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Sample records for reactor program quarterly

  1. Reactor Safety Research Programs Quarterly Report April- June 1981

    SciTech Connect

    Edler, S. K.

    1981-09-01

    This document summarizes the work performed by Pacific Northwest laboratory (PNL} from April1 through June 30, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory {INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  2. Reactor Safety Research Programs Quarterly Report April -June 1980

    SciTech Connect

    Edler, S. K.

    1980-11-01

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from April 1 through June 30, 1980, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission {NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining structural graphite strength, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation and postaccident coolability tests for the ESSOR Test Reactor Program, Ispra, Italy; blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  3. Reactor Safety Research Programs Quarterly Report October - December 1980

    SciTech Connect

    Edler, S K

    1981-04-01

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from October 1 through December 31, 1980, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining structural graphite strength, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NOE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation and postaccident coolability tests for the ESSOR Test Reactor Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  4. Reactor Safety Research Programs Quarterly Report July - September 1981

    SciTech Connect

    Edler, S. K.

    1982-01-01

    This document summarizes the work performed by Pacific Northwest laboratory (PNL) from July 1 through September 30, 1981, for the Division of Accident Evaluation, U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR} steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  5. Reactor Safety Research Programs Quarterly Report January - March 1980

    SciTech Connect

    Hagen, C. M

    1980-10-01

    This document summarizes the work performed by Pacific Northwest Laboratory from January 1 through March 31, 1980, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibilty of determining structural graphite strength, evaluating the feasibilty of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor steam generator tubes where serviceinduced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include the loss-of-coolant accident simulation tests at the NRU reactor, Chalk River, Canada; the fuel rod deformation and post-accident coolability tests for the ESSOR Test Reactor Program, Ispra, Italy; the blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and the experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  6. Reactor Safety Research Programs Quarterly Report October - December 1981

    SciTech Connect

    Edler, S. K.

    1982-03-01

    This document summarizes the work performed by Pacific Northwest laboratory (PNL) from October 1 through December 31, 1981, for the Division of Accident Evaluation, U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where serviceinduced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and post accident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  7. Reactor safety research programs. Quarterly report, July-September 1983

    SciTech Connect

    Edler, S.K.

    1984-04-01

    Evaluations of nondestructive examination (NDE) techniques and instrumentation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, and examining NDE reliability and probabilistic fracture mechanics. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Experimental data and validated models are being used to determine a method for evaluating the acceptance of welded or weld-repaired stainless steel piping. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada; and an instrumented fuel assembly irradiation program is being performed at Halden, Norway. Fuel assemblies and analytical support are being provided for experimental programs at other facilities, including the Super Sara Test Program, Ispra, Italy, and experimental programs at the Power Burst Facility.

  8. Reactor safety research programs. Quarterly report, April-June 1982

    SciTech Connect

    Edler, S.K.

    1982-11-01

    This document summarizes work performed by Pacific Northwest Laboratory (PNL) from April 1 through June 30, 1982, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities.

  9. Reactor safety research programs. Quarterly report, January-March 1982

    SciTech Connect

    Edler, S.K.

    1982-07-01

    This document summarizes work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1982, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities.

  10. Reactor-safety research programs. Quarterly report, October-December 1982. Volume 4

    SciTech Connect

    Edler, S.K.

    1983-04-01

    Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized-water-reactor steam-generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models being developed to provide better digital codes to compute the bahavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities.

  11. Reactor safety research programs. Quarterly report, April-June 1983. Vol. 2

    SciTech Connect

    Edler, S.K.

    1983-12-01

    This document summarizes work performed by Pacific Northwest Laboratory from April 1 through June 30, 1983, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Experimental data and validated models are being used to determine a method for evaluating the acceptance of welded or weld-repaired stainless steel piping. Core thermal models are being developed to provide better digital codes to compute the behavior or full-scale reactor systems under postulated accident conditions. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada; and an instrumented fuel assembly irradiation program is being performed at Halden, Norway. Fuel assemblies and analytical support are being provided for experimental programs at other facilities, including fuel rod deformation and severe fuel damage tests for the Super Sara Test Program, Ispra, Italy; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

  12. Reactor safety research programs. Quarterly report, October-December 1983. Vol. 4

    SciTech Connect

    Edler, S.K.

    1984-05-01

    Evaluations of nondestructive examination (NDE) techniques and instrumentation include investigating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems and examining NDE reliability and probabilistic fracture mechanics. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Experimental data and validated models are being used to determine a method for evaluating the acceptance of welded or weld-repaired stainless steel piping. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada; an instrumented fuel assembly irradiation program is being performed at Halden, Norway; and fuel assemblies and analytical support are being provided for experimental programs at the Power Burst Facility.

  13. Reactor-safety research programs. Quarterly report, July-September 1982

    SciTech Connect

    Edler, S.K.

    1983-03-01

    Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions.

  14. Advanced Reactor Safety Research Division. Quarterly progress report, January 1-March 31, 1980

    SciTech Connect

    Agrawal, A.K.; Cerbone, R.J.; Sastre, C.

    1980-06-01

    The Advanced Reactor Safety Research Programs quarterly progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: HTGR Safety Evaluation, SSC Code Development, LMFBR Safety Experiments, and Fast Reactor Safety Code Validation.

  15. Water Reactor Safety Research Division quarterly progress report, January 1-March 31, 1980

    SciTech Connect

    Romano, A.J.

    1980-06-01

    The Water Reactor Safety Research Programs Quarterly Report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: LWR Thermal Hydraulic Development, Advanced Code Evaluation, TRAC Code Assessment, and Stress Corrosion Cracking of PWR Steam Generator Tubing.

  16. Water Reactor Safety Research Division. Quarterly progress report, April 1-June 30, 1980

    SciTech Connect

    Abuaf, N.; Levine, M.M.; Saha, P.; van Rooyen, D.

    1980-08-01

    The Water Reactor Safety Research Programs quarterly report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: LWR Thermal Hydraulic Development, Advanced Code Evlauation, TRAC Code Assessment, and Stress Corrosion Cracking of PWR Steam Generator Tubing.

  17. A Novel Approach to Material Development for Advanced Reactor Systems. Quarterly progress report, Year 1 - Quarter 2

    SciTech Connect

    2000-03-27

    OAK B188 A Novel Approach to Material Development for Advanced Reactor Systems. Quarterly progress report, Year 1--Quarter 2. Year one of this project had three major goals. First, to specify, order and install a new high current ion source for more rapid and stable proton irradiation. Second, to assess the use low temperature irradiation and chromium pre-enrichment in an effort to isolate a radiation damage microstructure in stainless steels without the effects of RIS. Third, to prepare for the irradiation of reactor pressure vessel steel and Zircaloy. Program goals for Second Quarter, Year One: In year 1 quarter 2, the project goal was to complete an irradiation of an RPV steel sample and begin sample characterization. We also planned to identify sources of Zircaloy for irradiation and characterization.

  18. Light water reactor program

    SciTech Connect

    Franks, S.M.

    1994-12-31

    The US Department of Energy`s Light Water Reactor Program is outlined. The scope of the program consists of: design certification of evolutionary plants; design, development, and design certification of simplified passive plants; first-of-a-kind engineering to achieve commercial standardization; plant lifetime improvement; and advanced reactor severe accident program. These program activities of the Office of Nuclear Energy are discussed.

  19. Environmental Biosciences Program Quarterly Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2009-01-30

    Current research projects have focused Environmental Biosciences Program (EBP) talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene, low-dose ionizing radiation (gamma and neutron) and alpha radiation from plutonium. Trichloroethylene research has been conducted as a joint collaborative effort with the University of Georgia. Work on the trichloroethylene research projects has been slowed as a result of funding uncertainties. The impact of these funding uncertainties has been discussed with the United States Department of Energy (DOE). Laboratory work has been completed on several trichloroethylene risk assessment projects, and these projects have been brought to a close. Plans for restructuring the performance schedule of the remaining trichloroethylene projects have been submitted to the department. A comprehensive manuscript on the scientific basis of trichloroethylene risk assessment is in preparation. Work on the low-dose radiation risk assessment projects is also progressing at a slowed rate as a result of funding uncertainties. It has been necessary to restructure the proponency and performance schedule of these projects, with the project on Low-Dose Radiation: Epidemiology Risk Models transferred to DOE Office of Science proponency under a separate funding instrument. Research on this project will continue under the provisions of the DOE Office of Science funding instrument, with progress reported in accordance with the requirements of that funding instrument. Progress on that project will no longer be reported in quarterly reports for DE-FC09-02CH11109. Following a meeting at the Savannah River Site on May 8, 2008, a plan was submitted for development of an epidemiological cohort study and prospective medical surveillance system for the assessment of disease rates among workers at the Savannah River

  20. Reactor Safety Research Programs

    SciTech Connect

    Edler, S. K.

    1981-07-01

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  1. Reactor Safety Research Programs

    SciTech Connect

    Dotson, CW

    1980-08-01

    This document summarizes the work performed by Pacific Northwest laboratory from October 1 through December 31, 1979, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibilty of determining structural graphite strength, evaluating the feasibilty of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include the loss-of-coolant accident simulation tests at the NRU reactor, Chalk River, Canada; the fuel rod deformation and post-accident coolability tests for the ESSOR Test Reactor Program, lspra, Italy; the blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and the experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  2. Environmental Biosciences Program Quarterly Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2008-01-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene and low-dose ionizing radiation. Work on the trichloroethylene research projects has been slowed as a result of funding uncertainties. The impact of these funding uncertainties has been discussed with the DOE. Plans for restructuring the performance schedule of the trichloroethylene projects have been submitted to the department. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making.

  3. Environmental Biosciences Program Quarterly Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2007-07-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene and low-dose ionizing radiation. Work on the trichloroethylene research projects has been slowed as a result of funding uncertainties. The impact of these funding uncertainties has been discussed with the DOE. Plans for restructuring the performance schedule of the trichloroethylene projects have been submitted to the department. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making. Questions, comments or requests for further information concerning the activities under this cooperative

  4. Environmental Biosciences Program Quarterly Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2006-10-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene and low-dose ionizing radiation. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making. Questions, comments or requests for further information concerning the activities under this cooperative agreement can be forwarded to Dr. Lawrence C. Mohr in the EBP office of the Medical University of South Carolina at (843) 792-1532.

  5. Thermionic reactor program - An overview.

    NASA Technical Reports Server (NTRS)

    Beard, D. S.; Lynch, J. J.

    1972-01-01

    An overview of the AEC/NASA thermionic reactor program is presented with emphasis on the latest progress in this technology. The possible applications for utilization of thermionic reactors are reviewed and the joint AEC/NASA program approach to demonstrate thermionic technology is outlined. The thermionic reactor technology programs of France, West Germany, and the Soviet Union are highlighted.

  6. University Reactor Instrumentation Program

    SciTech Connect

    Vernetson, W.G.

    1992-11-01

    Recognizing that the University Reactor Instrumentation Program was developed in response to widespread needs in the academic community for modernization and improvement of research and training reactors at institutions such as the University of Florida, the items proposed to be supported by this grant over its two year period have been selected as those most likely to reduce foreed outages, to meet regulatory concerns that had been expressed in recent years by Nuclear Regulatory Commission inspectors or to correct other facility problems and limitations. Department of Energy Grant Number DE-FG07-90ER129969 was provided to the University of Florida Training Reactor(UFTR) facility through the US Department of Energy's University Reactor Instrumentation Program. The original proposal submitted in February, 1990 requested support for UFTR facility instrumentation and equipment upgrades for seven items in the amount of $107,530 with $13,800 of this amount to be the subject of cost sharing by the University of Florida and $93,730 requested as support from the Department of Energy. A breakdown of the items requested and total cost for the proposed UFTR facility instrumentation and equipment improvements is presented.

  7. Program status 3. quarter -- FY 1990: Confinement systems programs

    SciTech Connect

    1990-07-24

    Highlights of the DIII-D Research Operations task are: completed five weeks tokamak operations; initiated summer vent; achievement of 10.7% beta; carried out first dimensionless transport scaling experiment; completed IBW program; demonstrated divertor heat reduction with gas puffing; field task proposals presented to OFE; presentation of DIII-D program to FPAC; made presentation to Admiral Watkins; and SAN safety review. Summaries are given on research programs, operations, program development, hardware development, operations support and collaborative efforts. Brief summaries of progress on the International Cooperation task include: TORE SUPRA, ASDEX, JFT-2M, and JET. Funding for work on CIT physics was received this quarter. Several physics R and D planning tasks were initiated. Earlier in FY90, a poloidal field coil shaping system (PFC) was found for DIGNITOR. This quarter more detailed analysis has been done to optimize the design of the PFC system.

