, after having grown by a revised 1.8% in the first quarter.

  20. [Development of a ground-based experimental facility for space waste material processing with microorganism].

    Science.gov (United States)

    Ai, Wei-dang; Guo, Shuang-sheng; Wang, Xiao-xia; Fu, Lan

    2004-06-01

    To develop a ground-based experimental facility for microorganism waste processing, which will be used to recover nutrient from plant inedible biomass essential for growth and development of plants. After technical parameters and performance requirements were defined, planning demonstration, drawing design, fabrication, debug and plant inedible residue-biodegradation tests by microorganisms were conducted. The facility worked well, and the parameters, such as energy consumption, volume and weight, met the design requirement. The water-treated quality and the ability of treating plant residual by microorganism were better than the demands. The ground-based results demonstrated that total organic carbon (TOC) degradation above 92.1%, and chemical oxygen demand (COD) reduction over 95.5% could be maintained. The facility has reasonable technical indexes, and smooth and reliable performances. Its major working principle is suitable for the demand of space conditions. It is capable of being utilized for biodegradation of plant inedible biomass in space.

  1. Investigation of development and management of treatment planning systems for BNCT at foreign facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    A new computational dosimetry system for BNCT: JCDS is developed by JAERI in order to carry out BNCT with epithermal neutron beam at present. The development and management situation of computational dosimetry system, which are developed and are used in BNCT facilities in foreign countries, were investigated in order to accurately grasp functions necessary for preparation of the treatment planning and its future subjects. In present state, 'SERA', which are developed by Idaho National Engineering and Environmental Laboratory (INEEL), is used in many BNCT facilities. Followings are necessary for development and management of the treatment planning system. (1) Reliability confirmation of system performance by verification as comparison examination of calculated value with actual experimental measured value. (2) Confirmation systems such as periodic maintenance for retention of the system quality. (3) The improvement system, which always considered relative merits and demerits with other computational dosimetry system. (4) The development of integrated system with patient setting. (author)

  2. Energy Programs at the Johns Hopkins University Applied Physics Laboratory, Quarterly Report, January-March 1980

    Energy Technology Data Exchange (ETDEWEB)

    Entingh, Daniel J.

    1980-03-01

    The Johns Hopkins University Applied Physics Laboratory, under contracts with several agencies of the federal government and an agency of the State of Maryland, is engaged in developing energy resources, utilization concepts, and monitoring and storage methods. This Quarterly Report summarizes the work on the various tasks as of 31 March 1980. The Energy Quarterly Report is divided into four sections. The first, Geothermal Energy Development Planning and Technical Assistance, supported by the Department of Energy/Division of Geothermal Energy (DOE/DGE), contains reports on the progress of geothermal-related tasks on which effort was concentrated during the quarter. The second section, Operational Research, Hydroelectric Power Development, supported by the Department of Energy/Resource Applications (DOE/DGE), contains reports on small-scale hydroelectric investigations in the southeastern states. The third section, Seismotectonic Investigation, supported by the Reactor Safety Research Division of the Nuclear Regulatory Commission, reports on a neotectonic investigation in Connecticut. The fourth section, Energy Conversion and Storage Techniques, contains two articles, the first on OTEC core unit testing supported by the Department of Energy/Division of Central Solar Technology (DOE/CST), and the second on an analysis of the Community Annual Storage Energy System at the U.S. Naval Air Station, Norfolk, Va. This work is supported by the Department of Energy and the Department of Defense, Naval Facilities Engineering Command/Atlantic Division.

  3. Energy Programs at the Johns Hopkins University Applied Physics Laboratory, Quarterly Report, April-June 1980

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

    The Johns Hopkins University Applied Physics Laboratory, under contracts with several agencies of the federal government and an agency of the State of Maryland, is engaged in developing energy resources, utilization concepts, and monitoring and storage methods. This Quarterly Report summarizes the work on the various tasks as of 30 June 1980. The Energy Quarterly Report is divided into three sections. The first, Geothermal Energy Development Planning and Technical Assistance, supported by the Department of Energy/Division of Geothermal Energy (DOE/DGE), contains reports on the progress of geothermal-related tasks on which effort was concentrated during the quarter. The second section, Operational Research, Hydroelectric Power Development, supported by the Department of Energy/Resource Applications (DOE/RA), contains reports on small-scale hydroelectric investigations in the southeastern states. The third section, Energy Conversion and Storage Techniques, contains three articles. The first is on data analysis of OTEC core unit condenser tests, and is supported by the Department of Energy/Division of Central Solar Technology (DOE/CST). The second is on the current status of the Community Annual Storage Energy System at the U.S. Naval Air Station, Norfolk, Va., and is supported by the Department of Energy and the Department of Defense, Naval Facilities Engineering Command/Atlantic Division. The third is on utilization of landfill methane and is supported by Argonne National Laboratory.

  4. Thermal-hydraulic tests with out-of-pile test facility for BOCA development

    International Nuclear Information System (INIS)

    Kitagishi, Shigeru; Aoyama, Masashi; Tobita, Masahiro; Inaba, Yoshitomo; Yamaura, Takayuki

    2012-01-01

    The fuel transient test facility was prepared for power ramping tests of light-water-reactor (LWR) fuels in the Japan Materials Testing Reactor (JMTR) under a contract project with the Nuclear Industrial Safety Agent (NISA) of the Ministry of Economy, Trade and Industry (METI). It is necessary to develop high accuracy analysis procedure for power ramping tests after restart of the JMTR. The out-of-pile test facility to simulate thermal-hydraulic conditions of the fuel transient test facility was therefore developed. Applicability of the analysis code ACE-3D was examined for thermal-hydraulic analysis of power ramping tests for 10x10 BWR fuels by the fuel transient test facility. As the results, the calculated temperature was 304°C in comparison with measured value of 304.9-317.4°C in the condition of 600 W/cm. There is a bright prospect of high accuracy power ramping tests by the fuel transient test facility in JMTR. (author)

  5. Development of cancer therapy facility of HANARO and medical research in BNCT; development of the technique for boron concentration analysis

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hee Dong; Byun, Soo Hyun; Sun, Gwang Min; Kim, Suk Kwon; Kim, In Jung; Park, Chang Su [Seoul National University, Seoul (Korea)

    2002-03-01

    Objective and Necessity of the Project- Development of a boron concentration analysis facility used for BNCT. - Development of the technique for boron concentration analysis. Contents and Scopes of the Project - Construction of the boron concentration analysis facility based on PGAA. Estimation of the neutron beam characteristics. -Establishment of the technique for the boron concentration analysis. - Estimation of the reliability for the boron analysis. Results of the Project -Installation of the boron concentration analysis facility at Hanaro. - Neutron beam characteristics are the sample position (neutron flux : 7.9 x 10{sup 7} n/cm{sup 2}s, Cd-ratio : 266) Technique for the boron concentration analysis. - Boron detection sensitivity and limit (detection sensitivity : 2, 131 cps/mg-B, detection limit : 67 ng for 10,000 sec). 63 refs., 37 figs., 13 tabs. (Author)

  6. Developing a user-perception assessment tool for health facilities in South Africa

    CSIR Research Space (South Africa)

    Saidi, M

    2007-06-01

    Full Text Available . The broader tool is envisaged to assess the performance of health facilities in areas of functionality, impact, and building durability and quality. The process will involve developing and testing the tool at a pilot hospital in the country...

  7. RAFT-HDA Chemistry - Conception, Development and Application of a Facile Tool for Precision Macromolecular Engineering

    OpenAIRE

    Inglis, Andrew

    2010-01-01

    The conceptualization, development and application of the herein named RAFT-HDA Chemistry is reported. This chemistry is presented as a facile conjugation method (falling within the field of click chemistry) whereby synthetic polymeric materials may be covalently linked to other species, including other polymers with high efficiency.

  8. Quarterly report on program cost and schedule: Fourth quarter FY 1988

    International Nuclear Information System (INIS)

    1988-01-01

    Major program milestones completed in the fourth quarter of FY 1988 include completed preliminary draft NWPAA Section 175 Impacts Report, completed Title I ESF design, completed site reclamation in Texas, distributed review draft of the Dry Cask Storage Study, completed draft and final FY 1990 OMB budget, issued FY 1987 Annual Report to Congress, issued four draft Environmental Field Activity Plans, issued draft Environmental Program Overview, and made grant payments to local governments under Section 116 of NWPA, as amended. Major accomplishments during the fourth quarter of FY 1988 are listed. The Water Appropriation Permit Application was filed with the Nevada State Engineer on July 21, 1988. Installation and checkout of the Prototype Engineered Barrier Test equipment in G-tunnel is continuing with an expected early September test initiation data. The Configuration Management Plan was sent to DOE/HQ for approval. The prototype facility for testing the horizontal waste package emplacement configuration was completed in the G-tunnel

  9. Guidelines for the development of natural phenomena hazards design criteria for surface facilities

    International Nuclear Information System (INIS)

    Nelson, T.A.; Hossain, Q.A.; Murray, R.C.

    1992-01-01

    This paper discusses the rationale behind the guidelines, criteria, and methodologies that are currently used for natural phenomena hazard design and evaluation of DOE nuclear and non-nuclear facilities. The bases for the performance goals and usage categories specified in UCRL-15910 are examined, and the sources of intentional conservatism in the analyses, design, and evaluation methods and criteria are identified. Outlines of recent developments/changes in DOE Orders related to Natural Phenomena hazard mitigation are also presented. Finally, the authors recommend the use of DOE methodologies as embodied in UCRL-15910 for design and evaluation of surface facilities of the high level nuclear waste repository site

  10. PRELIMINARY STUDY TO PRIMARY EDUCATION FACILITIES (A Comparison Study between Indonesia and Developed Countries

    Directory of Open Access Journals (Sweden)

    Lucy Yosita

    2006-01-01

    Full Text Available This writing is a preliminary study to condition of primary education facilities in Indonesia, and then comparing these with theories as well as various relevant cases aimed to know the problem more obviously. Basically, there is difference between primary education facilities in Indonesia with those in developed countries. Meanwhile on the other hand, the condition as well as the completion of education facility is actually as the main factor contributes to address the purpose of learning process. If building design, interior and also site plan were dynamic in form, space, colour and tools, those would be probably more stimulate activity and influence into the growth of students. However, lastly, it is still required further analysis, as an example analysis to student's behaviour in spaces of learning environment, more detail and within enough time, not only at indoor but also at outdoor.

  11. QUARTERLY PROGRESS REPORT JANUARY, FEBRUARY, MARCH, 1968 REACTOR FUELS AND MATERIALS DEVELOPMENT PROGRAMS FOR FUELS AND MATERIALS BRANCH OF USAEC DIVISION OF REACTOR DEVELOPMENT AND TECHNOLOGY

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, J. J.; de Halas, D. R.; Nightingale, R. E.; Worlton, D. C.

    1968-06-01

    Progress is reported in these areas: nuclear graphite; fuel development for gas-cooled reactors; HTGR graphite studies; nuclear ceramics; fast-reactor nitrides research; non-destructive testing; metallic fuels; basic swelling studies; ATR gas and water loop operation and maintenance; reactor fuels and materials; fast reactor dosimetry and damage analysis; and irradiation damage to reactor metals.

  12. Development of turbopump cavitation performance test facility and the test of inducer performance

    International Nuclear Information System (INIS)

    Sohn, Dong Kee; Kim, Chun Tak; Yoon, Min Soo; Cha, Bong Jun; Kim, Jin Han; Yang, Soo Seok

    2001-01-01

    A performance test facility for turbopump inducer cavitation was developed and the inducer cavitation performance tests were performed. Major components of the performance test facility are driving unit, test section, piping, water tank, and data acquisition and control system. The maximum of testing capability of this facility are as follows: flow rate - 30kg/s; pressure - 13 bar, rotational speed - 10,000rpm. This cavitation test facility is characterized by the booster pump installed at the outlet of the pump that extends the flow rate range, and by the pressure control system that makes the line pressure down to vapor pressure. The vacuum pump is used for removing the dissolved air in the water as well as the line pressure. Performance tests were carried out and preliminary data of test model inducer were obtained. The cavitation performance test and cavitation bubble flow visualization were also made. This facility is originally designed for turbopump inducer performance test and cavitation test. However it can be applied to the pump impeller performance test in the future with little modification

  13. Impact assessment of the forest fires on Oarai Research and Development Center Waste Treatment Facility

    International Nuclear Information System (INIS)

    Shimomura, Yusuke; Kitamura, Ryoichi; Hanari, Akira; Sato, Isamu

    2016-03-01

    In response to new standards for regulating waste treatment facility ('new regulatory standards'; December 18, 2013 enforcement), it was carried out impact assessment of forest fires on the Waste Treatment Facility existed in Oarai Research and Development Center of Japan Atomic Energy Agency. At first, a fire spread scenario of forest fires was assumed. The intensity of forest fires was evaluated from field surveys, forest fire evaluation models and so on. As models of forest fire intensity evaluation, Rothermel Model and Canadian Forest Fire Behavior Prediction (FBP) System were used. Impact assessment of radiant heat to the facility was carried out, and temperature change of outer walls for the assumed forest fires was estimated. The outer wall temperature of facility was estimated around 160degC at the maximum, it was revealed that it doesn't reach allowable temperature limit. Consequently, it doesn't influence the strength of concrete. In addition, a probability of fire breach was estimated to be about 20%. This report illustrates an example of evaluation of forest fires for the new regulatory standards through impact assessment of the forest fires on the Waste Treatment Facility. (author)

  14. The development of hydro power in Poland. The most important hydro engineering facilities

    Directory of Open Access Journals (Sweden)

    Wojciech Majewski

    2013-09-01

    Full Text Available Poland is a country with scarce water resources, which places it in this regard at the end of the list of European countries. Also the capacity of retention reservoirs in Poland is very small compared to other neighbouring European countries, and does not exceed 6% of the average annual runoff from its territory. This results in the low hydropower potential. What is more, this low potential is used to a limited extent only, in contrast to most European countries. The first hydropower facilities were built in Poland in the interwar period. The development of hydropower facilities intensified in Poland after World War II. They were the low and high head plants, but also facilities with equilibrium reservoirs and reversible units. After World War II, in Poland, within its new borders, there were a lot of small hydropower plants, which initially were ignored by utility companies and were devastated. Later, they were gradually activated. The construction of new facilities, modernization of existing ones, as well as reconstruction of those degraded, are often obstructed by significant ecological restrictions. This paper presents these processes and describes the major hydropower facilities in Poland.

  15. Joint Force Quarterly. Issue 41, 2nd Quarter, April 2006

    Science.gov (United States)

    2006-04-01

    operating in the Pacific, Exercise Panamax ’05 (4th Combat Camera Squadron/Rick Sforza); Marines securing area along Amazon River , Exercise UNITAS ’04...companies participated, a million more people would be actively looking for threats. Aguas de Amazonas , a subsidiary of Suez Environnement, a...9 Richard B. Myers, “A Word from the Chair- man,” Joint Force Quarterly 37 (2d Quarter 2005), 5. 10 Wald, 26. 11 “Suez—Aguas de Amazonas Water for

  16. Design, development, manufacturing, testing and commissioning of instrumentation for critical facility

    International Nuclear Information System (INIS)

    Dutta, P.K.; Gadgil, Kautubh; Punekar, Parag; Ramkumar, N.; Gohel, Nilesh; Darbhe, M.D.; Bharathan, R.; Bharadhwaj, G.

    2006-01-01

    The Critical Facility (CF) is a low power research reactor. Neutronic and Process Instrumentation are important systems those ensure safety and control of the reactor. The Control and Instrumentation systems for the Critical facility have been designed, developed and commissioned by RRMD. Most of the nuclear instrumentation used here is originally designed and developed jointly by Electronics Division and RRMD during ZAC project for conversion of the earlier vacuum tube based instrumentation to the solid state circuits during 1984-85 for Zerlina, Apsara and Cirus and are in operation at Cirus and Apsara since commissioning in 1984-85. The Process Instrumentation is provided for monitoring important process parameters such as level, flow, temperature and pressure and generating trips, alarms and interlocks necessary for smooth operation of the systems and safety of personnel and equipment. The paper will provide technical information on the reactor instrumentation for both nuclear and process systems, used in Critical Facility, the associated trip and alarms logics, and their integration into the reactor monitoring control and protection system, information systems developed for Critical Facility. (author)

  17. Short-term energy outlook: Quarterly projections. Second quarter 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-02

    The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). An annual supplement analyzes the performance of previous forecasts, compares recent projections with those of other forecasting services, and discusses current topics related to the short-term energy markets. (See Short-Term Energy Outlook Annual Supplement, DOE/EIA-0202.) The forecast period for this issue of the Outlook extends from the second quarter of 1995 through the fourth quarter of 1996. Values for the first quarter of 1995, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in the Weekly Petroleum Status Report) or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data, compiled into the second quarter 1995 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS database is archived quarterly and is available from the National Technical Information Service.

  18. Waste Facilities

    Data.gov (United States)

    Vermont Center for Geographic Information — This dataset was developed from the Vermont DEC's list of certified solid waste facilities. It includes facility name, contact information, and the materials...

  19. Use of Pilot Plants for Developing Used Nuclear Fuel Recycling Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, Chris; Arm, Stuart [EnergySolutions LLC (United States); Banfield, Zara; Jeapes, Andrew; Taylor, Richard [National Nuclear Laboratory (United Kingdom)

    2009-06-15

    EnergySolutions and its teaming partners are working with the US Department of Energy (DOE) to develop processes, equipment and facilities for recycling used nuclear fuel (UNF). Recycling significantly reduces the volume of wastes that ultimately will be consigned to the National Geologic Repository, enables the re-use in new fuel of the valuable uranium and plutonium in the UNF, and allows the long-lived minor actinides to be treated separately so they do not become long term heat emitters in the Repository. A major requirement of any new UNF recycling facility is that pure plutonium is not separated anywhere in the process, so as to reduce the nuclear proliferation attractiveness of the facility. EnergySolutions and its team partner the UK National Nuclear Laboratory (NNL) have developed the NUEX process to achieve this and to handle appropriately the treatment of other species such as krypton, tritium, neptunium and technetium. NUEX is based on existing successful commercial UNF recycling processes deployed in the UK, France and imminently in Japan, but with a range of modifications to the flowsheet to keep some uranium with the plutonium at all times and to minimize aerial and liquid radioactive discharges. NNL's long-term experience in developing the recycling and associated facilities at the Sellafield site in the UK, and its current duties to support technically the operation of the Thermal Oxide Reprocessing Plant (THORP) at Sellafield provides essential input to the design of the US NUEX-based facility. Development work for THORP and other first-of-kind nuclear plants employed miniature scale fully radioactive through large scale inactive pilot plants. The sequence of development work that we have found most successful is to (i) perform initial process development at small (typically 1/5000) scale in gloveboxes using trace active materials, (ii) demonstrate the processes at the same small scale with actual irradiated fuel in hot cells and (iii

  20. Application of demography to energy facility development projects. Working Paper No. 39

    International Nuclear Information System (INIS)

    Krannich, R.S.; Stanfield, G.G.