  8. Nuclear Energy Research Initiative Program (NERI) Quarterly Progress Report; New Design Equations for Swelling and Irradiation Creep in Generation IV Reactors

    SciTech Connect

    Wolfer, W G; Surh, M P; Garner, F A; Chrzan, D C; Schaldach, C; Sturgeon, J B

    2003-02-13

    The objectives of this research project are to significantly extend the theoretical foundation and the modeling of radiation-induced microstructural changes in structural materials used in Generation IV nuclear reactors, and to derive from these microstructure models the constitutive laws for void swelling, irradiation creep and stress-induced swelling, as well as changes in mechanical properties. The need for the proposed research is based on three major developments and advances over the past two decades. First, new experimental discoveries have been made on void swelling and irradiation creep which invalidate previous theoretical models and empirical constitutive laws for swelling and irradiation creep. Second, recent advances in computational methods and power make it now possible to model the complex processes of microstructure evolution over long-term neutron exposures. Third, it is now required that radiation-induced changes in structural materials over extended lifetimes be predicted and incorporated in the design of Generation IV reactors. Our approach to modeling and data analysis is a dual one in accord with both the objectives to simulate the evolution of the microstructure and to develop design equations for macroscopic properties. Validation of the models through data analysis is therefore carried out at both the microscopic and the macroscopic levels. For the microstructure models, we utilize the transmission electron microscopy results from steels irradiated in reactors and from model materials irradiated by neutrons as well as ion bombardments. The macroscopic constitutive laws will be tested and validated by analyzing density data, irradiation creep data, diameter changes of fuel elements, and post-irradiation tensile data. Validation of both microstructure models and macroscopic constitutive laws is a more stringent test of the internal consistency of the underlying science for radiation effects in structural materials for nuclear reactors.

  9. UCLA program in reactor studies: The ARIES tokamak reactor study

    SciTech Connect

    Not Available

    1991-01-01

    The ARIES research program is a multi-institutional effort to develop several visions of tokamak reactors with enhanced economic, safety, and environmental features. The aims are to determine the potential economics, safety, and environmental features of a range of possible tokamak reactors, and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. Four ARIES visions are currently planned for the ARIES program. The ARIES-1 design is a DT-burning reactor based on modest'' extrapolations from the present tokamak physics database and relies on either existing technology or technology for which trends are already in place, often in programs outside fusion. ARIES-2 and ARIES-4 are DT-burning reactors which will employ potential advances in physics. The ARIES-2 and ARIES-4 designs employ the same plasma core but have two distinct fusion power core designs; ARIES-2 utilize the lithium as the coolant and breeder and vanadium alloys as the structural material while ARIES-4 utilizes helium is the coolant, solid tritium breeders, and SiC composite as the structural material. Lastly, the ARIES-3 is a conceptual D-{sup 3}He reactor. During the period Dec. 1, 1990 to Nov. 31, 1991, most of the ARIES activity has been directed toward completing the technical work for the ARIES-3 design and documenting the results and findings. We have also completed the documentation for the ARIES-1 design and presented the results in various meetings and conferences. During the last quarter, we have initiated the scoping phase for ARIES-2 and ARIES-4 designs.

  10. The Savannah River Site's Groundwater Monitoring Program, third quarter 1991

    SciTech Connect

    Not Available

    1992-02-17

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During third quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. Analytical results from third quarter 1991 are listed in this report.

  11. Optimization of reactor configuration in coal liquefaction. Fourth quarterly report, 1 July 1992--30 September 1992

    SciTech Connect

    Comolli, A.G.; Johanson, E.S.; Lee, L.K.; Stalzer, R.M.

    1992-12-01

    This quarterly report covers activities of optimization of Reactor Configuration in Coal Liquefaction during the period July 1--September 30, 1992, at Hydrocarbon Research, Inc. in Lawrenceville and Princeton, New Jersey. This DOE contract period is from October 1, 1991 to September 30, 1993. The overall objective of the program is to achieve a new approach to liquefaction that generates an all distillates product slate at reduced cost of about $25 per barrel of crude oil equivalent. The quarterly report covers work on Laboratory Support, Laboratory Scale Operations, Technical Assessment, and Project Management.

  12. ENVIRONMENTAL TECHNOLOGY VERIFICATION PROGRAM QUARTERLY REPORT - OCTOBER 2003

    EPA Science Inventory

    The U.S. EPA Environmental Technology Verification (ETV) Program provides credible performance data for commercial-ready environmental technologies to speed their implementation for the benefit of vendors, purchasers, permitters, and the public. The ETV Quarterly Reports provide...

  13. SITE QUARTERLY REPORT HIGHLIGHTS (SUPERFUND INNOVATIVE TECHNOLOGY EVALUATION (SITE) PROGRAM)

    EPA Science Inventory

    The SITE Quarterly Report Highlights were designed to keep readers and stakeholders informed of recent developments in the SITE program. Pertinent items listed in the Highlights include (1) schedules for planned SITE Demonstrations, (2) SITE solicitation updates, (3) new developm...

  14. Solar Energy Technologies Program Newsletter - First Quarter 2010

    SciTech Connect

    2010-04-22

    The first quarter 2010 edition of the Solar Energy Technologies Program newsletter summarizes the activities for the past three months, funding opportunities, highlights from the national labs, and upcoming events.

  15. Solar Energy Technologies Program Newsletter - Fourth Quarter 2009

    SciTech Connect

    DOE Solar Energy Technologies Program

    2009-12-31

    The Fourth Quarter 2009 edition of the Solar Energy Technologies Program newsletter summarizes the activities for the past three months, funding opportunities, highlights from the national labs, and upcoming events.

  16. Stockpile Management Program quarterly report. 2. quarter 1998

    SciTech Connect

    1998-11-01

    The objective of this program is to ensure the safety and reliability of the enduring nuclear weapons stockpile by: (1) maintaining robust nuclear facilities that comprise the infrastructure needed to conduct the various laboratory programs; (2) maintaining capabilities and qualified personnel needed to successfully implement the Program and ensure availability of competencies; (3) meeting present and future production and surveillance requirements to support the enduring stockpile and other programmatic deliverables; and (4) capturing and maintaining expertise and competency in the processes and technologies required to build a complete physics package. Summaries of accomplishments are presented for approximately 30 projects managed under this program.

  17. A Novel Approach to Materials Development for Advanced Reactor Systems. Quarterly Progress Report, Year 1; Quarter 4

    SciTech Connect

    Was, G.S.; Atzmon, M.; Wang, L.

    2000-09-28

    OAK B188 A Novel Approach to Materials Development for Advanced Reactor Systems. Quarterly Progress Report, Year 1; Quarter 4. Year one of this project had three major goals. First, to specify, order and install a new high current ion source for more rapid and stable proton irradiation. Second, to assess the use of chromium pre-enrichment and hardening by combining cold-work and irradiation in an effort to isolate a radiation damage microstructure in stainless steel without the effects of RIS. Third, to initiate irradiation of reactor pressure vessel steel and Zircaloy. In year 1 quarter 4, the project goal was to begin characterization of the microstructure of model alloys of RPV steels irradiated over a range of doses. We also planned to prepare samples for microstructure isolation in stainless steels, and to receive and characterize Zircaloy samples for subsequent irradiation.

  18. High flux isotope reactor. Quarterly report, April, May, and June 1981

    SciTech Connect

    Corbett, B.L.; Poteet, K.H.

    1982-01-01

    Routine reactor operation with four end-of-cycle shutdowns resulted in an on-stream time of 92.3% for the quarter. The outer control pates were changed and a semi-annual core component inspection made.

  19. Environmental Hazards Assessment Program. Quarterly report, January 1994--March 1994

    SciTech Connect

    Not Available

    1994-05-04

    The objectives of the EHAP program are to: Develop a holistic, national basis for risk assessment, risk management and risk communication; Develop a pool of talented scientists and experts in cleanup activities, especially in human health aspects, and; Identify needs and develop programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health oriented aspects of environmental restoration and waste management. This report describes activities and reports on progress for the third quarter of year two (January-March, 1994) of the grant. To better accomplish objectives, grant efforts are organized into three major elements: The Crossroads of Humanity Series; Research, Science and Education Programs; and Program Management. The Crossroads of Humanity Series charted a new course, incorporating lessons learned during previous quarters into a series of programs designed to address environmental issues in a real world setting. Reports are included on the various research programs with milestones and deliverables from the third quarter.

  20. Breazeale Reactor Modernization Program

    SciTech Connect

    Davison, C. C.

    2003-04-16

    The Penn State Breazeale Nuclear Reactor is the longest operating licensed research reactor in the nation. The facility has played a key role in educating scientists, engineers and in providing facilities and services to researchers in many different disciplines. In order to remain a viable and effective research and educational institution, a multi-phase modernization project was proposed. Phase I was the replacement of the 25-year old reactor control and safety system along with associated wiring and hardware. This phase was fully funded by non-federal funds. Tasks identified in Phases II-V expand upon and complement the work done in Phase I to strategically implement state-of-the-art technologies focusing on identified national needs and priorities of the future.

  1. Environmental Hazards Assessment Program: Quarterly report, October--December 1993

    SciTech Connect

    Not Available

    1994-02-01

    This report describes activities and reports on progress for the second quarter (October 93 - December 93) of the second year of the grant to support the Environmental Hazards Assessment Program (EHAP). It reports progress against grant objectives and the Program Implementation Plan published at the end of the first year of the grant.

  2. Reactor service life extension program

    SciTech Connect

    Caskey, G.R.; Sindelar, R.L.; Ondrejcin, R.S.; Baumann, E.W.

    1990-01-01

    A review of the Savannah River Site production reactor systems was initiated in 1980 and led to implementation of the Reactor Materials Program in 1984 to assess reactor safety and reactor service life. The program evaluated performance of the reactor tanks, primary coolant piping, and thermal shields, components of welded construction that were fabricated from Type 304 stainless steel. The structural integrity analysis of the primary coolant system has shown that the pressure boundary is not susceptible to gross rupture, including a double ended guillotine break or equivalent large area bank. Residual service life is potentially limited by two material degradation modes, irradiation damage and intergranular stress corrosion cracking. Analysis of the structural integrity of the tanks and piping has shown that continued safe operation of the reactors for several additional decades is not limited by the material performance of the primary coolant system. Although irradiation damage has not degraded material behavior to an unacceptable level, past experience has revealed serious difficulties with repair welding on irradiated stainless steel. Stress corrosion can be mitigated by newly identified limits on impurity concentrations in the coolant water and by stress mitigation of weld residual stresses. Work continues in several areas: the effects of helium on mechanical behavior of irradiated stainless steel; improved weld methods for piping and the reactor tanks; and a surveillance program to track irradiation effects on the tank walls.

  3. Reactor service life extension program

    SciTech Connect

    Caskey, G.R.; Sindelar, R.L.; Ondrejcin, R.S.; Baumann, E.W.

    1990-12-31

    A review of the Savannah River Site production reactor systems was initiated in 1980 and led to implementation of the Reactor Materials Program in 1984 to assess reactor safety and reactor service life. The program evaluated performance of the reactor tanks, primary coolant piping, and thermal shields, components of welded construction that were fabricated from Type 304 stainless steel. The structural integrity analysis of the primary coolant system has shown that the pressure boundary is not susceptible to gross rupture, including a double ended guillotine break or equivalent large area bank. Residual service life is potentially limited by two material degradation modes, irradiation damage and intergranular stress corrosion cracking. Analysis of the structural integrity of the tanks and piping has shown that continued safe operation of the reactors for several additional decades is not limited by the material performance of the primary coolant system. Although irradiation damage has not degraded material behavior to an unacceptable level, past experience has revealed serious difficulties with repair welding on irradiated stainless steel. Stress corrosion can be mitigated by newly identified limits on impurity concentrations in the coolant water and by stress mitigation of weld residual stresses. Work continues in several areas: the effects of helium on mechanical behavior of irradiated stainless steel; improved weld methods for piping and the reactor tanks; and a surveillance program to track irradiation effects on the tank walls.

  4. Oak Ridge Research Reactor quarterly report, April, May, and June 1981

    SciTech Connect

    Hurt, S.S. III; Lance, E.D.

    1982-01-01

    The ORR operated at an average power level of 29.8 MW for 90.7% of the time during April, May, and June 1981. The reactor was shut down on eight occasions, one of which was unscheduled. Reactor downtime needed for refueling, maintenance, and checks was normal, with the reactor remaining available for operation 91.6% of the time. Maintenance activities, both mechanical and instrument, were essentially routine in nature. In-service inspection completed during the quarter is described.