    1977-01-01

    The emergence of concern regarding socioeconomic consequences of large-scale development projects has resulted in a growing literature directed as estimating the types and levels of various impact dimensions which can be expected to result in human communities experiencing such development. Among these dimensions, a focus on population change has been prevalent. Accurate demographic predictions may be viewed as critical for the adequate comprehension of and preparation for impacts deriving from projects such as energy facility developments. Unfortunately, the state of the art in projecting demographic consequences of energy projects has been generally inadequate. Several of the more influential prior methods for estimating local demographic effects of developing energy facilities are critiqued, although their specific prediction figures are not summarized. The studies reviewed were found to be of dubious practical utility, probably due in part to the failure of basic demography to provide a base of support for applied demographic research. This report sets forth recommendations for the development of a theoretical perspective which would more adequately serve the needs of practitioners attempting to predict local demographic effects of energy facility development

  1. Neutron research and facility development at the Oak Ridge Electron Linear Accelerator 1970 to 1995

    Energy Technology Data Exchange (ETDEWEB)

    Peelle, R.W.; Harvey, J.A.; Maienschein, F.C.; Weston, L.W.; Olsen, D.K.; Larson, D.C.; Macklin, R.L.

    1982-07-01

    This report reviews the accomplishments of the first decade of operation of the Oak Ridge Electron Linear Accelerator (ORELA) and discusses the plans for the facility in the coming decade. Motivations for scientific and applied research during the next decade are included. In addition, ORELA is compared with competing facilities, and prospects for ORELA's improvement and even replacement are reported. Development efforts for the next few years are outlined that are consistent with the anticipated research goals. Recommendations for hardware development include improving the electron injection system to give much larger short-pulse currents on a reliable basis, constructing an Electron Beam Injector Laboratory to help make this improvement possible, continuing a study of possibly replacing the electron accelerator with a proton machine, and replacing or upgrading the facility's data-acquistion and immediate-analysis computer systems. Increased operating time and more involvement of nuclear theorists are recommended, and an effective staff size for optimum use of this unique facility is discussed. A bibliography of all ORELA-related publications is included.

  2. Common Data Acquisition Systems (DAS) Software Development for Rocket Propulsion Test (RPT) Test Facilities

    Science.gov (United States)

    Hebert, Phillip W., Sr.; Davis, Dawn M.; Turowski, Mark P.; Holladay, Wendy T.; Hughes, Mark S.

    2012-01-01

    The advent of the commercial space launch industry and NASA's more recent resumption of operation of Stennis Space Center's large test facilities after thirty years of contractor control resulted in a need for a non-proprietary data acquisition systems (DAS) software to support government and commercial testing. The software is designed for modularity and adaptability to minimize the software development effort for current and future data systems. An additional benefit of the software's architecture is its ability to easily migrate to other testing facilities thus providing future commonality across Stennis. Adapting the software to other Rocket Propulsion Test (RPT) Centers such as MSFC, White Sands, and Plumbrook Station would provide additional commonality and help reduce testing costs for NASA. Ultimately, the software provides the government with unlimited rights and guarantees privacy of data to commercial entities. The project engaged all RPT Centers and NASA's Independent Verification & Validation facility to enhance product quality. The design consists of a translation layer which provides the transparency of the software application layers to underlying hardware regardless of test facility location and a flexible and easily accessible database. This presentation addresses system technical design, issues encountered, and the status of Stennis development and deployment.

  3. Development of operational criteria for the interim spent fuel storage facility

    International Nuclear Information System (INIS)

    Kim, M. H.; Kim, J. C.; Kim, D. K.; Cho, D. K.; Bae, K. M.

    1997-03-01

    The final objective is to develop the technical criteria for the facility operation of the interim spent fuel storage facility. For this purpose, elementary technical issues are evaluated for the wet storage of spent fuels and status of operation in foreign counties are examined. Urgent objective of this study is to provide technical back data for the development of operational criteria. For the back data for the development of operational criteria, domestic technical data for the wet storages are collected as well as standards and criteria related to the spent fuel storage. Operational stutus of spent fuel storages in foreign countries CLAB in Sweden and MRS in the United States are studied. Dry storage concept is also studied in order to find the characteristics of wet storage concept. Also basic technical issues are defined and studied in order to build a draft of operational criteria

  4. NASA Data Acquisition System Software Development for Rocket Propulsion Test Facilities

    Science.gov (United States)

    Herbert, Phillip W., Sr.; Elliot, Alex C.; Graves, Andrew R.

    2015-01-01

    Current NASA propulsion test facilities include Stennis Space Center in Mississippi, Marshall Space Flight Center in Alabama, Plum Brook Station in Ohio, and White Sands Test Facility in New Mexico. Within and across these centers, a diverse set of data acquisition systems exist with different hardware and software platforms. The NASA Data Acquisition System (NDAS) is a software suite designed to operate and control many critical aspects of rocket engine testing. The software suite combines real-time data visualization, data recording to a variety formats, short-term and long-term acquisition system calibration capabilities, test stand configuration control, and a variety of data post-processing capabilities. Additionally, data stream conversion functions exist to translate test facility data streams to and from downstream systems, including engine customer systems. The primary design goals for NDAS are flexibility, extensibility, and modularity. Providing a common user interface for a variety of hardware platforms helps drive consistency and error reduction during testing. In addition, with an understanding that test facilities have different requirements and setups, the software is designed to be modular. One engine program may require real-time displays and data recording; others may require more complex data stream conversion, measurement filtering, or test stand configuration management. The NDAS suite allows test facilities to choose which components to use based on their specific needs. The NDAS code is primarily written in LabVIEW, a graphical, data-flow driven language. Although LabVIEW is a general-purpose programming language; large-scale software development in the language is relatively rare compared to more commonly used languages. The NDAS software suite also makes extensive use of a new, advanced development framework called the Actor Framework. The Actor Framework provides a level of code reuse and extensibility that has previously been difficult

  5. EMSL Quarterly Highlights Report Second Quarter, Fiscal Year 2010 (January 1, 2010 through March 31, 2010)

    Energy Technology Data Exchange (ETDEWEB)

    West, Staci A.; Showalter, Mary Ann; Manke, Kristin L.; Carper, Ross R.; Wiley, Julie G.; Beckman, Mary T.

    2010-04-20

    The Environmental Molecular Sciences Laboratory (EMSL) is a U.S. Department of Energy (DOE) national scientific user facility located at Pacific Northwest National Laboratory (PNNL) in Richland, Washington. EMSL is operated by PNNL for the DOE-Office of Biological and Environmental Research. At one location, EMSL offers a comprehensive array of leading-edge resources and expertise. Access to the instrumentation and expertise is obtained on a peer-reviewed proposal basis. Staff members work with researchers to expedite access to these capabilities. The "EMSL Quarterly Highlights Report" documents current research and activities of EMSL staff and users.

  6. Experimental facility for development of high-temperature reactor technology: instrumentation needs and challenges - 15066

    International Nuclear Information System (INIS)

    Sabharwall, P.; O'Brien, J.E.; Yoon, S.J.; Sun, X.

    2015-01-01

    A high-temperature, multi-fluid, multi-loop test facility is under development at the Idaho National Laboratory for support of thermal hydraulic, materials, and system integration research for high-temperature reactors. The experimental facility includes a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The 3 loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). Research topics to be addressed include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuits heat exchangers (PCHEs) at prototypical operating conditions. Each loop will also include an interchangeable high-temperature test section that can be customized to address specific research issues associated with each working fluid. This paper also discusses needs and challenges associated with advanced instrumentation for the multi-loop facility, which could be further applied to advanced high-temperature reactors. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integrated System Test (ARTIST) facility. A preliminary design configuration of the ARTIST facility will be presented with the required design and operating characteristics of the various components. The initial configuration will include a high-temperature (750 C. degrees), high-pressure (7 MPa) helium loop thermally integrated with a molten fluoride salt (KF-ZrF 4 ) flow loop operating at low pressure (0.2 MPa), at a temperature of ∼ 450 C. degrees. The salt loop will be thermally integrated with the steam/water loop operating at PWR conditions. Experiment design challenges include identifying suitable materials and components that will withstand the required loop operating conditions. The instrumentation needs to be highly accurate (negligible drift) in measuring operational data for extended periods of times, as data collected will be

  7. Experimental facility for development of high-temperature reactor technology: instrumentation needs and challenges

    Directory of Open Access Journals (Sweden)

    Sabharwall Piyush

    2015-01-01

    Full Text Available A high-temperature, multi-fluid, multi-loop test facility is under development at the Idaho National Laboratory for support of thermal hydraulic materials, and system integration research for high-temperature reactors. The experimental facility includes a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The three loops will be thermally coupled through an intermediate heat exchanger (IHX and a secondary heat exchanger (SHX. Research topics to be addressed include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuit heat exchangers (PCHEs at prototypical operating conditions. Each loop will also include an interchangeable high-temperature test section that can be customized to address specific research issues associated with each working fluid. This paper also discusses needs and challenges associated with advanced instrumentation for the multi-loop facility, which could be further applied to advanced high-temperature reactors. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integral System Test (ARTIST facility. A preliminary design configuration of the ARTIST facility will be presented with the required design and operating characteristics of the various components. The initial configuration will include a high-temperature (750 °C, high-pressure (7 MPa helium loop thermally integrated with a molten fluoride salt (KF-ZrF4 flow loop operating at low pressure (0.2 MPa, at a temperature of ∼450 °C. The salt loop will be thermally integrated with the steam/water loop operating at PWR conditions. Experiment design challenges include identifying suitable materials and components that will withstand the required loop operating conditions. The instrumentation needs to be highly accurate (negligible drift in measuring operational data for extended periods of times, as data collected will be

  8. Development of decommissioning management system for nuclear fuel cycle facilities (DECMAN)

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichirou; Ishijima, Noboru; Tanimoto, Ken-ichi [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-04-01

    In making a plan of decommissioning of nuclear fuel facilities, it is important to optimize the plan on the standpoint of a few viewpoints, that is, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost (they are called evaluation indexes). In the midst of decommissioning, the decommissioning plan would be modified suitably to optimize the evaluation indexes adjusting to progress of the decommissioning. The decommissioning management code (DECMAN), that is support system on computer, has been developed to assist the decommissioning planning. The system calculates the evaluation indexes quantitatively. The system consists of three fundamental codes, facility information database code, technical know-how database code and index evaluation code, they are composed using Oracle' database and 'G2' expert system. The functions of the system are as follows. (1) Facility information database code. Information of decommissioning facility and its rooms, machines and pipes in the code. (2) Technical know-how database code. Technical Information of tools to use in decommissioning work, cutting, dose measure, and decontamination are there. (3) Index evaluation code. User build decommissioning program using above two database codes. The code evaluates five indexes, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost, on planning decommissioning program. Results of calculation are shown in table, chart, and etc. (author)

  9. Hydrogeologic investigation of the Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama

    Energy Technology Data Exchange (ETDEWEB)

    Gardner, F.G.; Kearl, P.M.; Mumby, M.E.; Rogers, S.