  5. Parachute Creek Shale Oil Program Environmental Monitoring Program. Quarterly report, fourth quarter, October 1-December 31, 1991

    SciTech Connect

    Not Available

    1992-02-28

    The Energy Security Act of 1980 established a program to provide financial assistance to private industry in the construction and operation of commercial-scale synthetic fuels plants. The Parachute Creek Shale Oil Program is one of four projects awarded financial assistance. The Program agreed to comply with existing environmental monitoring regulations and to develop an Environmental Monitoring Plan (EMP) incorporating supplemental monitoring in the areas of water, air, solid waste, and worker health and safety during the period 1985-1992. These activities are described in a series of quarterly and annual reports. The document contains environmental compliance data collected in the fourth quarter of 1991, contents of reports on compliance data submitted to regulatory agencies, and supplemental analytical results from retorted shale pile runoff water collected following a storm event during the third quarter of 1991.

  6. New Production Reactors Program Plan

    SciTech Connect

    Not Available

    1990-12-01

    Part I of this New Production Reactors (NPR) Program Plan: describes the policy basis of the NPR Program; describes the mission and objectives of the NPR Program; identifies the requirements that must be met in order to achieve the mission and objectives; and describes and assesses the technology and siting options that were considered, the Program's preferred strategy, and its rationale. The implementation strategy for the New Production Reactors Program has three functions: Linking the design, construction, operation, and maintenance of facilities to policies requirements, and the process for selecting options. The development of an implementation strategy ensures that activities and procedures are consistent with the rationale and analysis underlying the Program. Organization of the Program. The strategy establishes plans, organizational structure, procedures, a budget, and a schedule for carrying out the Program. By doing so, the strategy ensures the clear assignment of responsibility and accountability. Management and monitoring of the Program. Finally, the strategy provides a basis for monitoring the Program so that technological, cost, and scheduling issues can be addressed when they arise as the Program proceeds. Like the rest of the Program Plan, the Implementation Strategy is a living document and will be periodically revised to reflect both progress made in the Program and adjustments in plans and policies as they are made. 21 figs., 5 tabs.

  7. University Reactor Matching Grants Program

    SciTech Connect

    John Valentine; Farzad Rahnema; Said Abdel-Khalik

    2003-02-14

    During the 2002 Fiscal year, funds from the DOE matching grant program, along with matching funds from the industrial sponsors, have been used to support research in the area of thermal-hydraulics. Both experimental and numerical research projects have been performed. Experimental research focused on two areas: (1) Identification of the root cause mechanism for axial offset anomaly in pressurized water reactors under prototypical reactor conditions, and (2) Fluid dynamic aspects of thin liquid film protection schemes for inertial fusion reactor chambers. Numerical research focused on two areas: (1) Multi-fluid modeling of both two-phase and two-component flows for steam conditioning and mist cooling applications, and (2) Modeling of bounded Rayleigh-Taylor instability with interfacial mass transfer and fluid injection through a porous wall simulating the ''wetted wall'' protection scheme in inertial fusion reactor chambers. Details of activities in these areas are given.

  8. The Savannah River Site's Groundwater Monitoring Program, third quarter 1989

    SciTech Connect

    Not Available

    1989-01-01

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During third quarter 1989 (July--September), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the third quarter is presented in the Flagging Criteria section of this document. All analytical results from third quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  9. The Savannah River Site's Groundwater Monitoring Program, second quarter 1989

    SciTech Connect

    Not Available

    1989-01-01

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During second quarter 1989 (April--June), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  10. The Savannah River Site's Groundwater Monitoring Program, second quarter 1990

    SciTech Connect

    Not Available

    1991-02-07

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During second quarter 1990 (April through June) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1990 are listed in this report.

  11. The Savannah River Site's Groundwater Monitoring Program, first quarter 1989

    SciTech Connect

    Not Available

    1989-01-01

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During first quarter 1989 (January--March), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the first quarter is presented in the Flagging Criteria section of this document. All analytical results from first quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  12. Environmental surveillance program. Quarterly progress report, July--September, 1993

    SciTech Connect

    Walker, D.W.; Hall, L.F.; Downs, J.

    1996-02-01

    This report contains data developed from monitoring site measurements and laboratory analyses of environmental samples that were collected during the period of July-September, 1993. Because some laboratory procedures are lengthy and could adversely affect the desired timeliness of reports, results of some analyses from this time period will be included in the next quarterly report. Quarterly reports, then, will be routine periodic documents that present continually updated information concerning the potential presence of environmental contaminants in the vicinity of the Idaho National Engineering Laboratory (INEL). During the third calendar quarter of 1993, Environmental Surveillance Program (ESP) measurements did not reveal unexpected levels of contaminants in any environmental samples measured or analyzed. Most of the results reported in this document are related to off-site air and ground water measurements. Future reports will include results of monitoring at additional locations and for additional environmental materials. Annual reports from the ESP will contain data generated during the previous four calendar quarters, and will display measurement trends for various combinations of locations, contaminants and environmental media. The annual report will also include more interpretive material and discussions than will normally be found in quarterly reports.

  13. Physics of reactor safety. Quarterly report, July-September 1980. Volume III

    SciTech Connect

    Not Available

    1980-11-01

    This Quarterly progress report summarizes work done during the months of July-September 1980 in Argonne National Laboratory's Applied Physics and Components Technology Divisions for the Division of Reactor Safety Research of the US Nuclear Regulatory Commission. The work in the Applied Physics Division includes reports on reactor safety modeling and assessment by members of the Reactor Safety Appraisals Section. Work on reactor core thermal-hydraulics is performed in ANL's Components Technology Division, emphasizing 3-dimensional code development for LMFBR accidents under natural convection conditions. An executive summary is provided including a statement of the findings and recommendations of the report.

  14. Novel reactor configuration for synthesis gas conversion to alcohols. Quarterly report, July 1, 1991--September 30, 1991

    SciTech Connect

    Akgerman, A.; Anthony, R.G.

    1991-12-31

    Our objectives during this quarter were to complete construction and shake down runs on our new reactor assemblies, obtain activity data on the catalyst employing the slurry reactor, incorporate pressure drop and change in number of moles options into our reactor simulation code and start experiments in the trickle bed reactor.

  15. Parachute Creek Shale Oil Program Environmental Monitoring Program. Quarterly report, third quarter, July 1-September 30, 1991

    SciTech Connect

    Not Available

    1991-11-30

    The Energy Security Act of 1980 established a program to provide financial assistance to private industry in the construction and operation of commercial-scale synthetic fuels plants. The Parachute Creek Shale Oil Program is one of four projects awarded financial assistance. The Program agreed to comply with existing environmental monitoring regulations and to develop an Environmental Monitoring Plan (EMP) incorporating supplemental monitoring in the areas of water, air, solid waste, and worker health and safety during the period 1985-1992. These activities are described in a series of quarterly and annual reports. The document contains nine compliance reports and results of comprehensive and supplemental environmental monitoring conducted during the third quarter of 1991.

  16. Oil shale programs. Sixteenth quarterly report, October-December 1979

    SciTech Connect

    Stevens, A. L.

    1980-06-01

    This document is the sixteenth in a continuing series of quarterly reports, and describes the Sandia National Laboratories oil shale activities during the period between October 1, 1979 and December 31, 1979. Sandia's major responsibility to the DOE in situ oil shale program is to provide a quantitative evaluation to DOE of the various field projects being supported by DOE in the development of commercial in situ oil shale processes. This requires the deployment of instrumentation systems and analysis techniques to evaluate key procedures and operations. In order to fulfill this responsibility, it is necessary to develop new and advanced instrumentation systems and associated deployment, recording and analysis techniques that are unique to the field projects. In addition, a rock mechanics program provides material properties, material response models, and computational methods to support the design and evaluation functions. This report describes detailed activities in these project areas over the last quarter.

  17. The Savannah River Plant's Groundwater Monitoring Program, fourth quarter 1987

    SciTech Connect

    Not Available

    1987-01-01

    The Savannah River Plant's Groundwater Monitoring Program is administered by the Environmental Monitoring Group of the Health Protection Department. During the fourth quarter of 1987 (October--December), routine monitoring was performed on monitoring wells and drinking water locations. This quarterly report includes the radioactive monitoring data from drinking water. These data were collected from SRP drinking water systems supplied by wells. Two sets of flagging criteria were established in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels but are intended to aid personnel in sample scheduling, interpretation of data, and trend identification. The first-level flagging criteria are based on detection limits or background levels in SRP groundwater. The second-level flagging criteria are based on various water standards or levels significantly above background. During the fourth quarter of 1987, Priority Pollutant analyses were conducted on LFW wells and Appendix IX analyses were conducted on FSB point-of-compliance wells. Also during this quarter, one drinking water sample exceeded the first-level flagging criteria.

  18. Environmental Biosciences Program Fourth Quarter Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2004-06-30

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene (TCE), polychlorinated biphenyls (PCBs), asbestos and low-dose ionizing radiation. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making.

  19. Environmental Biosciences Program Second Quarter Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2003-12-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene (TCE), polychlorinated biphenyls (PCBs), asbestos and low-dose ionizing radiation. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making.

  20. Environmental Biosciences Program Third Quarter Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2004-03-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene (TCE), polychlorinated biphenyls (PCBs), asbestos and low-dose ionizing radiation. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making.

  1. Environmental Biosciences Program Second Quarter Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2004-12-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene (TCE), polychlorinated biphenyls (PCBs), and low-dose ionizing radiation. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making. Questions, comments or requests for further information concerning the activities under this cooperative agreement can be forwarded to Dr. Lawrence C. Mohr in the EBP office of the Medical University of South Carolina at (843) 792-1532.

  2. Environmental Biosciences Program Fourth Quarter Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2005-06-30

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation s need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems. Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene (TCE), polychlorinated biphenyles (PCBs), and low-dose ionizing radiation. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making. Questions, comments or requests for further information concerning the activities under this cooperative agreement can be forwarded to Dr. Lawrence C. Mohr in the EBP office of the Medical University of South Carolina at (843) 792-1532.

  3. Environmental Biosciences Program Fourth Quarter Report

    SciTech Connect

    Lawrence C. Mohr, M.d.

    2003-04-30

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific program, employing a range of research initiatives to identify, study and resolve environmental health risk issues. These initiatives are consistent with the Medical University's role as a comprehensive state-supported health sciences institution and the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable the Medical University to be a national resource for the scientific investigation of environmental health issues. EBP's success in convening worldwide scientific expertise is due in part to the inherent credibility the Medical University brings to the process of addressing these complex issues.

  4. Environmental Biosciences Program Third Quarter Report

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2003-01-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific program, employing a range of research initiatives to identify, study and resolve environmental health risk issues. These initiatives are consistent with the Medical University's role as a comprehensive state-supported health sciences institution and the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable the Medical University to be a national resource for the scientific investigation of environmental health issues. EBP's success in convening worldwide scientific expertise is due in part to the inherent credibility the Medical University brings to the process of addressing these complex issues.

  5. Second Quarter Report Environmental Biosciences Program

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2002-10-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific program, employing a range of research initiatives to identify, study and resolve environmental health risk issues. These initiatives are consistent with the Medical University's role as a comprehensive state-supported health sciences institution and the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable the Medical University to be a national resource for the scientific investigation of environmental health issues. EBP's success in convening worldwide scientific expertise is due in part to the inherent credibility the Medical University brings to the process of addressing these complex issues.

  6. The Savannah River Site's Groundwater Monitoring Program: Second quarter 1992

    SciTech Connect

    Rogers, C.D. )

    1992-10-07

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During second quarter 1992, EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of criteria to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Since 1991, the flagging criteria have been based on the federal Environmental Protection Agency (EPA) drinking water standards and on method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1992 are listed in this report.

  7. The Savannah River Site's Groundwater Monitoring Program: Fourth quarter 1991

    SciTech Connect

    Rogers, C.D. )

    1992-06-02

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During fourth quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from fourth quarter 1991 are listed in this report.

  8. FY 80 heavy oil program. First quarterly report, January 1980

    SciTech Connect

    Fox, R.L.; Wayland, J.R.

    1980-05-01

    Evaluation testing of packers and computational analysis of well bore insulation for heavy oil steam recovery injection wells have been investigated this quarter. An experimental program to measure downhole steam quality is under development. Initial examination of the application of the DOE downhole steam generator program to heavy oil reservoirs has commenced. The examination of alternate extraction concepts of heavy oil has been initiated. An overburden replacement technique was evaluated both computationally and in a laboratory scale experiment. Microwave heating and in situ hydrogenation are being analyzed.

  9. Advances by the Integral Fast Reactor Program

    SciTech Connect

    Lineberry, M.J.; Pedersen, D.R.; Walters, L.C.; Cahalan, J.E.

    1991-01-01

    The advances by the Integral Fast Reactor Program at Argonne National Laboratory are the subject of this paper. The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The advances stressed in the paper include fuel irradiation performance, improved passive safety, and the development of a prototype fuel cycle facility. 14 refs.

  10. ELECTRONIC TECHNOLOGY, A SUGGESTED TWO-YEAR POST-HIGH-SCHOOL PROGRAM. SIX-QUARTER PROGRAM.

    ERIC Educational Resources Information Center

    DOBROVOLNY, JERRY S.

    THIS REPORT OUTLINES A 2-YEAR ELECTRONIC TECHNOLOGY PROGRAM ADJUSTED FROM A 4-SEMESTER TO A 6-QUARTER SEQUENCE. IT DESCRIBES THE PHILOSOPHY AND OBJECTIVES OF THE COURSE AND THE DESIRABLE CHARACTERISTICS OF THE FACULTY AND STUDENTS. IT GIVES THE CURRICULUM AND DETAILED COURSE OUTLINES FOR ALL PHASES OF THE PROGRAM AND FOR THE SUPPORTIVE STUDIES…

  11. Environmental Hazards Assessment Program. Quarterly report, July--September 1995

    SciTech Connect

    1995-10-31

    This report describes activities and reports on progress for the first quarter (July--September) of the fourth year of the grant to support the Environmental Hazards Assessment Program (EHAP) at the Medical University of South Carolina. It reports progress against the grant objectives and the Program Implementation Plan published at the end of the first year of the grant. The objectives of EHAP stated in the proposal to DOE are to: (1) develop a holistic, national basis for risk assessment, risk management, and risk communication that recognizes the direct impact of environmental hazards on the health and well-being of all; (2) develop a pool of talented scientists and experts in cleanup activities, especially in human health aspects; and (3) identify needs and develop programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health-oriented aspects of environmental restoration and waste management.

  12. Environmental Hazards Assessment Program. Quarterly report, April--June 1995

    SciTech Connect

    1995-07-31

    The objectives of this report are to: (1) develop a holistic, national basis for risk assessment, risk management, and risk communication that recognizes the direct impact of environmental hazards, both chemical and radiation, on the health and well-being of all; (2) develop a pool of talented scientists and experts in cleanup activities, especially in human health aspects; and (3) identify needs and develop programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health oriented aspects of environmental restoration and waste management. This report describes the progress made this quarter in the following areas: public and professional outreach; science programs; clinical programs; and information support and access systems.

  13. Catalyst and reactor development for a liquid-phase Fischer-Tropsch process. Quarterly technical progress report, 1 April 1981-30 June 1981

    SciTech Connect

    Brockington, J.W.; Dyer, P.N.; Pierantozzi, R.; Brain, B.W.; Bauer, J.V.

    1981-07-01

    In October 1980, Air Products and Chemicals, Inc. began a three year contract with the DOE: Catalyst and Reactor Development for a Liquid Phase Fischer-Tropsch Process. The program contains four major tasks: (1) Project Work Plan, (2) Slurry Catalyst Development, (3) Slurry Reactor Design Studies, and (4) Pilot Facility Design. This report describes work on Tasks 2 and 3 carried out in the third quarter of the contract. In Task 2, the computerized search of the Fischer-Tropsch literature was continued, and improvements were made in data processing programs. Shakedown tests were completed on the first 300 ml slurry reactor, and construction of the second and third reactors began. Five modified conventional slurry catalysts were prepared, and two batches were tested in the gas phase giving information on selectivity as a function of composition and activation. Four supported cluster catalyst were synthesized, and seven were tested in the gas phase.

  14. Methane coupling by membrane reactor. Quarterly technical progress report, September 25, 1995--December 24, 1995

    SciTech Connect

    1996-03-15

    The performance of the third type of catalytic membrane reactor configuration, with catalyst deposited in the membrane and no catalyst or inert materials in the tube side, was evaluated. The C{sub 2} selectivity obtained was about 10% due to the gas phase reaction in the empty tube side of the reactor. The membrane reactor with an oxygen-permeable dense membrane has been built. The use of a dense membrane will eliminate the loss of hydrocarbon from the tube side to the shell side, as observed in the Vycor glass membrane reactor. Also, air can be used as the oxygen source without contaminating the product. La/MgO was synthesized and will be used as the catalyst for the dense membrane reactor. This catalyst was reported in the literature to show significant improvement of C{sub 2} selectivity and yield for oxidative coupling of methane in a packed-bed reactor by using the operation mode of staged-feed of oxygen. A reactor mode for methane oxidative coupling in reactors with both distributed oxygen feed and C{sub 2} product removal was developed based on the general model of cross-flow reactors reported in the last quarterly report. A distributed oxygen feed could give rise to much higher C{sub 2} yield than the co-feed reactor as long as the space time is long enough. In the case of a two-membrane reactor, where oxygen is supplied by one membrane and products are removed through the other membrane, a high separation factor of C{sub 2} product to methane for the product-removal membrane is critical to achieve high C{sub 2} yield.

  15. DOE Safety Metrics Indicator Program (SMIP) Third Quarter FY 2001 Quarterly Report

    SciTech Connect

    Dickerson, L.S.

    2001-09-17

    The Safety Metrics Indicator Program (SMIP) retrieved 69 packaging- or transportation-related occurrences from the Occurrence Reporting and Processing System (ORPS) during the period from April 1 through June 30, 2001. Only those incidents that occur in preparation for transport, during transport, and during unloading of hazardous material are considered as packaging- or transportation-related occurrences. Other incidents with packaging and transportation (P and T) significance but not involving hazardous material (such as vehicle accidents or empty packagings) are not rated to the SMIP criteria, but are archived in the SMIP Subsidiary Database of occurrences, a sub-database of the main SMIP P and T Occurrence Database. Fifty-one of the originally-selected 69 occurrences were appropriate for classification to the SMIP criteria, 26 of which have offsite applicability. Eight of the original 69 reports are archived in a subsidiary database because they either do not involve the transport of hazardous material or they do not involve transport by vehicle, plane, boat, or rail. The others were either deleted because more thorough review revealed that they were not strictly related to P and T or they were canceled by the reporting site and removed from the ORPS. The number and severity of the selected occurrence reports (ORs) are similar with historical reporting. No adverse trends were pronounced. However, when the number of ORs obtained during the third quarter are combined with those obtained during the first and second quarters, it appears that there may be a slight increase over the 150 P and T-related ORs that are typically retrieved from the ORPS annually. On the other hand, the severity of the ORs continues to be non-alarming. None of the 51 ORs that were rated had event consequence measures (WEC) greater than 2, 31 of which were categorized as having a WEC of 1. This means that all of the third quarter fiscal year (FY) 2001 ORs had only slight consequences at

  16. Research Program of a Super Fast Reactor

    SciTech Connect

    Oka, Yoshiaki; Ishiwatari, Yuki; Liu, Jie; Terai, Takayuki; Nagasaki, Shinya; Muroya, Yusa; Abe, Hiroaki; Akiba, Masato; Akimoto, Hajime; Okumura, Keisuke; Akasaka, Naoaki; GOTO, Shoji

    2006-07-01

    Research program of a supercritical-pressure light water cooled fast reactor (Super Fast Reactor) is funded by MEXT (Ministry of Education, Culture, Sports, Science and Technology) in December 2005 as one of the research programs of Japanese NERI (Nuclear Energy Research Initiative). It consists of three programs. (1) development of Super Fast Reactor concept; (2) thermal-hydraulic experiments; (3) material developments. The purpose of the concept development is to pursue the advantage of high power density of fast reactor over thermal reactors to achieve economic competitiveness of fast reactor for its deployment without waiting for exhausting uranium resources. Design goal is not breeding, but maximizing reactor power by using plutonium from spent LWR fuel. MOX will be the fuel of the Super Fast Reactor. Thermal-hydraulic experiments will be conducted with HCFC22 (Hydro chlorofluorocarbons) heat transfer loop of Kyushu University and supercritical water loop at JAEA. Heat transfer data including effect of grid spacers will be taken. The critical flow and condensation of supercritical fluid will be studied. The materials research includes the development and testing of austenitic stainless steel cladding from the experience of PNC1520 for LMFBR. Material for thermal insulation will be tested. SCWR (Supercritical-Water Cooled Reactor) of GIF (Generation-4 International Forum) includes both thermal and fast reactors. The research of the Super Fast Reactor will enhance SCWR research and the data base. The research period will be until March 2010. (authors)

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

    SciTech Connect

    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

  18. Short contact time direct coal liquefaction using a novel batch reactor. Quarterly report, 1996

    SciTech Connect

    Klein, M.T.; Calkins, W.H.; Huang, H.

    1996-05-01

    The objective of this research is to optimize the design and operation of the bench scale batch reactor (SCTBR) for coal liquefaction at short contact times (0.01 to 10 minutes or longer). Additional objectives are to study the kinetics of direct coal liquefaction particularly at short reaction times, and to investigate the role of the organic oxygen components of coal and their reaction pathways during liquefaction. Many of those objectives have already been achieved and others are still in progress. This quarterly report covers further progress toward those objectives. Much of the previous quarterly report was concerned mainly in the retrograde reactions occurring during the liquefaction process. This report is largely devoted to the kinetics and mechanisms of the liquefaction process itself and the influence of the liquefaction solvents.

  19. Quarterly Program Progress Report April 1, 2002-June 30, 2002

    SciTech Connect

    Palafox, Neal A., MD, MPH

    2002-07-31

    DOE B188 DOE/PHRI Special Medical Care Program in the Republic of the Marshall Islands (RMI)Quarterly Program Progress Report The DOE/PHRI Special Medical Care Program continues to provide, on a year round basis, a broad spectrum of medical care to the DOE patient population. During the fourth quarter of Year 4, the following medical services were provided: (1) Annual medical examinations for the DOE patient population (see Exhibit 1 for details). (2) Medications for the DOE patient population. (3) Preventive and primary medical care to the DOE patient population in the RMI as time and resources permit. (4) Additional manpower for the outpatient clinics at Ebeye and Majuro Hospitals (see Exhibit 2 for details). (5) Ancillary services such as labs, radiology and pharmacy in coordination with Kwajalein Hospital, Majuro Hospital and the 177 Health Care Program (177 HCP). (6) Referrals to Ebeye Hospital, Majuro Hospital and Kwajalein Hospital as necessary. (7) Referrals to Straub Clinic and Hospital in Honolulu as necessary (for details see Exhibit 1). (8) Monitored and adjusted monthly annual examination schedules based on equipment failure at Kwajalein. In addition to the above, the program was also involved in the following activities during this quarter: (1) Organized and conducted continuing medical education (CME) talks for the program's RMI staff and other RMI healthcare workers. (2) Held meetings with RMI government officials and Local Atoll government officials. (3) Input past medical records into the Electronic Medical Record (EMR) system. (4) Made adjustments to and created more templates for the EMR system. (5) Coordinated with the Public Health Departments on Majuro and Ebeye. (6) Met with PEACESAT to discuss possible collaboration on high speed Internet access. (7) Looked for opportunities to expand the program's telehealth capabilities. (8) Participated in the DOE-RMI Meeting in Honolulu. (9) Finalized the agreement with the RMI Ministry of Health and

  20. Energy Programs at the Johns Hopkins University Applied Physics Laboratory, Quarterly Report, October-December 1980

    SciTech Connect

    1980-12-01

    The Johns Hopkins University Applied Physics Laboratory 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 December 1980. The Energy Quarterly Report is divided into five 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 a report on institutional problems for small-scale hydroelectric power development in the southeastern states and a list of documents published by APL in the hydroelectric program and in the geothermal program, above. The third section, Seismotectonic Investigations, contains an article on work on the geologic structure of the Danbury Quadrangle that is supported by the Reactor Safety Research Division of the Nuclear Regulatory Commission (NRC) and an in-house supported study on a new method for assessing earthquakes in intraplate regions. The fourth section, Energy Conversion and Storage Techniques, contains four articles. The first is an evaluation of the Einstein refrigerator, supported by independent IR and D funds. The second concerns fly-wheel technology development at APL supported by the Department of Energy, Division of Energy Storage (DOE/STOR). The third is a report on APL energy conservation efforts at its own buildings, and the fourth is an article on liquefied natural gas (LNG) safety evaluation, supported by the National Academy of Sciences. The fifth section explores the value of establishing an Energy Research Institute at The Johns Hopkins University.