    1996-09-01

    This document describes the geology and hydrogeology at the former Advanced Coal Liquefaction Research and Development (ACLR&D) facility in Wilsonville, Alabama. The work was conducted by personnel from the Oak Ridge National Laboratory Grand Junction office (ORNL/GJ) for the U.S. Department of Energy (DOE) Pittsburgh Energy Technology Center (PETC). Characterization information was requested by PETC to provide baseline environmental information for use in evaluating needs and in subsequent decision-making for further actions associated with the closeout of facility operations. The hydrogeologic conceptual model presented in this report provides significant insight regarding the potential for contaminant migration from the ACLR&D facility and may be useful during other characterization work in the region. The ACLR&D facility is no longer operational and has been dismantled. The site was characterized in three phases: the first two phases were an environmental assessment study and a sod sampling study (APCO 1991) and the third phase the hydraulic assessment. Currently, a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) remedial investigation (RI) to address the presence of contaminants on the site is underway and will be documented in an RI report. This technical memorandum addresses the hydrogeologic model only.

  10. Development of probabilistic safety assessment method for mixed oxide fuel fabrication facilities

    International Nuclear Information System (INIS)

    Tamaki, Hitoshi; Yoshida, Kazuo; Watanabe, Norio; Muramatsu, Ken

    2006-01-01

    A Probabilistic Safety Assessment (PSA) procedure for Mixed Oxide (MOX) fuel fabrication facilities was developed. The procedure is a 'two-part five-step' approach which takes characteristics of MOX fuel fabrication facilities into consideration. In the first part, so-called preliminary PSA, the hazard analysis approach was applied, which consists of two analysis steps: Functional Failure Modes and Effects Analysis (FFMEA) and Risk Matrix Analysis. The FFMEA analyzes a variety of functions of equipment composing the facility to identify potential abnormal events exhaustively. In the Risk Matrix Analysis, these potential events are screened to select abnormal events as candidates to be analyzed in the second part, using two-dimensional matrix based on the likelihood evaluated by probabilistic index method and maximum unmitigated radioactive release calculated by the Five-Factor Formula. For the selected abnormal events, in the second part, so-called detailed PSA, accident sequences, their occurrence frequencies and consequences are analyzed. These three analysis steps correspond to PSA procedure for nuclear power plant. The applicability of the PSA procedure was demonstrated through the trial application to model plant of MOX fuel fabrication facility. (author)

  11. Short-term energy outlook: Quarterly projections, fourth quarter 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-14

    The Energy Information Administration (EIA) prepares quarterly short-term energy supply, demand, and price projections for printed publication in January, April, July, and October in the Short-Term Energy Outlook. The details of these projections, as well as monthly updates on or about the 6th of each interim month, are available on the internet at: www.eia.doe.gov/emeu/steo/pub/contents.html. The forecast period for this issue of the Outlook extends from the fourth quarter of 1997 through the fourth quarter of 1998. Values for the fourth quarter of 1997, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in EIA`s Weekly Petroleum Status Report) or are calculated from model simulations that use the latest exogenous information available (for example, electricity sales and generation are simulated by using actual weather data). The historical energy data, compiled in the fourth quarter 1997 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. 19 tabs.

  12. 25 CFR 170.807 - What must BIA include when it develops an IRR Transportation Facilities Maintenance Management...

    Science.gov (United States)

    2010-04-01

    ... What must BIA include when it develops an IRR Transportation Facilities Maintenance Management System... 25 Indians 1 2010-04-01 2010-04-01 false What must BIA include when it develops an IRR Transportation Facilities Maintenance Management System? 170.807 Section 170.807 Indians BUREAU OF INDIAN AFFAIRS...

  13. Mixed Waste Management Facility Groundwater Monitoring Report

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.

    1998-03-01

    During fourth quarter 1997, eleven constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility. No constituents exceeded final PDWS in samples from upgradient monitoring wells. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

  14. Surrogate Final Technical Report for "Solar: A Photovoltaic Manufacturing Development Facility"

    Energy Technology Data Exchange (ETDEWEB)

    Farrar, Paul [State University of New York Research Foundation, Albany, NY (United States)

    2014-06-27

    The project goal to create a first-of-a-kind crystalline Silicon (c-Si) photovoltaic (PV) Manufacturing & Technology Development Facility (MDF) that will support the growth and maturation of a strong domestic PV manufacturing industry, based on innovative and differentiated technology, by ensuring industry participants can, in a timely and cost-effective manner, access cutting-edge manufacturing equipment and production expertise needed to accelerate the transition of innovative technologies from R&D into manufacturing.

  15. Evolution of facility layout requirements and CAD [computer-aided design] system development

    International Nuclear Information System (INIS)

    Jones, M.

    1990-06-01

    The overall configuration of the Superconducting Super Collider (SSC) including the infrastructure and land boundary requirements were developed using a computer-aided design (CAD) system. The evolution of the facility layout requirements and the use of the CAD system are discussed. The emphasis has been on minimizing the amount of input required and maximizing the speed by which the output may be obtained. The computer system used to store the data is also described

  16. Development and demonstration of sodium fire mitigation system in the SAPFIRE facility

    International Nuclear Information System (INIS)

    Himeno, Y.; Miyahara, S.; Morii, T.; Sasaki, K.

    1989-01-01

    Flow pattern of a realistic sodium leak from the sodium piping equipped with jackets and thermal insulator was experimentally investigated. Then, based on this result, the fire mitigation system consisting of an inclined liner, a drain piping, and a smothering tank has been developed. The performance of the system was, in final, validated in the large-scale sodium leak and fire test in the SAPFIRE facility. (author)

  17. Development of a charged particle detector array in Pelletron-LINAC facility

    International Nuclear Information System (INIS)

    John, Bency; Inkar, A.L.; Saxena, A.; Vind, R.P.; Gupta, Y.K.; Biswas, D.C.; Nayak, B.K.; Thomas, R.G.; Danu, L.S.; Choudhury, R.K.; Kailas, S.; Topkar, A.; Venkatramanan, S.; Kumar, Manish; Sunilkumar, S.

    2010-01-01

    A charged particle detector array consisting of 50 Si-CsI detector telescopes for study of heavy-ion reactions is under construction in BARC-TIFR Pelletron-LINAC facility. Developmental work carried out for the detector modules, front-end and pulse shape discrimination electronics, scattering chamber and other mechanical parts are summarized. Some new ideas developed during the course of work are pointed out. (author)

  18. Quarterly coal report, July--September 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks. Coke production consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for July through September 1997 and aggregated quarterly historical data for 1991 through the second quarter of 1997. Appendix A displays, from 1991 on, detailed quarterly historical coal imports data. 72 tabs.

  19. The development of seasonal emission factors from a Canadian commercial laying hen facility

    Science.gov (United States)

    Morgan, Robert J.; Wood, David J.; Van Heyst, Bill J.

    2014-04-01

    Pollutants emitted from poultry housing facilities are a concern from a human health, bird welfare, and environmental perspective. Development of emission factors for these aerial pollutants is difficult due to variable climatic conditions, the number and type of poultry, and the wide range of management practices used. To address these concerns, a study was conducted to develop emission factors for ammonia and particulate matter over a period of one year from a commercial poultry laying hen facility in Wellington County, Ontario, Canada. Instruments housed inside an on-site mobile trailer were used to monitor in-house concentrations of ammonia and size fractionated particulate matter via a heated sample line. Along with a ventilation profile, emission factors were developed for the facility. Average emissions of 19.53 ± 19.97, 2.55 ± 2.10, and 1.10 ± 1.52 g day-1 AU-1 (where AU is defined as an animal unit equivalent to 500 kg live mass) for ammonia, PM10, PM2.5, respectively, were observed. All emissions peaked during the winter months, with the exception of PM2.5 which increased in the summer.

  20. The partnership approach to siting and developing radioactive waste management facilities

    International Nuclear Information System (INIS)

    2010-03-01

    History shows that the search for sites for radioactive waste management facilities has been marred by conflicts and delays. Affected communities have often objected that their concerns and interests were not addressed. In response, institutions have progressively turned away from the traditional 'decide, announce and defend' model, and are learning to 'engage, interact and co-operate'. This shift has fostered the emergence of partnerships between the proponent of the facility and the potential host community. Working in partnership with potential host communities enables pertinent issues and concerns to be raised and addressed, and creates an opportunity for developing a relationship of mutual understanding and mutual learning, as well as for developing solutions that will add value to the host community and region. Key elements of the partnership approach are being incorporated into waste management strategies, leading increasingly to positive outcomes. National radioactive waste management programmes are in various phases of siting facilities and rely on different technical approaches for the various categories of waste. In all cases, it is necessary for institutional actors and the potential or actual host community to build a meaningful, workable relationship. Partnership approaches are effective in achieving a desirable combination of licensable site and management concept while meeting the sometimes competing requirements of fair representation and competent participation. Partnership arrangements facilitate reaching agreement on measures for local control, financial support and future development

  1. NREL PV Working With Industry Newsletter: 4th Quarter 1999

    Energy Technology Data Exchange (ETDEWEB)

    Moon, S.; Poole, L.