  1. FY 80 Tar Sands program. Second quarterly report, April 1980

    SciTech Connect

    Wayland, J.R.; Fox, R.L.

    1980-09-01

    The research and development efforts in support of the Tar Sands program reservoir access and alternate extraction activities that were initiated last quarter have been continued and expanded. The development of a short course on the utilization of specialized drilling technology to Tar Sands has been investigated. The steam quality sampler is undergoing laboratory testing. Plans for a Tar Sands enhanced permeability workshop have been initiated. A special report on possible application of sand control methods to the Tar Sands steam injection test (TS-1S) experiment has been prepared. The first stage of the analysis of rf and microwave heating has been completed. The results of a series of laboratory experiments on in-situ hydrogenation are presented.

  2. The Savannah River Site Groundwater Monitoring Program Fourth Quarter 2000 (October thru December 2000)

    SciTech Connect

    Dukes, M.D.

    2001-08-02

    This report summarizes the Groundwater Monitoring Program conducted by SRS during fourth quarter 2000. It includes the analytical data, field data, data review, quality control, and other documentation for this program.

  3. Solar Energy Research Institute Biomass Program. Quarterly technical report, fourth quarter, FY 1984

    SciTech Connect

    Corder, R.E.; Lowenstein, M.Z.; McIntosh, R.

    1984-10-01

    Highlights of progress made during the fourth quarter of 1984 are summarized. Research was performed in 3 subprograms: aquatic species; anaerobic digestion; and photo/biological hydrogen. In the aquatic species subprogram, investigators: completed evaluation of energy fixation relationship between growth and lipid accumulation (Chlorella SO1); completed evaluation of metabolic blockers to enhance lipid accumulation; determined long-term sustainable productivities for Platymonas in a shallow raceway system; completed evaluation of species screening procedure using Platymonas; issued LOI for collection of microalgae strains; and completed establishment of oleaginous microalgae collection. In the anaerobic digestion subprogram, investigators: completed research on causticized straw-manure mixutre (USDA); performed chemical analysis of different swine manure fractions (Missouri); and completed preliminary evaluation of the conversion of lignocellulosics to liquid fuels with hydrogen iodide and other reductants (SERI). In the photo/biological hydrogen subprogram, investigators: isolated and characterized 10 new strains of photosynthetic bacteria; completed characterization of chemical treatments of O/sub 2/ evolution from photosystem II preparations; and submitted two papers on algal hydrogenase. Separate abstracts have been prepared for each program for inclusion in the Energy Data Base. (DMC)

  4. FY 80 Tar Sands Program first quarterly report, January 1980

    SciTech Connect

    Fox, R.L.; Wayland, J.R.

    1980-05-01

    Research and development efforts in support of the Tar Sands program well completions and stimulation subactivity and new and novel concepts task have been initiated. The objectives of the well completion and stimulation efforts are to carry out research and development in areas with significant for long-range tar sand extraction development as well as provide potential interaction and support of the near-term tar sand field experiments. Evaluation testing of packers and computational analysis of well bore insulation for tar sands steam recovery injection wells have been investigated this quarter. Production well completions for the tar sand steam drive experiment have been examined, and a program to measure downhole steam quality in the experiment is under development. Initial examination of the application of the DOE downhole steam generator program to tar sand reservoirs has commenced. The examination of new and novel concepts for extraction of tar sands has been initiated. An overburden replacement technique was evaluated both computationally and in a laboratory scale experiment. Analyses of both microwave heating and in situ hydrogenation are being initiated.

  5. Environmental Hazards Assessment Program quarterly report, January--March 1995

    SciTech Connect

    1995-04-30

    The objectives of the Environmental Hazards Assessment Program (EHAP) stated in the proposal to DOE are to: develop a holistic, national basis for risk assessment, risk management, and risk communication that recognizes the direct impact of environmental hazards on the health and well-being of all; develop a pool of talented scientists and experts in cleanup activities, especially in human health aspects; and identify needs and develop programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health oriented aspects of environmental restoration and waste management. This report describes activities and reports on progress for the third quarter (January--March) of the third year of the grant. It reports progress against these grant objectives and the Program Implementation Plan published at the end of the first year of the grant. Questions, comments, or requests for further information concerning the activities under this grant can be forwarded to Jack Davis in the EHAP office of the Medical University of South Carolina at (803) 727-6450.

  6. Methane coupling by membrane reactor. Quarterly technical progress report, June 25, 1994--September 24, 1994

    SciTech Connect

    Ma, Yi Hua

    1995-01-04

    This quarterly report describes results from the experimental studies on oxidative coupling of methane, oxygen conducting perovskite dense membrane synthesis and modeling studies of the methane coupling reaction. The focus of the experimental study is to explore the effects of varying catalyst loading, varying methane to oxygen ratios and feed conditions when the oxygen conversion is much less than 100%. Results from these studies help in understanding the effects of various parameters controlling methane coupling. Dense membrane synthesis and characterization results are presented which describe new approaches to the synthesis and characterization of these membranes. The modeling results described in this report present a theoretical fit to the experimental data on oxidative coupling of methane in fixed bed reactors. The parameters from the fit are used to predict the trends in experimental data obtained from VYCOR membrane reactors. The predicted trends are based on a theoretical model employing simplified methane coupling kinetics.

  7. Program status 1. quarter -- FY 1989: Confinement systems programs

    SciTech Connect

    1989-01-20

    Brief summaries are given for DIII-D Research Operations covering the following areas: beta and stability; confinement; boundary physics; electron cyclotron heating; ion Bernstein wave heating; current drive; tokamak operations; neutral beam operations; ECH operations; ICH operations; computer data systems; program development; and hardware development. The progress summaries on the International Cooperation task are given for the Tora Supra, HIDEX -- Nagoya Tokamak Experiment, ASDEX, JET, JFT-2M, CHS, and JT-60. Finally a brief summary of progress on the CIT physics task is given.

  8. The Savannah River Site`s Groundwater Monitoring Program, third quarter 1991

    SciTech Connect

    Not Available

    1992-02-17

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. Analytical results from third quarter 1991 are listed in this report.

  9. The Savannah River site`s groundwater monitoring program: second quarter 1997

    SciTech Connect

    Rogers, C.D.

    1997-11-01

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1997, EPD/EMS conducted extensive sampling of monitoring wells. A detailed explanation of the flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1997 are included in this report.

  10. Program status. 2nd quarter - FY 1995. Confinement systems programs

    SciTech Connect

    1995-04-18

    We conducted physics experiments: record normalized {Beta} = 4.9 achieved in VH-mode, {Beta} limits of ITER-like configurations evaluated, FWCD commissioning. The tokamak vessel was opened to atmosphere for six weeks and a number of key diagnostics for understanding the divertor were installed. The DIII-D Advisory Committee met in January to review the DIII-D program and plan. They commended us for recent progress and supported the vanadium divertor design. The U.S./Japan DIII-D steering committee met and recommended extending the agreement to the year 2000. The field work proposal for FY 96/97 was presented in Washington on March 29, 1995. A review of the DIII-D plan to install vanadium structural components as part of the new radiative divertor modification was held in Washington 31, 1995 and the panel endorsed the plans. Preliminary plans were developed with PPPL for collaborations in FY96,

  11. Program for the Analysis of Reactor Transients

    Energy Science and Technology Software Center (ESTSC)

    2002-01-29

    This program is designed for use in predicting the course of and consequence of nondestructive accidents in research and test reactor cores. It is intended primarily for the analysis of plate type research and test reactors and has been subjected to extensive comparisons with the SPERT I and SPERT II experiments. These comparisons were quite favorable for a wide range of transients up to and including melting of the clad. Favorable comparisons have also beenmore » made for TRIGA reactor pulses in pin geometry. The PARET/ANL code has been used by the RERTR (Reduced Enrichment Research and Test Reactor) Program for the safety evaluation of many of the candidate reactors for reduced enrichment.« less

  12. Program for the Analysis of Reactor Transients

    SciTech Connect

    Woodruff, W. L.; Smith, R. S.

    2002-01-29

    This program is designed for use in predicting the course of and consequence of nondestructive accidents in research and test reactor cores. It is intended primarily for the analysis of plate type research and test reactors and has been subjected to extensive comparisons with the SPERT I and SPERT II experiments. These comparisons were quite favorable for a wide range of transients up to and including melting of the clad. Favorable comparisons have also been made for TRIGA reactor pulses in pin geometry. The PARET/ANL code has been used by the RERTR (Reduced Enrichment Research and Test Reactor) Program for the safety evaluation of many of the candidate reactors for reduced enrichment.

  13. Program status 3. quarter -- FY 1994: Confinement systems programs

    SciTech Connect

    1994-07-19

    Highlights of the DIII-D Research Operations are: began experimental research operations; successfully passed radiative divertor project review; presented papers at PSI, Diagnostics, and EPS meetings and prepared IAEA synopses; new computer speeds up data acquisition; completed installation of FWCD antennas with Faraday shields; and completed report of radiative divertor preliminary design with review committee. Summaries are given for progress in research programs; operations; mechanical engineering; electrical engineering; upgrade project; operations support; and collaborative efforts. Brief summaries are given for progress on the International Cooperation task which include JET, ASDEX, TEXTOR, TORE SUPRA, JAERI, TRINTI, T-10, and ARIES support. The work in support of the development plan for the TPX (Tokamak Physics Experiment) goals and milestones continued. Progress in improving on existing models and codes leading to improved understanding of experiments is given. Highlights from the User Service Center are: 18 gigabytes of disks were purchased for exclusive fusion use; a Hewlett-Packard 9000 Series 800 T500 computer was selected as the fusion complete server; the first VAX was removed from the USC cluster; security vulnerability on HP VUE software was corrected; and a cleanup script was developed for the NERSC Cray system. A list of personnel and their assignments is given for the ITER Design Engineering task.

  14. N Reactor Deactivation Program Plan. Revision 4

    SciTech Connect

    Walsh, J.L.

    1993-12-01

    This N Reactor Deactivation Program Plan is structured to provide the basic methodology required to place N Reactor and supporting facilities {center_dot} in a radiologically and environmentally safe condition such that they can be decommissioned at a later date. Deactivation will be in accordance with facility transfer criteria specified in Department of Energy (DOE) and Westinghouse Hanford Company (WHC) guidance. Transition activities primarily involve shutdown and isolation of operational systems and buildings, radiological/hazardous waste cleanup, N Fuel Basin stabilization and environmental stabilization of the facilities. The N Reactor Deactivation Program covers the period FY 1992 through FY 1997. The directive to cease N Reactor preservation and prepare for decommissioning was issued by DOE to WHC on September 20, 1991. The work year and budget data supporting the Work Breakdown Structure in this document are found in the Activity Data Sheets (ADS) and the Environmental Restoration Program Baseline, that are prepared annually.

  15. Program summary for the Civilian Reactor Development Program

    SciTech Connect

    1982-07-01

    This Civilian Reactor Development Program document has the prime purpose of summarizing the technical programs supported by the FY 1983 budget request. This section provides a statement of the overall program objectives and a general program overview. Section II presents the technical programs in a format intended to show logical technical interrelationships, and does not necessarily follow the structure of the formal budget presentation. Section III presents the technical organization and management structure of the program.

  16. Advanced turbine systems program. Quarterly report, February 1--April 30, 1996

    SciTech Connect

    1996-12-31

    Allison continued progress on the following tasks during this quarter: (distributed generation) market study, GFATS system definition and analysis, Castcool{trademark} blade technology demonstration, low emissions combustion system, ceramic vane design and evaluation, and program management.

  17. Los Alamos National Laboratory Science Education Programs. Quarterly progress report, April 1--June 30, 1995

    SciTech Connect

    Gill, D.

    1995-09-01

    This report is quarterly progress report on the Los Alamos National Laboratory Science Education Programs. Included in the report are dicussions on teacher and faculty enhancement, curriculum improvement, student support, educational technology, and institutional improvement.

  18. The Savannah River Site`s Groundwater Monitoring Program. First quarter 1992

    SciTech Connect

    Not Available

    1992-08-03

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted during the first quarter of 1992. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program`s activities; and serves as an official document of the analytical results.

  19. The Savannah River Site`s groundwater monitoring program. First quarter 1991

    SciTech Connect

    Not Available

    1991-10-18

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted by EPD/EMS in the first quarter of 1991. In includes the analytical data, field data, data review, quality control, and other documentation for this program, provides a record of the program`s activities and rationale, and serves as an official document of the analytical results.

  20. The Savannah River Site`s Groundwater Monitoring Program, First Quarter 1996, Volumes I and II

    SciTech Connect

    Rogers, C.D.

    1996-10-22

    This report summarizes the Savanna River Site (SRS) Groundwater Monitoring Program conducted by EPD/EMS during the first quarter 1996. It includes the analytical data, field data, data review, quality control, and other documentation for this program. It also provides a record of the program`s activities and serves as an official record of the analytical results.

  1. Advanced Reactors Transition Program Resource Loaded Schedule

    SciTech Connect

    GANTT, D.A.

    2000-01-12

    The Advanced Reactors Transition (ART) Resource Loaded Schedule (RLS) provides a cost and schedule baseline for managing the project elements within the ART Program. The Fast Flux Test Facility (FETF) activities are delineated through the end of FY 2000, assuming continued standby. The Nuclear Energy (NE) Legacies and Plutonium Recycle Test Reactor (PRTR) activities are delineated through the end of the deactivation process. This revision reflects the 19 Oct 1999 baseline.

  2. Advanced Reactors Transition Program Resource Loaded Schedule

    SciTech Connect

    BOWEN, W.W.

    1999-11-08

    The Advanced Reactors Transition (ART) Resource Loaded Schedule (RLS) provides a cost and schedule baseline for managing the project elements within the ART Program. The Fast Flux Test Facility (FFTF) activities are delineated through the end of FY 2000, assuming continued standby. The Nuclear Energy (NE) Legacies and Plutonium Recycle Test Reactor (PRTR) activities are delineated through the end of the deactivation process. This document reflects the 1 Oct 1999 baseline.

  3. Mechanical design and construction new transport reactor system. Second quarterly progress report, January--March 1995

    SciTech Connect

    1995-04-01

    During the last quarter, the detailed mechanical design of the new reactor system was completed and construction of the unit was well underway. The new design includes a mixing zone, riser reactor, cyclone, and downcomer as well as instrumentation, heating elements, insulation, and a structural system for supporting the unit. Design modifications were also made to the hydrocarbon feed system. There were no changes required for the downstream sections which cool and condition the reactor product gas, recover liquid products (if any), and measure product gas make. Construction of the unit is expected to be completed by early May, with shakedown runs beginning immediately after. Installation of the electrical windings, insulation of the unit, erection, hook-up, and checkout are the main items yet to be completed. It is expected that the unit will be ready for test work in the latter part of May. The initial tests planned are both pyrolysis runs and partial oxidation runs using a simulated aromatic naphtha feed. Later this year, heavier hydrocarbon feeds will be tested.

  4. Automatic reactor model synthesis with genetic programming.

    PubMed

    Dürrenmatt, David J; Gujer, Willi

    2012-01-01

    Successful modeling of wastewater treatment plant (WWTP) processes requires an accurate description of the plant hydraulics. Common methods such as tracer experiments are difficult and costly and thus have limited applicability in practice; engineers are often forced to rely on their experience only. An implementation of grammar-based genetic programming with an encoding to represent hydraulic reactor models as program trees should fill this gap: The encoding enables the algorithm to construct arbitrary reactor models compatible with common software used for WWTP modeling by linking building blocks, such as continuous stirred-tank reactors. Discharge measurements and influent and effluent concentrations are the only required inputs. As shown in a synthetic example, the technique can be used to identify a set of reactor models that perform equally well. Instead of being guided by experience, the most suitable model can now be chosen by the engineer from the set. In a second example, temperature measurements at the influent and effluent of a primary clarifier are used to generate a reactor model. A virtual tracer experiment performed on the reactor model has good agreement with a tracer experiment performed on-site. PMID:22277238

  5. Fuel cycle programs. Quarterly progress report, October-December 1982

    SciTech Connect

    Steindler, M.J.; Bates, J.K.; Cannon, T.F.; Couture, R.A.; Deeken, P.G.; Fagan, J.E.; Gerding, T.J.; Hoh, J.C.; Kincinas, J.E.; Kolba, V.M.

    1983-08-01

    An information base has been assembled for the future analysis of concepts for disposing of /sup 85/Kr, /sup 129/I, /sup 3/H, and /sup 14/C from the nuclear fuel cycle. A blanket processing program emphasizing tritium recovery and effective heat transfer is in progress. The current experiment designated TRIO-01 is designed to test the performance of a miniaturized solid breeder blanket assembly with continuous in situ recovery of tritium. The thermal-hydraulic response of solid breeder blankets and the tritium system problems associated with liquid metal blankets are being analyzed. Thermal-hydraulic analysis is also being supplied for the First Wall/Blanket/Shield Program. Tritium needs and systems required for both tokamak and mirror fusion reactors are being supplied. Work is being done on (1) the sealing properties of fresh and altered proposed backfill materials for high-level nuclear waste in the expected hydrothermal, high-radiation environments of repositories, (2) the extent to which radioactivity might move from a nuclear waste repository because of flowing groundwater, (3) the effects of dissolved organic acids on the partitioning of /sup 241/Am and /sup 237/Np between synthetic groundwater and crushed basalt, and (4) the partitioning of a small group of toxic phenol compounds between dolomite and water. Development and testing of equipment for the destructive analysis of full-length irradiated fuel rods from the Light Water Breeder Reactor are in progress. Work has been done on: (1) the full-scale shear, (2) the dual dissolver system, (3) scrap and waste disposal, (4) the process control and data management system, and (5) analytical systems. Testing of simulated nuclear waste glasses is being done by exposing preleached Savannah River Laboratory type 131 glass to a second static leach test and by hydrating tektite glass meteorites and Pacific Northwest Laboratories type 76-68 glass in water vapor at elevated temperatures.

  6. The Savannah River Site's Groundwater Monitoring Program First Quarter 1998 (January through March 1998)

    SciTech Connect

    Hutchison, J.B.

    1999-05-26

    This report summarizes the Groundwater Monitoring Program conducted by the Savannah River Site during first quarter 1998. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official record of the analytical results.

  7. The Savannah River Site's Groundwater Monitoring Program Second Quarter 2000 (April through June 2000)

    SciTech Connect

    Dukes, M.D.

    2001-04-17

    This report summarizes the Groundwater Monitoring Program conducted by SRS during second quarter 2000. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official record of the analytical results.

  8. The Savannah River Site's Groundwater Monitoring Program - Third Quarter 1999 (July through September 1999)

    SciTech Connect

    Hutchison, J.B.

    2000-09-05

    This report summarizes the Savannah River Site Groundwater Monitoring Program during the third quarter 1999. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program activities; and serves as an official record of the analytical results.

  9. The Savannah River Site's Groundwater Monitoring Program Third Quarter 2000 (July through September 2000)

    SciTech Connect

    Dukes, M.D.

    2001-05-02

    This report summarizes the Groundwater Monitoring Program conducted by SRS during third quarter 2000. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official record of the analytical results.

  10. The Savannah River Site's Groundwater Monitoring Program First Quarter 2000 (January through March 2000)

    SciTech Connect

    Dukes, M.

    2000-11-16

    This report summarizes the Groundwater Monitoring Program conducted by SRS during first quarter 2000. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official record of the analytical results.

  11. The Savannah River Site's Groundwater Monitoring Program second quarter 1999 (April through June 1999)

    SciTech Connect

    Hutchison, J.B.

    1999-12-16

    This report summarizes the Groundwater Monitoring Program conducted by Savannah River Site during first quarter 1999. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official record of the analytical results.

  12. The Savannah River Site's Groundwater Monitoring Program Third Quarter 1998 (July through September 1998)

    SciTech Connect

    Hutchison, J.B.

    1999-05-10

    This report summarizes the Groundwater Monitoring Program conducted by SRS during third quarter 1998. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official record of the analytical results.

  13. The Savannah River Site's Groundwater Monitoring Program - Fourth Quarter 1999 (October through December 1999)

    SciTech Connect

    Hutchison, J.B.

    2000-10-12

    This report summarizes the Groundwater Monitoring Program conducted by the Savannah River site during fourth quarter 1999. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official records of the analytical results.

  14. The Savannah River Site's Groundwater Monitoring Program First Quarter 1999 (January through March 1999)

    SciTech Connect

    Hutchison, J.B.

    1999-12-08

    This report summarizes the Groundwater Monitoring Program conducted by Savannah River Site during first quarter 1999. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official record of the analytical results.

  15. The Savannah River Site's Groundwater Monitoring Program - Second Quarter 1998 (April through June 1998)

    SciTech Connect

    Hutchison, J B

    1999-02-10

    This report summarizes the Groundwater Monitoring Program conducted by SRS during second quarter 1998. It includes the analytical data, field data, data review, quality control, and other documentation for the program; provides a record of the program's activities; and serves as an official record of the analytical results.

  16. Energy programs. Quarterly report, January-March 1980

    SciTech Connect

    Not Available

    1980-01-01

    The Johns Hopkins University Applied Physics Laboratory, is engaged in developing energy resource, 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, 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, contains reports on small-scale hydroelectric investigations in the southeastern states. The third section, Seismotectonic Investigation, 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 US Naval Air Station, Norfolk, Va.

  17. Advanced reactor safety research quarterly report, October-December 1982. Volume 24

    SciTech Connect

    1984-04-01

    This report describes progress in a number of activities dealing with current safety issues relevant to both light water reactors (LWRs) and breeder reactors. The work includes a broad range of experiments to simulate accidental conditions to provide the required data base to understand important accident sequences and to serve as a basis for development and verification of the complex computer simulation models and codes used in accident analysis and licensing reviews. Such a program must include the development of analytical models, verified by experiment, which can be used to predict reactor and safety system performance under a broad variety of abnormal conditions. Current major emphasis is focused on providing information to NRC relevant to (1) its deliberations and decisions dealing with severe LWR accidents and (2) its safety evaluation of the proposed Clinch River Breeder Reactor.

  18. FY 1991 environmental research programs for the DOE Field Office, Nevada: Work plan and quarterly reports, fourth quarter report

    SciTech Connect

    1991-10-01

    This research includes a wide range of research and support activities associated with the Weapons Testing Program conducted at the Nevada Test Site (NTS). Ongoing and new environmental research programs to be conducted by DRI over the period of this contract include archaeological studies, site mitigation plans, compliance activities, and historical research; offsite community radiation monitoring support; environmental compliance activities related to state and federal regulations; hydrologic assessment of containment of underground nuclear detonations; hydrology/radionuclide investigations designed to better understand and predict the possible subsurface movement of radionuclides at the NTS; and support of various statistical and data management and design, laboratory, field, and administrative activities. In addition to these, archaeological site characterization, flood hazards for rail transportation, and paleofaunal investigations will be carried out in support of the Yucca Mountain Project. Other areas of the overall program which required DRI support are classified security activities, radiation safety and training, quality assurance and control, computer protection and historical data management, review and classification of DRI documents, and preparation of any special reports, e.g., quarterly reports, not included in the requirements of the individual projects. A new set of programs funded by the Office of Technology Development will be in place by the third quarter of FY 1991. These projects will address environmental restoration and waste management concerns, among other related topics. In accordance with specific contract requirements for each activity, DRI will produce summary, status and final reports and, in some cases, journal articles which will present the results of specific research efforts. This document contains the work plan, including project descriptions, tasks, deliverables and quarterly progress reports on each project for FY 1991.

  19. FY 1991 environmental research programs for the Nevada Operations Office: Work plan and quarterly reports, first and second quarter reports

    SciTech Connect

    1991-05-01

    The work carried out on behalf of the DOE by the Desert Research Institute (DRI) includes a wide range of research and support activities associated with the Weapons Testing Program conducted at the Nevada Test Site (NTS). Ongoing and new environmental research programs to be conducted by DRI over the period of this contract include archaeological studies, site mitigation plans, compliance activities, and historical research; offsite community radiation monitoring support; environmental compliance activities related to stat and federal regulations; hydrologic assessment of containment of underground nuclear detonations; hydrology/radionuclide investigations designed to better understand and predict the possible subsurface movement of radionuclides at the NTS; and support of various statistical and data management and design, laboratory, field, and administrative activities. In addition to these, archaeological site characterization, flood hazards for rail transportation, and paleofaunal investigations will be carried out in support of the Yucca Mountain Project. Other areas of the overall program which require DRI support are classified security activities, radiation safety and training, quality assurance and control, computer protection and historical data management, review and classification of DRI documents, and preparation of any special reports, e.g., quarterly reports, not included in the requirements of the individual projects. A new set of programs funded by the Office of Technology Development will be in place by the third quarter of FY 1991. These projects will address environmental restoration and waste management concerns, among other related topics. This document contains the Work Plan, including project descriptions, tasks, deliverables and quarterly progress reports on each project for FY 1991.

  20. The Savannah River Site`s Groundwater Monitoring Program: Third quarter 1992

    SciTech Connect

    Rogers, C.D.