    2000-03-03

    NREL PV Working With Industry is a quarterly newsletter devoted to the research, development, and deployment performed by NREL staff in concert with their industry and university partners. The Fourth Quarter, 1999 issue, titled ''Knowledge is PV Power'' focuses on the contribution of the university-based subcontractors to the PV Program. The editorialist is Robert Birkmire, Director of the Institute of Energy Conversion, which is affiliated with the University of Delaware.

  2. Development of remote handling technology for nuclear fuel cycle facilities in Japan

    International Nuclear Information System (INIS)

    Maekawa, Hiromichi; Sakai, Akira; Miura, Noriaki; Kozaka, Tetsuo; Hamada, Takashi

    2015-01-01

    Remote handling technology has been systematically developed for nuclear fuel cycle facilities in Japan since 1970s, primarily in parallel with the development of reprocessing and HLLW (High Level Liquid Waste) vitrification process. In case of reprocessing and vitrification process to handle highly radioactive and hazardous materials, the most of components are installed in the radiation shielded hot cells and operators are not allowed to enter the work area in the cells for operation and maintenance. Therefore, a completely remote handling system is adopted for the cells to reduce radiation doses of operators and increase the availability of the facility. The hot cells are generally designed considering the scale of components (laboratory, demonstration, or full-scale), the function of the systems (chemical process, material handling, dismantling, decontamination, or chemical analysis), and the environmental conditions (radiation dose rate, airborne concentration, surface contamination, or fume/mist/dust). Throughout our domestic development work for remote handling technology, the concept of the large scale integrated cell has been adopted rather than a number of small scale separated cells, for the reasons to reduce the total installation space and the number of remote handling equipment required for the each cell as much as possible. In our domestic remote maintenance design, several new concepts have been developed, tested, and demonstrated in the Tokai Virtrification Facility (TVF) and the Rokkasho HLLW Vitrification and Storage Facility (K-facility). Layout in the hot cells, the performance of remote handling equipment, and the structure of the in-cell components are important factors for remote maintenance design. In case of TVF (hot tests started in 1995), piping and vessels are prefabricated in the rack modules and installed in two lines on both sides of the cell. These modules are designed to be remotely replaced in the whole rack. Two overhead cranes

  3. The National Carbon Capture Center at the Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2014-12-30

    The National Carbon Capture Center (NCCC) at the Power Systems Development Facility supports the Department of Energy (DOE) goal of promoting the United States’ energy security through reliable, clean, and affordable energy produced from coal. Work at the NCCC supports the development of new power technologies and the continued operation of conventional power plants under CO2 emission constraints. The NCCC includes adaptable slipstreams that allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity and accelerate their development path to commercialization. During its first contract period, from October 1, 2008, through December 30, 2014, the NCCC designed, constructed, and began operation of the Post-Combustion Carbon Capture Center (PC4). Testing of CO2 capture technologies commenced in 2011, and through the end of the contract period, more than 25,000 hours of testing had been achieved, supporting a variety of technology developers. Technologies tested included advanced solvents, enzymes, membranes, sorbents, and associated systems. The NCCC continued operation of the existing gasification facilities, which have been in operation since 1996, to support the advancement of technologies for next-generation gasification processes and pre-combustion CO2 capture. The gasification process operated for 13 test runs, supporting over 30,000 hours combined of both gasification and pre-combustion technology developer testing. Throughout the contract period, the NCCC incorporated numerous modifications to the facilities to accommodate technology developers and increase test capabilities. Preparations for further testing were ongoing to continue advancement of the most promising technologies for

  4. Development of cancer therapy facility of Hanaro and medical research in BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Byung Jin; Kim, M. S.; Kim, M. J.; Park, S. J. [KAERI, Taejon (Korea, Republic of); Lee, C. H.; Kwack, H. S.; Kim, M. S. [Korea Inst. of Radiological and Medical Sciences, Seoul (Korea, Republic of); Kim, J. K.; Park, S. H.; Shin, C. H. [Hanyang Univ., Seoul (Korea, Republic of)

    2003-05-01

    In order to support the domestic research on the Boron Neutron Capture Therapy(BNCT) which is a promising treatment method for tumor in principle, a neutron irradiation facility and a Prompt Gamma Neutron Activation Analysis (PGNAA) equipment for the boron concentration measurement are developed and installed at Hanaro. Meanwhile basic research has been performed to develop BNCT medical technology using above Hanaro facilities when they are ready. The Hanaro BNCT facility gives almost pure thermal neutron beam, it can be applied to all level of BNCT research from the cell culture and animal study to clinical trials by focussed irradiation, and its use does not cause any interference with other utilization. It can also be used for other purposes such as standard thermal neutron field and a dynamic neutron radiography with excellent features. The PGNAA equipment will be used not only for the boron concentration measurement but also for the general multi-element simultaneous analyses. The medical research for BNCT covers basic research on dose evaluation, boron compound behaviour and new compound development. Technologies for neutron and gamma transport calculation and their measurement, and micro dosimetry are developed. While import of a dose planning program has been pushed, domestic development of the program has been tried. Imaging technologies for boron distribution using SPECT or PET are developed by labeling I-123 or F-18 to BPA. Data for the BPA accumulation into the brain tumor are produced by clinical trials of the technology. A general and versatile method for the synthesis of o-carborane clusters containing of their important biological activities as neurotransmitter, antipsychotic or anticancer is developed. We found three promising compounds of which accumulation into B-16 melanoma cell is about 10 times of BPA.

  5. On exposure of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The Law for Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1988 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the exposure of workers was below the permissible exposure dose in 1988 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of Japan Atomic Energy Research Institute and Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

  6. Short-term energy outlook. Quarterly projections, first quarter 1995

    International Nuclear Information System (INIS)

    1995-02-01

    The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). The forecast period for this issue of the Outlook extends from the first quarter of 1995 through the fourth quarter of 1996. Values for the fourth quarter of 1994, however, are preliminary EIA estimates or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data, compiled into the first quarter 1995 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS database is archived quarterly and is available from the National Technical Information Service. The cases are produced using the Short-Term Integrated Forecasting System (STIFS). The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. Macroeconomic estimates are produced by DRI/McGraw-Hill but are adjusted by EIA to reflect EIA assumptions about the world price of crude oil, energy product prices, and other assumptions which may affect the macroeconomic outlook. The EIA model is available on computer tape from the National Technical Information Service

  7. Quarterly environmental radiological survey summary - first quarter 1997 100, 200, 300, and 600 areas

    International Nuclear Information System (INIS)

    Mckinney, S.M.

    1997-01-01

    This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The First Quarter 1997 survey results and the status of actions required are summarized below: (1) All of the routine environmental radiological surveys scheduled during January, February, and March 1997, were performed as planned. (2) One hundred four environmental radiological surveys were performed during the first quarter 1997, twenty-nine at the active waste sites and seventy-five at the inactive waste sites. Contamination above background levels was found at eight of the active waste sites and seven of the inactive waste sites. Contamination levels as high as >1,000,000 disintegrations per minute (dpm) were reported. Of these contaminated surveys twelve were in Underground Radioactive Material (URM) areas and three were in contamination areas. The contamination found within ten of the URM areas was immediately cleaned up and no further action was required. In the remaining five sites the areas were posted and will require decontamination. Radiological Problem Reports (RPR's) were issued and the sites were turned over to the landlord for further action if required. (3) During the first quarter of 1997, 5.6 hectares (13.8 acres) were stabilized and radiologically down posted from Contamination Area (CA)/Soil Contamination (SC) to URM. (4) During the first quarter of 1997, the size of 216-A-25 Gable Mountain Pond was increased from 30.4 to 34.5 hectares (75.0 to 85.2 acres). This increase in size was due to the correction of the original boundary area by using the advanced technology of a global positioning system (GPS). An area, 1.6 hectares (4.0 acres), east of and adjacent to the 241-S/SX/SY tank farm complex was posted as a contamination/soil contamination area. (5) Five open Surveillance Compliance Inspection Reports (SCIRs) had not been resolved

  8. Development of a vacuum leak test method for large-scale superconducting magnet test facilities

    International Nuclear Information System (INIS)

    Kawano, Katsumi; Hamada, Kazuya; Okuno, Kiyoshi; Kato, Takashi

    2006-01-01

    Japan Atomic Energy Agency (JAEA) has developed leak detection technology for liquid helium temperature experiments in large-scale superconducting magnet test facilities. In JAEA, a cryosorption pump that uses an absorbent cooled by liquid nitrogen with a conventional helium leak detector, is used to detect helium gas that is leaking from pressurized welded joints of pipes and valves in a vacuum chamber. The cryosorption pump plays the role of decreasing aerial components, such as water, nitrogen and oxygen, to increase the sensitivity of helium leak detection. The established detection sensitivity for helium leak testing is 10 -10 to 10 -9 Pam 3 /s. A total of 850 welded and mechanical joints inside the cryogenic test facility for the ITER Central Solenoid Model Coil (CSMC) experiments have been tested. In the test facility, 73 units of glass fiber-reinforced plastic (GFRP) insulation break are used. The amount of helium permeation through the GFRP was recorded during helium leak testing. To distinguish helium leaks from insulation-break permeation, the helium permeation characteristic of the GFRP part was measured as a function of the time of helium charging. Helium permeation was absorbed at 6 h after helium charging, and the detected permeation is around 10 -7 Pam 3 /s. Using the helium leak test method developed, CSMC experiments have been successfully completed. (author)

  9. States and compacts: Issues and events affecting facility development efforts, including the Barnwell opening

    International Nuclear Information System (INIS)

    Larson, G.S.

    1995-01-01

    Ten years have passed since the first regional low-level radioactive waste compacts received Congressional consent and initiated their efforts to develop new disposal capacity. During these 10 years, both significant achievements and serious setbacks have marked our efforts and affect our current outlook. Recent events in the waste marketplace, particularly in the operating status of the Barnwell disposal facility, have now raised legitimate questions about the continued rationale for the regional framework that grew out of the original legislation enacted by Congress in 1980. At the same time, licensing activities for new regional disposal facilities are under way in three states, and a fourth awaits the final go-ahead to begin construction. Uncertainty over the meaning and reliability of the marketplace events makes it difficult to gauge long-term implications. In addition, differences in the status of individual state and compact facility development efforts lead to varying assessments of the influence these events will, or should, have on such efforts

  10. Considerations in the development and implementation of a maintenance robot for nuclear power facilities

    International Nuclear Information System (INIS)

    Rohrabacher, A.; Carlton, R.; Gelhaus, F.

    1987-01-01

    The Nuclear Power Division of the Electric Power Research Institute (EPRI) began its automated nuclear plant maintenance research (research project 2232) in 1982 with surveys of domestic and Japanese ongoing and potential uses of robotic systems in nuclear power facilities. After studying these potential research areas, EPRI initiated a three-pronged effort. All surveys concluded that a mobile system for general environmental, visual, and auto surveillance would be beneficial, and EPRI contracted for the development and evaluation of the Surveyor robot. Work also began to catalog existing systems and to quantify the methodology that a utility could use to optimally complete the plant-mission, robot-system selection process. The conceptualizing phase of the effort defined the necessary physical attributes for the machine to perform a variety of maintenance tasks. Characteristics such as mobility, strength, conditions of service, materials of construction, tool functional requirements, facility interfaces, and operator interface were defined to the extent practical. Substantial versatility is required for the variability of the targeted maintenance tasks and for the variability of facility layouts and designs found throughout the nuclear industry. A key contribution to this development effort comes from the project's Utility Advisors Group. The contract's host utility provides membership to lead this group, and that company will train in the use of the machine for 6 months prior to utilizing it in their power plant for 2 yr

  11. States and compacts: Issues and events affecting facility development efforts, including the Barnwell opening

    Energy Technology Data Exchange (ETDEWEB)

    Larson, G.S.

    1995-12-31

    Ten years have passed since the first regional low-level radioactive waste compacts received Congressional consent and initiated their efforts to develop new disposal capacity. During these 10 years, both significant achievements and serious setbacks have marked our efforts and affect our current outlook. Recent events in the waste marketplace, particularly in the operating status of the Barnwell disposal facility, have now raised legitimate questions about the continued rationale for the regional framework that grew out of the original legislation enacted by Congress in 1980. At the same time, licensing activities for new regional disposal facilities are under way in three states, and a fourth awaits the final go-ahead to begin construction. Uncertainty over the meaning and reliability of the marketplace events makes it difficult to gauge long-term implications. In addition, differences in the status of individual state and compact facility development efforts lead to varying assessments of the influence these events will, or should, have on such efforts.

  12. Canadian development program for off-gas management in nuclear facilities

    International Nuclear Information System (INIS)

    Sridhar, T.S.

    1983-01-01

    The Canadian program for the development and evaluation of processes and technology for the separation and containment of radioactive species in off-gases is directed towards the following specific aspects: 1) assessment of available treatment technology and evaluation of future clean-up requirements; 2) development and engineering evaluation, under realistic conditions, of promising new processes that would be inherently simpler and safer; and 3) specification of off-gas emission control systems for future nuclear facilities based on the most favourable technology. The program is being carried out by Atomic Energy of Canada Limited in collaboration with the electrical utility, Ontario Hydro, and selected Canadian universities. A brief description is presented of methods for removing tritium and carbon-14 from the moderator systems of CANDU power reactors, methods for removing iodine from the off-gases of a molybdenum-99 production facility at the Chalk River Nuclear Laboratories, and procedures for monitoring the off-gas effluent composition in the Thorium Fuel Reprocessing Experiment (TFRE) facility at the Whiteshell Nuclear Research Establishment

  13. Cogeneration and Small Power Production Quarterly Report to the California Public Utilities Commission Third Quarter 1983

    Energy Technology Data Exchange (ETDEWEB)

    None

    1983-01-01

    In the Third Quarter of 1983, the number of signed contracts and committed projects rose from 240 to 258, with a total estimated nominal capacity of these projects of 1,547 MW. Of this nominal capacity, about 416 MW is operational, and the balance is under contract for development. A map indicating the location of operational facilities under contract with PG and E is provided. Of the 258 signed contracts and committed projects, 83 were cogeneration, solid waste, or biomass projects with a potential of 779 MW. PG and E also had under active discussion 38 cogeneration projects that could generate a total of 797 MW to 848 MW, and 19 solid waste/biomass projects with a potential of 152 MW to 159 MW. Two contracts have been signed with geothermal projects, capable of producing 83 MW. There are 6 solar projects with signed contracts and a potential of 36 MW, as well as 3 solar projects under active discussion for 31 MW. Wind farm projects under contract number 21, with a generating capability of 528 MW. Also, discussions are being conducted with 17 wind farm projects, totaling 257 to 262 MW. There are 94 wind projects of 100 kW or less with signed contracts and a potential of almost 1 MW, as well as 8 other small wind projects under active discussion. There are 50 hydroelectric projects with signed contracts and a potential of 112 MW, as well as 67 projects under active discussion for 175 MW. In addition, there are 31 hydroelectric projects, with a nominal capacity of 185 MW, that PG and E is planning to construct.

  14. Cogeneration and Small Power Production Quarterly Report to the California Public Utilities Commission Second Quarter 1983

    Energy Technology Data Exchange (ETDEWEB)

    None

    1983-01-01

    In the Second Quarter of 1983, the number of signed contracts and committed projects rose from 223 to 240, with a total estimated nominal capacity of these projects of 1,449 MW. Of this nominal capacity, about 361 MW is operational, and the balance is under contract for development. A map indicating the location of currently operating facilities is provided as Figure A. Of the 240 signed contracts and committed projects, 75 were cogeneration, solid waste, or biomass projects with a potential of 740 MW. PG and E also had under active discussion 32 cogeneration projects that could generate a total of 858 MW to 921 MW, and 10 solid waste/biomass projects with a potential of 113 MW to 121 MW. Two contracts have been signed with geothermal projects, capable of producing 83 MW. There are 6 solar projects with signed contracts and a potential of 36 MW, as well as another solar project under active discussion for 30 MW. Wind farm projects under contract number 19, with a generating capability of 471 MW. Also, discussions are being conducted with 12 wind farm projects, totaling 273 to 278 MW. There are 89 wind projects of 100 kW or less with signed contracts and a potential of almost 1 MW, as well as 10 other projects under active discussion. There are 47 hydroelectric projects with signed contracts and a potential of 110 MW, as well as 65 projects under active discussion for 175 MW. In addition, there are 30 hydroelectric projects, with a nominal capacity of 291 MW, that PG and E is constructing or planning to construct. Table A displays the above information. In tabular form, in Appendix A, are status reports of the projects as of June 30, 1983.

  15. Cogeneration and Small Power Production Quarterly Report to the California Public Utilities Commission First Quarter 1984

    Energy Technology Data Exchange (ETDEWEB)

    None

    1984-01-01

    At the end of the First Quarter of 1984, the number of signed contracts and letter agreements for cogeneration and small power production projects was 322, with a total estimated nominal capacity of 2,643 MW. Of these totals, 215 projects, capable of producing 640 MW, are operational. A map indicating the location of operational facilities under contract with PG and E is provided. Developers of cogeneration, solid waste, or biomass projects had signed 110 contracts with a potential of 1,467 MW. In total, 114 contracts and letter agreements had been signed with projects capable of producing 1,508 MW. PG and E also had under active discussion 35 cogeneration projects that could generate a total of 425 MW to 467 MW, and 11 solid waste or biomass projects with a potential of 94 MW to 114 MW. One contract had been signed for a geothermal project, capable of producing 80 MW. There were 7 solar projects with signed contracts and a potential of 37 MW, as well as 5 solar projects under active discussion for 31 MW. Wind farm projects under contract numbered 32, with a generating capability of 848 MW. Also, discussions were being conducted with 18 wind farm projects, totaling 490 MW. There were 101 wind projects of 100 kW or less with signed contracts and a potential of 1 MW, as well as 6 other small wind projects under active discussion. There were 64 hydroelectric projects with signed contracts and a potential of 148 MW, as well as 75 projects under active discussion for 316 MW. In addition, there were 31 hydroelectric projects, with a nominal capacity of 187 MW, that Pg and E was planning to construct.

  16. National Low-Temperature Neutron Irradiation Facility (NLTNIF). The status of development

    International Nuclear Information System (INIS)

    Coltman, R.R. Jr.; Kerchner, H.R.; Klabunde, C.E.; Young, F.W. Jr.