    1993-02-04

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1992, EPD/EMS conducted extensive sampling of monitoring wells. Table 1 lists those well series with constituents in the groundwater above Flag 2 during third quarter 1992, organized by location. Results from all laboratory analyses are used to generate this table. Specific conductance and pH data from the field also are included in this table.

  1. Electric and hybrid vehicle program: Site operator program. Quarterly progress report, April--June, 1994 (3rd quarter of FY-1994)

    SciTech Connect

    Kiser, D.M.; Brown, H.L.

    1994-10-01

    The DOE Site Operator Program was initially established to meet the requirements of the Electric and Hybrid Vehicle Research, Development, and Demonstration Act of 1976. The Program has since evolved in response to new legislation and interests. Its mission now includes three major activity categories; advancement of Electric Vehicle (EV) technologies, development of infrastructure elements needed to support significant EV use, and increasing public awareness and acceptance of EVs. The 13 Program participants, their geographic locations, and the principal thrusts of their efforts are identified. The EV inventories of each participant are summarized. This third quarter report (FY-94) will include a summary of activities from the previous three quarters. The report section sequence has been revised to provide a more easily seen program overview, and specific operator activities are now included.

  2. Electric and Hybrid Vehicle Program, Site Operator Program. Quarterly progress report, October--December 1995 (first quarter of fiscal year 1996)

    SciTech Connect

    Francfort, J.E.; Bassett, R.R.; Briasco, S.

    1996-03-01

    This is the Site Operator Program quarterly report for USDOE electric and hybrid vehicle research. Its mission now includes the three major activity categories of advancement of electric vehicle (EV) technologies, development of infrastructure elements needed to support significant EV use and increasing public awareness and acceptance of EVs. The 11 Site Operator Program participants, their geographic locations, and the principal thrusts of their efforts are identified. The EV inventories of the site operators totals about 250 vehicles. The individual fleets are summarized.

  3. A pilot plant scale reactor/separator for ethanol from cellulosics. ERIP/DOE quarterly report no. 3 and 4

    SciTech Connect

    Dale, M.C.; Moelhman, M.; Butters, R.

    1998-12-01

    The objective of this project is to develop and demonstrate a continuous, low energy process for the conversion of cellulosics to ethanol. This process involves a pretreatment step followed by enzymatic release of sugars and the consecutive simultaneous saccharification/fermentation (SSF) of cellulose (glucans) followed by hemi-cellulose (pentosans) in a multi-stage continuous stirred reactor separator (CSRS). During quarters 3 and 4, we have completed a literature survey on cellulase production, activated one strain of Trichoderma reesei. We continued developing our proprietary Steep Delignification (SD) process for biomass pretreatment. Some problems with fermentations were traces to bad cellulase enzyme. Using commercial cellulase enzymes from Solvay & Genecor, SSF experiments with wheat straw showed 41 g/L ethanol and free xylose of 20 g/L after completion of the fermentation. From corn stover, we noted 36 g/L ethanol production from the cellulose fraction of the biomass, and 4 g/L free xylose at the completion of the SSF. We also began some work with paper mill sludge as a cellulose source, and in some preliminary experiments obtained 23 g/L ethanol during SSF of the sludge. During year 2, a 130 L process scale unit will be operated to demonstrate the process using straw or cornstalks. Co-sponsors of this project include the Indiana Biomass Grants Program, Bio-Process Innovation.

  4. EPA`s overview of the Acid Rain Program`s emissions tracking system (ETS) quarterly report process

    SciTech Connect

    Wockenfuss, M.E.

    1997-12-31

    The Acid Rain Program`s Emission Tracking System (ETS) was developed to collect, quality assure and publish the monitored and sampled emissions data collected and reported by the electric utility industry. Data are collected from fossil-fuel burning electrical generating stations that are affected by the Acid Rain Program. Since its operational start in 1993 the ETS and the data collection that surrounds it, the quarterly report process, has evolved to handle the Environmental Protection Agency`s (EPA) increased expectations of quarterly report data quality. The quarterly report process that supports the ETS provides utilities with multiple data submission options. It also provides software tools so that utilities can perform their own data assessment. This paper highlights the quarterly report process and the systems that are at the center of that process. It also analyzes utility performance relating to their 1995 and 1996 quarterly data reports and previews how the EPA`s quarterly report process will evolve over the next year.

  5. Educational Technology Program. Quarterly Technical Summary, 1 March through 31 May 1973.

    ERIC Educational Resources Information Center

    Frick, Frederick C.

    During this quarter further investigations of alternative designs for the Lincoln Training System LTS-4 project's features and subsystems continued. Software efforts proceeded concurrently in three areas: 1) system architecture, monitor, and input/output programs; 2) a new version of the Lincoln Terminal Language, LTL-2; and 3) programs to apply…

  6. The Savannah River Site`s Groundwater Monitoring Program: First quarter 1993, Volume 1

    SciTech Connect

    Rogers, C.D.

    1993-08-01

    This report summarizes the Savannah River Site (SRS) Groundwater Monitoring Program conducted by the Environmental Protection Department`s Environmental Monitoring Section (EPD/EMS) during the first quarter of 1993. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program`s activities; and serves as an official document of the analytical results.

  7. The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter 1992

    SciTech Connect

    Not Available

    1993-05-17

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted by the Environmental Protection Department`s Environmental Monitoring Section (EPD/EMS) during the fourth quarter of 1992. It includes the analytical data, field data, data review, quality control, and other documentation for this program, provides a record of the program`s activities; and serves as an official document of the analytical results.

  8. Unconventional digital reactor control without conventional programming

    SciTech Connect

    Edwards, R.M.; Johns, R.M.; Kenney, S.J.

    1995-12-31

    Recent advances in simulation technology have resulted in the capability to design, test, and implement advanced control algorithms without the need for the labor-intensive effort of writing and debugging of computer programs. This technology has been adopted for a program of experimental development of power reactor control, which is jointly sponsored by the National Science Foundation and the Electric Power Research Institute. The experimental reactor control test bed utilizes the General Atomic Mark III TRIGA reactor at the Penn State Breazeale reactor facility. Control experiments are conducted within the movable experiment technical specifications of the TRIGA. A digital controller with an experimental control algorithm is interfaced to a secondary control rod (SCR). The new technology presented in this paper utilizes a UNIX network-compatible microprocessor-based controller operating under the Wind River Systems VxWorks real-time operating system. The controller interfaces with the Math-works MATLAB/SIMULINK development environment and Real-Time Innovations 8 monitoring software remotely operated on a SPARC workstation.

  9. Quarterly report on program cost and schedule, third quarter FY 1992

    SciTech Connect

    1992-10-01

    This report is intended to provide a summary of the cost and schedule performance for the civilian Radioactive Waste Management Program. Historical and current cost profiles (extracted from the DOE Financial information System) are presented for each of the major program elements. Also included in this report are the program schedule baseline, the status of near-term program milestones and the status of the Nuclear Waste Fund revenues and disbursements. This report includes data through June 1992.

  10. Quarterly report on the Ferrocyanide Safety Program for the period ending June 30, 1995

    SciTech Connect

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

    1995-07-01

    This is the seventeenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six pans of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented.

  11. Quarterly report on the Ferrocyanide Safety Program for the period ending June 30, 1994

    SciTech Connect

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

    1994-07-01

    This is the thirteenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated With Hanford site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (Borsheim et al. 1993), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 3.0 and 4.0.

  12. Quarterly report on the Ferrocyanide Safety Program for the period ending September 30, 1995

    SciTech Connect

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

    1995-10-01

    This is the eighteenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 2.0 through 4.0.

  13. Quarterly report on the Ferrocyanide Safety Program for the period ending December 31, 1995

    SciTech Connect

    Cash, R.J.; Meacham, J.E.

    1996-01-01

    This is the nineteenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 2.0 through 4.0. 58 refs.

  14. Quarterly report on the ferrocyanide safety program for the period ending December 31, 1994

    SciTech Connect

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

    1995-01-01

    This is the fifteenth quarterly report on the progress of active addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 2.0 through 4.0. 60 refs.

  15. Electric and Hybrid Vehicle Program, Site Operator Program. Quarterly progress report for July through September 1994 (Fourth quarter of fiscal year 1994)

    SciTech Connect

    Kiser, D.M.; Brown, H.L.

    1995-03-01

    The Site Operator Program was initially established by the Department of Energy (DOE) to incorporate the electric vehicle activities dictated by the Electric and Hybrid Vehicle Research, Development and Demonstration Act of 1976. In the ensuing years, the Program has evolved in response to new legislation and interests. The Program currently includes twelve sites located in diverse geographic, metrologic, and metropolitan areas across the US. Information is shared reciprocally with a thirteenth site, not under Program contract. The vehicles are operator-owned, except for two Griffon vans. The Mission Statement of the Site Operator Program includes three major activities: advancement of electric vehicle technologies; development of infrastructure elements necessary to support significant electric vehicle use; and increasing the awareness and acceptance of electric vehicles (EVs) by the public. The current participants in the Site Operator Program are shown. The ultimate thrust of program activities varies among sites, reflecting not only the Operator`s business interests but also geographic and climate-related operating conditions. This fourth quarter report (FY-94) includes a summary of activities from the previous three quarters. The report section sequence has been revised to provide a more easily seen program overview, and specific operator activities are now found in Appendix A.

  16. Integrated Data Collection Analysis (IDCA) ProgramQuarterly Review Meeting

    SciTech Connect

    Sandstrom, Mary M.; Brown, Geoffrey W.; Warner, Kirstin F.; Sorensen, Daniel N.; Remmers, Daniel L.; Shelley, Timothy J.; Reyes, Jose A.; Phillips, Jason J.; Hsu, Peter C.; Reynolds, John G.

    2011-12-05

    On November 9 and 10, 2011 the IDCA had the annual quarterly meeting. The meeting started the afternoon of the first day with a tour of the NSWC IHD explosives safety testing and analysis facilities. The meeting on the second day addressed the formal sponsor review and further technical issues for the IDCA. Examination of the IHD equipment during the tour, lead to a long discussion on liquid test methods. The discussion resulted in revision of liquid test methods in the impact test and selection of a new liquid test standard. In addition, modifications to friction, spark and thermal test methods were discussed.

  17. Fossil Energy Program. Quarterly progress report, March 31, 1983

    SciTech Connect

    Not Available

    1983-06-01

    This quarterly report covers the progress made during the period January 1 through March 31 for the Oak Ridge National Laboratory research and development projects that are carried out in support of the increased utilization of coal and other fossil fuels as sources of clean energy. These projects are supported by various parts of DOE including Fossil Energy, Basic Energy Sciences, Office of Health and Environmental Research, Office of Environmental Compliance and Overview, the Electric Power Research Institute, and by the Tennessee Valley Authority and the EPA Office of Research and Development through inter-agency agreements with DOE.

  18. The Savannah River Plant`s Groundwater Monitoring Program - second quarter 1987

    SciTech Connect

    1996-10-01

    This report is a summary of the groundwater monitoring program conducted by the Environmental Monitoring Group of the Health Protection Department in the second quarter of 1987 and includes the analytical results, field data, and detailed documentation for this program. The purpose of this report is twofold. First, the report provides a historical record of the activities and the rationale of the program; second, it provides an official document of the analytical results.

  19. Quarterly report on program cost and schedule, second quarter FY 1990

    SciTech Connect

    1990-08-01

    This report is intended to provide a summary of the cost and schedule performance for the Civilian Radioactive Waste Management Program. Historical and current cost profiles are presented for each of the major program elements. Also included in this report is the status of the Nuclear Waste Fund revenues and disbursements. This report includes data through March 1990. 1 fig.

  20. UCLA program in reactor studies: The ARIES tokamak reactor study. Progress report, December 1, 1990--November 30, 1991

    SciTech Connect

    Not Available

    1991-12-01

    The ARIES research program is a multi-institutional effort to develop several visions of tokamak reactors with enhanced economic, safety, and environmental features. The aims are to determine the potential economics, safety, and environmental features of a range of possible tokamak reactors, and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. Four ARIES visions are currently planned for the ARIES program. The ARIES-1 design is a DT-burning reactor based on ``modest`` extrapolations from the present tokamak physics database and relies on either existing technology or technology for which trends are already in place, often in programs outside fusion. ARIES-2 and ARIES-4 are DT-burning reactors which will employ potential advances in physics. The ARIES-2 and ARIES-4 designs employ the same plasma core but have two distinct fusion power core designs; ARIES-2 utilize the lithium as the coolant and breeder and vanadium alloys as the structural material while ARIES-4 utilizes helium is the coolant, solid tritium breeders, and SiC composite as the structural material. Lastly, the ARIES-3 is a conceptual D-{sup 3}He reactor. During the period Dec. 1, 1990 to Nov. 31, 1991, most of the ARIES activity has been directed toward completing the technical work for the ARIES-3 design and documenting the results and findings. We have also completed the documentation for the ARIES-1 design and presented the results in various meetings and conferences. During the last quarter, we have initiated the scoping phase for ARIES-2 and ARIES-4 designs.