    1985-12-01

    In May 1983, the Department of Energy authorized the establishment of a National Low-Temperature Neutron Irradiation Facility (NLTNIF) at ORNL's Bulk Shielding Reactor (BSR). The NLTNIF, which will be available for qualified experiments at no cost to users, will provide a combination of high radiation intensities and special environmental and testing conditions that have not been previously available in the US. Since the DOE authorization, work has proceeded on the design and construction of the new facility without interruption. This report describes the present status of the development of the NLTNIF and the anticipated schedule for completion and performance testing. There is a table of the major specifications and capabilities and a schematic layout of the irradiation cryostate for design and dimensioning of test and experiment assemblies

  17. Low prevalence of chronic beryllium disease among workers at a nuclear weapons research and development facility.

    Science.gov (United States)

    Arjomandi, Mehrdad; Seward, James; Gotway, Michael B; Nishimura, Stephen; Fulton, George P; Thundiyil, Josef; King, Talmadge E; Harber, Philip; Balmes, John R

    2010-06-01

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

  18. Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

    International Nuclear Information System (INIS)

    1978-01-01

    This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years

  19. Development of Regulatory Framework on Decommissioning of Nuclear Facilities in the Philippines

    Energy Technology Data Exchange (ETDEWEB)

    Piqueroa, Ronald E. [Korea Advanced Institue of Science and Technology, Daejeon (Korea, Republic of); Lee, Jung Joon; Ahn, Sangmyeon [Radioactive Waste Safety Evaluation Dept., Daejeon (Korea, Republic of)

    2013-10-15

    The PRR-1 was obtained through the bilateral agreement between the Philippines and USA on July 25, 1955. The operation started in 1963 at 1 MW and converted to TRIGA type and shutdown on 1988. In 2005, the Philippine Nuclear Research Institute (PNRI) formally decided to decommission the reactor by internally regulating the process under the Nuclear Regulatory Division of PNRI based on PNRI Office Order in 2005 and granted authorization to start decommissioning in 2007. However, there are only few specific regulations and guidelines related to decommissioning of nuclear facilities. PRR-1 was accepted as a model reactor for the IAEA Research Reactor Decommissioning Demonstration Project (R2D2P) and currently receiving support and assistance from IAEA for the completion and implementation of decommissioning plan. Comparing with the IAEA Safety Standards, key points which are not present should be incorporated in developing the current regulatory framework on decommissioning of nuclear facilities in the Philippines.

  20. Process and mechanical development for the Savannah River TRU Waste Facility

    International Nuclear Information System (INIS)

    Charlesworth, D.L.

    1986-01-01

    A Transuranic Waste Facility will be designed and built to retrieve, process, and prepare noncombustible 238 Pu and 239 Pu waste that is now being retrievably stored for disposal. Development work is planned or is now in progress to support this effort, including cold run-in and testing of a large, low-speed shredder and material handling system, a bagless transfer system, a robotically controlled manipulator (''Telerobot''), and an incineration process. Preliminary tests of the shredder system, Telerobot, and bagless transfer system have been completed and an integrated test facility is being built that will allow extensive testing of these components. Cold run-in of a continuous incineration process designed to burn 238 Pu contaminated waste is now in progress

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-01-11

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

  2. Neutron and meson sources on the base of high-current cyclotron facilities (prospects of development)

    International Nuclear Information System (INIS)

    Dmitrievskij, V.P.

    1985-01-01

    A brief review is given and possible ways of development of neutron and meson generators on the basis of accelerating facilities are shown. The following conclusions are made: to combine two types of generators (neutron, meson) in one accelerated beam the deuteron beam for the energy 800-1000 MeV/nucleon should be accepted as the optimal one; accelerated beam energy distribution between mesocatalytic and emission branches of neutron generation is determined by the choice of mesocatalytic reactor target parameters; efficiency is the determining parameter of the accelerating facility (complex) when it is u sed for neutron or meson generators; a combination of linear and superconducting cyclic accelerators is the most perspective co mplex as to the efficiency

  3. Development of technical design for waste processing and storage facilities for Novi Han repository

    International Nuclear Information System (INIS)

    Canizares, J.; Benitez, J.C.; Asuar, O.; Yordanova, O.; Demireva, E.; Stefanova, I.

    2005-01-01

    Empresarion Agrupados Internacional S.A. (Spain) and ENPRO Consult Ltd. (Bulgaria) were awarded a contract by the Central Finance and Contracts Unit to develop the technical design of the waste processing and storage facilities at the Novi Han repository. At present conceptual design phase is finished. This conceptual design covers the definition of the basic design requirements to be applied to the installations defined above, following both European and Bulgarian legislation. In this paper the following items are considered: 1) Basic criteria for the layout and sizing of buildings; 2) Processing of radioactive waste, including: treatment and conditioning of disused sealed sources; treatment of liquid radioactive wastes; treatment of solid radioactive waste; conditioning of liquid and solid radioactive waste; 3) Control of waste packages and 4) Storage of radioactive waste, including storage facility and waste packages. An analysis of inventories of stored and estimated future wastes and its subsequent processes is also presented and the waste streams are illustrated

  4. Development and application of a Controlled Release Facility (CRF) to validate flux quantifying methodologies.

    Science.gov (United States)

    Helmore, Jonathan

    2017-04-01

    The National Physical Laboratory, the UK's National Measurement Institute, has developed a novel facility capable of replicating the gaseous emission flux characteristics of a variety of real-word scenarios as may be found in small to medium scale industry and agriculture. The Controlled Release Facility (CRF) can be used to challenge conventional remote sensing techniques, as well as validate new Unmanned Aerial Vehicle (UAV) and distributed sensor network based methods, for source identification and flux calculation. The CRF method will be described and the results from three case studies will be discussed: The replication of an operational on-shore shale gas well using emissions of natural gas to atmosphere and measurements using Differential Absorption LIDAR (DIAL); the replication of fugitive volatile organic compounds emissions from a petrochemical unit and measurements using DIAL; and the replication of methane and carbon dioxide emissions from landfill and measurements using both fixed wing and multi-rotor UAVs.

  5. Developing an expert system to control a beam line at the Los Alamos Meson Physics Facility

    International Nuclear Information System (INIS)

    Clearwater, S.H.; Papcun, G.; Clark, D.A.

    1985-01-01

    High energy particle experiments require an accelerator as a source of high energy particles. To increase the productivity of an accelerator facility, we wish to develop an expert system to control beam lines. Expert Systems are a branch of Artificial Intelligence where a computer program performs tasks requiring human expertise. Unlike most expert systems we have a physical model underlying our beam line and this model can be used with the expert system to improve performance. The development of the expert system will lead to an increased understanding of the beam line as well as the possibility of state-of-the-art expert system building

  6. Development status of oxygen solid electrolyte sensors in HLMC in respect to monoblock reactor facilities

    International Nuclear Information System (INIS)

    Martynov, P.N.; Askhadullin, R.Sh.; Storozhenko, A.N.; Shelemet'ev, V.M.; Sadovnichij, R.P.; Ivanov, I.I.

    2014-01-01

    The results of developing sensors on the base of solid electrolytes to control oxygen in lead and lead-bismuth coolants are considered. It is found out that ceramic detecting elements on the base of solid electrolytes from oxide ceramics are able to work a long time in conditions of high temperatures and thermal shocks in molten metals (in gases). They show stable conducting and mechanical properties, thermal resistance, low gas permeability. Using considered detecting elements different sensors, including ones for monoblock reactors and facilities, are developed and manufactured. The given sensors can be used for both continuous and periodical oxygen control in heavy liquid metal coolants [ru

  7. Tank 42 sludge-only process development for the Defense Waste Processing Facility (DWPF)

    International Nuclear Information System (INIS)

    Lambert, D.P.

    2000-01-01

    Defense Waste Processing Facility (DWPF) requested the development of a sludge-only process for Tank 42 sludge since at the current processing rate, the Tank 51 sludge has been projected to be depleted as early as August 1998. Testing was completed using a non-radioactive Tank 42 sludge simulant. The testing was completed under a range of operating conditions, including worst case conditions, to develop the processing conditions for radioactive Tank 42 sludge. The existing Tank 51 sludge-only process is adequate with the exception that 10 percent additional acid is recommended during sludge receipt and adjustment tank (SRAT) processing to ensure adequate destruction of nitrite during the SRAT cycle

  8. The LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2002-01-01

    Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). A reliable supply of HEU metal from the United States used in the manufacture of targets for the NRU research reactor has been a key factor to enable MDS Nordion to develop a secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets provides predictable, consistent yields for our high-volume molybdenum production process. Each link of the isotope supply chain, from isotope production to ultimate use by the physician, has been established using this proven and established method of HEU target irradiation and processing to extract molybdenum-99. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the construction of two MAPLE reactors and a New Processing Facility. The design of the MAPLE facilities was based on an established process developed by Atomic Energy of Canada Ltd. (AECL) - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a three phase LEU Target Development and Conversion Program for the MAPLE facilities. Phase 1, the Initial Feasibility Study, which identified the technical issues to convert the MAPLE reactor targets from HEU to LEU for large scale commercial production was reported on at the RERTR- 2000 conference. The second phase of the LEU Target Development and Conversion Program was developed with extensive consultation and involvement of experts knowledgeable in target development, process system design, enriched uranium conversion chemistry and commercial scale reactor operations and molybdenum production. This paper will provide an overview of the Phase 2 Conversion Development Program, report on progress to date, and further

  9. Test facility for the development of 150-keV, multi-megawatt neutral beam systems

    International Nuclear Information System (INIS)

    Haughian, W.; Baker, W.R.; Biagi, L.A.; Hopkins, D.B.

    1975-11-01

    The next generation of CTR experiments, such as the Tokamak Fusion Test Reactor (TFTR), will require neutral-beam injection systems that produce multi-megawatt, 120-keV deuterium-beam pulses of 0.5-second duration. Since present injection systems are operating in the 10- to 40-keV range, an intensive development effort is in progress to meet a 150-keV requirement. The vacuum system and power supplies that make up a test facility to be used in the development of these injectors are described

  10. CENER/NREL Collaboration in Testing Facility and Code Development: Cooperative Research and Development Final Report, CRADA Number CRD-06-207

    Energy Technology Data Exchange (ETDEWEB)

    Moriarty, P.

    2014-11-01

    Under the funds-in CRADA agreement, NREL and CENER will collaborate in the areas of blade and drivetrain testing facility development and code development. The project shall include NREL assisting in the review and instruction necessary to assist in commissioning the new CENER blade test and drivetrain test facilities. In addition, training will be provided by allowing CENER testing staff to observe testing and operating procedures at the NREL blade test and drivetrain test facilities. CENER and NREL will exchange blade and drivetrain facility and equipment design and performance information. The project shall also include exchanging expertise in code development and data to validate numerous computational codes.

  11. The National Carbon Capture Center at the Power Systems Development Facility: Topical Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2011-03-01

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy and dedicated to the advancement of clean coal technology. In addition to the development of advanced coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to study CO2 capture from coal-derived syngas and flue gas. The newly established NCCC will include multiple, adaptable test skids that will allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity. During the Budget Period One reporting period, efforts at the PSDF/NCCC focused on developing a screening process for testing consideration of new technologies; designing and constructing pre- and post-combustion CO2 capture facilities; developing sampling and analytical methods; expanding fuel flexibility of the Transport Gasification process; and operating the gasification process for technology research and for syngas generation to test syngas conditioning technologies.

  12. On exposure management of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1993

    International Nuclear Information System (INIS)

    1994-01-01

    The Law of Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1993 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the the exposure of workers was below the permissible exposure dose in 1993 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of JAERI and PNC. (J.P.N.)

  13. Measuring governance at health facility level: developing and validation of simple governance tool in Zambia.

    Science.gov (United States)

    Mutale, Wilbroad; Mwanamwenge, Margaret Tembo; Balabanova, Dina; Spicer, Neil; Ayles, Helen

    2013-08-09

    Governance has been cited as a key determinant of economic growth, social advancement and overall development. Achievement of millennium development goals is partly dependant on governance practices. In 2007, Health Systems 20/20 conducted an Internet-based survey on the practice of good governance. The survey posed a set of good practices related to health governance and asked respondents to indicate whether their experience confirmed or disconfirmed those practices. We applied the 17 governance statements in rural health facilities of Zambia. The aim was to establish whether the statements were reliable and valid for assessing governance practices at primary care level. Both quantitative and qualitative methods were used. We first applied the governance statements developed by the health system 20/20 and then conducted focus group discussion and In-depth interviews to explore some elements of governance including accountability and community participation. The target respondents were the health facility management team and community members. The sample size include 42 health facilities. Data was analyzed using SPSS version 17 and Nvivo version 9. The 95% one-sided confidence interval for Cronbach's alpha was between 0.69 and 0.74 for the 16 items.The mean score for most of the items was above 3. Factor analysis yielded five principle components: Transparency, community participation, Intelligence & vision, Accountability and Regulation & oversight. Most of the items (6) clustered around the transparency latent factor. Chongwe district performed poorly in overall mean governance score and across the five domains of governance. The overall scores in Chongwe ranged between 51 and 94% with the mean of 80%. Kafue and Luangwa districts had similar overall mean governance scores (88%). Community participation was generally low. Generally, it was noted that community members lacked capacity to hold health workers accountable for drugs and medical supplies. The study

  14. Development of a tool to measure women's perception of respectful maternity care in public health facilities.

    Science.gov (United States)

    Sheferaw, Ephrem D; Mengesha, Teka Z; Wase, Solomon B

    2016-03-29

    Maternal mortality continues to be the biggest challenge facing Ethiopia and other developing countries. Although progress has been made in making maternity services available closer to the community, the rate of deliveries attended by skilled birth attendants has remained very low. Absence of respectful maternity care (RMC) is believed to have contributed to low utilization of facility delivery services. This study outlines steps undertaken to construct and validate a scale that measures women's perception of respectful maternity care provided in health facilities. An inductive item generation process that included a literature review and in-depth interviews with labor and delivery clients, followed by an expert review, assured face validity and content validity of the tool. A draft RMC scale with 37 items and two additional measures of global satisfaction items, measured on a five-point Likert scale, were administered to a developmental sample of 509 postnatal care clients visiting facilities immediately after childbirth to 7 weeks postpartum. IBM SPSS 20 was used to perform exploratory factor analysis (EFA) using principal component analysis (PCA) with oblique rotation method. The final RMC scale with 15 items was loaded on four components. The extracted components were labeled as friendly care, abuse-free care, timely care, and discrimination-free care. The final RMC scale correlated strongly with the global satisfaction measures, indicating criterion-related validity of the scale. Content-related validity was assured by the process of item generation. Construct validity of the RMC scale was confirmed by high average factor loading of the four components ranging from 0.76 to 0.82 and low correlation between the components. Stability of the scale was confirmed by running PCA in a randomly selected split sample of 320 samples from the validation sample. The final 15-item scale showed an adequate reliability with α = 0.845. The 15-item RMC scale is a valid and

  15. First quarter 2005 sales data

    International Nuclear Information System (INIS)

    2005-04-01

    This press release brings information on the AREVA group sales data. First quarter 2005 sales for the group were 2,496 millions of euros, up 3,6% year-on-year from 2,41 millions. The change in foreign exchange rates between the two periods show a negative impact of 22 millions euros, which is much lower than in the first quarter of 2004. It analyzes also in more details the situation of the front end, the reactors and service division, the back end division, the transmission and distribution division and the connectors division. (A.L.B.)

  16. Short-term energy outlook, Quarterly projections. Third quarter 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-08-04

    The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). An annual supplement analyzes the performance of previous forecasts, compares recent cases with those of other forecasting services, and discusses current topics related to the short-term energy markets. (See Short-Term Energy Outlook Annual Supplement, DOE/EIA-0202.) The forecast period for this issue of the Outlook extends from the third quarter of 1993 through the fourth quarter of 1994. Values for the second quarter of 1993, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in the Weekly Petroleum Status Report) or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data are EIA data published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding.

  17. Applied Meteorology Unit (AMU) Quarterly Report First Quarter FY-04

    Science.gov (United States)

    Bauman, William; Wheeler, Mark; Labert, Winifred; Jonathan Case; Short, David

    2004-01-01

    This report summarizes the Applied Meteorology Unit (AMU) activities for the First Quarter of Fiscal Year 2004 (October - December 2003). Tasks reviewed are: (1) Objective Lightning Probability Forecast, (2) Mesonet Temperature and Wind Climatology, (3) Severe Weather Forecast Decision Aid and (4) Anvil Transparency Relationship to Radar Reflectivity

  18. Short-term energy outlook, quarterly projections, first quarter 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    The forecast period for this issue of the Outlook extends from the first quarter of 1998 through the fourth quarter of 1999. Values for the fourth quarter of 1997, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in EIA`s Weekly Petroleum Status Report) or are calculated from model simulations that use the latest exogenous information available (for example, electricity sales and generation are simulated by using actual weather data). The historical energy data, compiled in the first quarter 1998 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. Macroeconomic estimates are adjusted by EIA to reflect EIA assumptions which may affect the macroeconomic outlook. By varying the assumptions, alternative cases are produced by using the STIFS model. 24 figs., 19 tabs.

  19. Short-term energy outlook: Quarterly projections, Third quarter 1992

    International Nuclear Information System (INIS)

    1992-08-01

    The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). An annual supplement analyzes the performance of previous forecasts, compares recent cases with those of other forecasting services, and discusses current topics related to the short-term energy markets. (See Short-Term Energy Outlook Annual Supplement, DOE/EIA-0202.) The principal users of the Outlook are managers and energy analysts in private industry and government. The forecast period for this issue of the Outlook extends from the third quarter of 1992 through the fourth quarter of 1993. Values for the second quarter of 1992, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in the Weekly Petroleum Status Report) or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data are EIA data published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding

  20. Dip coating process. Silicon sheet growth development for the large-area silicon sheet task of the low-cost silicon solar array project. Quarterly report No. 6, March 22, 1977--June 24, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Zook, J.D.; Heaps, J.D.; Maciolek, R.B.; Koepke, B.; Butter, C.D.; Schuldt, S.B.

    1977-06-30

    The objective of this research program is to investigate the technical and economic feasibility of producing solar-cell-quality sheet silicon by coating one surface of carbonized ceramic substrates with a thin layer of large-grain polycrystalline silicon from the melt. Significant progress was made in silicon on ceramic (SOC) solar cell performance. SOC cells having 1 cm/sup 2/ active areas demonstrated measured conversion efficiencies as high as 7.2 percent. Typical open circuit voltages (V/sub oc/) and short circuit current densities (J/sub sc/) were 0.51 volt and 20 mA/cm/sup 2/ respectively. Since the active surface of these solar cells is a highly reflective ''as-grown'' surface, one can expect improvement in J/sub sc/ after an anti-reflection (AR) coating is applied. It is significant that single-crystal comparison cells, also measured without benefit of an AR coating, had efficiencies in the 8.5 percent range with typical V/sub oc/'s and J/sub sc/'s of 0.54 volt and 23 mA/cm/sup 2/, respectively. Therefore, improvement in cell design and junction diffusion techniques should increase the efficiency of both the SOC and single-crystal cells. During this quarter the dip coating facility was inadvertently contaminated, but has since been restored to a purity level exceeding its original state. With this facility, silicon coatings were grown with a single-crystal seed attached to the substrate. Single-crystal silicon was not forthcoming, but the results were nonetheless encouraging. Several of the carbon coating types tried appear promising, including one which has high purity and can be applied uniformly by swab or airbrush.