  1. Advanced reactor safety research. Quarterly report, April-June 1982. Volume 22

    SciTech Connect

    1983-10-01

    Overall objective of this work is to provide NRC a comprehensive data base essential to (1) defining key safety issues, (2) understanding risk-significant accident sequences, (3) developing and verifying models used in safety assessments, and (4) assuring the public that power reactor systems will not be licensed and placed in commercial service in the United States without appropriate consideration being given to their effects on health and safety. This report describes progress in a number of activities dealing with current safety issues relevant to both light water and breeder reactors. The work includes a broad range of experiments to simulate accidental conditions to provide the required data base to understand important accident sequences and to serve as a basis for development and verification of the complex computer simulation models and codes used in accident analysis and licensing reviews. Such a program must include the development of analytical models, verified by experiment, which can be used to predict reactor and safety system performance under a broad variety of abnormal conditions. Current major emphasis is focused on providing information to NRC relevant to (1) its deliberations and decisions dealing with severe LWR accidents, and (2) its safety evaluation of the proposed Clinch River Breeder Reactor.

  2. Gas-cooled fast breeder reactor. Quarterly progress report, February 1-April 30, 1980

    SciTech Connect

    Not Available

    1980-05-01

    Information is presented concerning the reactor vessel; reactivity control mechanisms and instrumentation; reactor internals; primary coolant circuits;core auxiliary cooling system; reactor core; systems engineering; and reactor safety and reliability;

  3. Environmental Monitoring Program summary data report -- First Calendar Quarter 1995

    SciTech Connect

    Black, S.C.; Glines, W.M.; Townsend, Y.E.

    1995-07-01

    During the first calendar quarter of 1995, air samples were collected and analyzed from 47 air particulate/halogen sampling stations, 6 noble gas sampling stations, and 16 tritiated water vapor sampling stations. Surface water samples were collected and analyzed from 1 wastewater containment pond and 10 sewage lagoons. Groundwater samples were obtained from 11 potable and 1 non-potable supply wells and 6 drinking water consumption points. Ambient radiation levels were measured at 201 locations. Water sampling was conducted for analysis of bacteria, volatile organic compounds (VOCs), inorganic constituents, and water quality as required by the federal Safe Drinking Water Act and state of Nevada regulations. Samples were taken at various locations throughout all drinking water distribution systems on the NTS.

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

    SciTech Connect

    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.

  5. The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter, 1989

    SciTech Connect

    Not Available

    1989-12-31

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During fourth quarter 1989 (October--December), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria section of this document. All analytical results from fourth quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  6. The Savannah River Site`s Groundwater Monitoring Program, third quarter 1989

    SciTech Connect

    Not Available

    1989-12-31

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During third quarter 1989 (July--September), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the third quarter is presented in the Flagging Criteria section of this document. All analytical results from third quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  7. The Savannah River Site`s Groundwater Monitoring Program, second quarter 1989

    SciTech Connect

    Not Available

    1989-12-31

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During second quarter 1989 (April--June), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  8. The Savannah River Site`s Groundwater Monitoring Program, second quarter 1990

    SciTech Connect

    Not Available

    1991-02-07

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1990 (April through June) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1990 are listed in this report.

  9. The Savannah River Site`s Groundwater Monitoring Program, first quarter 1989

    SciTech Connect

    Not Available

    1989-12-31

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During first quarter 1989 (January--March), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the first quarter is presented in the Flagging Criteria section of this document. All analytical results from first quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

  10. Engineering Development of Slurry Bubble Column Reactor (SBCR) Technology: Final quarterly technical progress no. 2, 1 July - 30 September 1995

    SciTech Connect

    Toseland, B.A.; Tischer, R.E.

    1997-12-31

    The major technical objectives of this program are threefold: (1) to develop the design tools and a fundamental understanding of the fluid dynamics of a slurry bubble column reactor to maximize reactor productivity, (2) to develop the mathematical reactor design models and gain an understanding of the hydrodynamic fundamentals under industrially relevant process conditions, and (3) to develop an understanding of the hydrodynamics and their interaction with the chemistries occurring in the bubble column reactor. Successful completion of these objectives will permit more efficient usage of the reactor column and tighter design criteria, increase overall reactor efficiency, and ensure a design that leads to stable reactor behavior when scaling up to large diameter reactors.

  11. Short-rotation woody-crops program. Quarterly progress report for period ending August 31, 1981

    SciTech Connect

    Cushman, J.H.; Ranney, J.W.

    1982-04-01

    Progress of twenty-one projects in the Short Rotation Woody Crops Program is summarized for the period June 1 through August 31, 1981. Individual quarterly reports included from each of the projects discuss accomplishments within specific project objectives and identify recent papers and publications resulting from the research. The major program activities are species screening and genetic selection, stand establishment and cultural treatment, and harvest, collection, transportation, and storage.

  12. Program status 2. quarter -- FY 1990: Fusion technology development

    SciTech Connect

    1990-05-01

    During this period, the ARIES-I blanket design team has concentrated its efforts on preparation of the final report. For the ARIES-II blanket design, two concepts are being evaluated. They are the Li self-cooled and the helium-cooled lithium breeder designs. The scoping design of the second concept has been completed. Varian EIMAC has had two tube failures in trying to assemble the X2274 tetrodes for the tests in Japan. Despite the failures it is still possible for the tubes to be ready as scheduled. Also during this quarter, the joint US/PRC integral experiment on beryllium was completed in March and the analysis of results has begun. Finally, the final design of DIII-D Divertor Material Exposure System (DiMES) was completed. Preliminary analysis by ANL of DIII-D divertor erosion, using measured plasma conditions, predicts maximum net erosion of 50 {micro}m and maximum net deposition of 23 {micro}m. Measurement by SNL-L of the 12 tiles removed in December 1989 is still pending.

  13. Enforcement actions: Significant actions resolved reactor licensees. Quarterly progress report, October--December 1994, Volume 13, No. 4, Part 1

    SciTech Connect

    1995-02-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (October--December 1994) and includes copies of letters Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

  14. Enforcement actions: Significant actions resolved reactor licensees. Volume 14, No. 2, Part 2, Quarterly progress report, April--June 1995

    SciTech Connect

    1995-08-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April--June 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

  15. Electric and Hybrid Vehicle Program; Site Operator Program. Quarterly progress report, October--December 1991

    SciTech Connect

    Warren, J.F.

    1992-01-01

    Activities during the first quarter centered around integrating the new participants into the program. A meeting of the Site Operators, in conjunction with the first meeting of the Electric Vehicle Users Task Force, was held in October. A second meeting of the Task Force was held in December. During these meetings the new contractual requirements were explained to the participants. The Site Operator Data Base was distributed and explained. The Site Operators will begin using the data base in December 1991 and will supply the operating and maintenance data to the INEL on a monthly basis. The Operators requested that they be able to have access to the data of the other Operators and it was agreed that they would be provided this on floppy disk monthly from the INEL. Presentations were made to the DOE sponsored Automotive Technology Development-Contractors Coordination Meeting in October. An overview of the program was given by EG&G. Representatives from Arizona Public Service, Texas A&M University, and York Technical College provided details of their programs and the results and future goals. Work was begun on commercializing the Versatile Data Acquisition System (VDAS). A Scope of Work has been written for a Cooperative Research and Development Agreement (CRADA) to be submitted to the USABC. If implemented, the CRADA will provide funds for the development and commercialization of the VDAS. Participants in the Site Operator Program will test prototypes of the system within their fleets, making the data available to the USABC and other interested organizations. The USABC will provide recommendations on the data to be collected. Major activities by the majority of the Operators were involved with the continued operation and demonstration of existing vehicles. In addition, several of the operators were involved in identifying and locating vehicles to be added to their fleets. A list of the vehicles in each Site Operator fleet is included as Appendix A to this report.

  16. A program toward a fusion reactor

    NASA Astrophysics Data System (ADS)

    Rebut, P.-H.; Watkins, M. L.; Gambier, D. J.; Boucher, D.

    1991-08-01

    Near breakeven conditions have been attained in the JET tokamak [Fusion Technol. 11, 13 (1987)], with beryllium as the first-wall material. A fusion triple product (nDτETi) of 8-9×1020 m-3 sec keV has been reached (within a factor of 8 of that required in a fusion reactor). However, this has only been achieved transiently. At high heating powers, an influx of impurities still limits the achievement of better performance and steady-state operation. In parallel, an improved quantitative understanding of fusion plasmas has emerged from the development of a particular plasma model. Good quantitative agreement is obtained between the model and JET data. The main predictions are also consistent with statistical scaling laws. With such a model, a predictive capability begins to emerge to define the parameters and operating conditions of a DEMO, including impurity levels. Present experimental results and model predictions suggest that impurity dilution is a major threat to a reactor. A divertor concept must be developed further to ensure impurity control before a DEMO can be constructed. A New Phase for JET is planned in which an axisymmetric pumped divertor configuration will be used to address the problems of impurity control, plasma fueling, and helium ash exhaust. It should demonstrate a concept of impurity control and the operational domain for such a device. A single Next Step facility (ITER) is a high risk strategy in terms of physics, technology, and management, since it does not provide a sufficiently sound foundation for a DEMO. A Next Step program is proposed, which could comprise several complementary facilities, each optimized with respect to specific clear objectives. In a minimum program, there could be two Next Step tokamaks, and a Materials Test Facility. Such a program would allow division of effort and sharing of risk across the various scientific and technical problems, permit cross comparison, and ensure continuity of results. It could even be

  17. Advanced Research and Technology Development Fossil Energy Materials Program. Quarterly progress report ending June 30, 1984

    SciTech Connect

    Not Available

    1984-08-01

    The objective of the AR and TD Fossil Energy Materials Program is to conduct 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. The management of the Program has been decentralized to DOE Oak Ridge Operations Office (ORO) and the Oak Ridge National Laboratory (ORNL) as technical support contractor. A substantial portion of the work on the AR and TD Fossil Energy Materials Program is performed by participating subcontractor organizations. The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FYs 1982 to 1986, in which projects are organized according to fossil energy technologies. It is the intent of the AR and TD Fossil Energy Materials Program to sponsor materials research which is generic to a number of 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.

  18. DOE reactor-pumped laser program

    SciTech Connect

    Felty, J.R.; Lipinski, R.J.; McArthur, D.A.; Pickard, P.S.

    1993-12-31

    FALCON is a high-power, steady-state, nuclear reactor-pumped laser (RPL) concept that is being developed by the Department of Energy. The FALCON program has experimentally demonstrated reactor-pumped lasing in various mixtures of xenon, argon, neon, and helium at at wavelengths of 585, 703, 725, 1271, 1733, 1792, 2032, 2630, 2650, and 3370 nm with intrinsic efficiency as high as 2.5%. The major strengths of a reactor-pumped laser are continuous high-power operation, modular construction, self-contained power, compact size, and a variety of wavelengths (from visible to infrared). These characteristics suggest numerous applications not easily accessible to other laser types. A ground-based RPL could beam its power to space for such activities as illuminating geosynchronous communication satellites in the earth`s shadow to extend their lives, beaming power to orbital transfer vehicles, removing space debris, and providing power (from earth) to a lunar base during the long lunar night. The compact size and self-contained power also makes an RPL very suitable for ship basing so that power-beaming activities could be situated around the globe. The continuous high power of an RPL opens many potential manufacturing applications such as deep-penetration welding and cutting of thick structures, wide-area hardening of metal surfaces by heat treatment or cladding application, wide-area vapor deposition of ceramics onto metal surfaces, production of sub-micron sized particles for manufacturing of ceramics, wide-area deposition of diamond-like coatings, and 3-D ceramic lithography.

  19. DOE reactor-pumped laser program

    SciTech Connect

    Felty, J.R.; Lipinski, R.J.; McArthur, D.A.; Pickard, P.S.

    1994-12-31

    FALCON is a high-power, steady-state, nuclear reactor-pumped laser (RPL) concept that is being developed by the Department of Energy. The FALCON program has experimentally demonstrated reactor-pumped lasing in various mixtures of xenon, argon, neon, and helium at wavelengths of 585, 703, 725, 1271, 1733, 1792, 2032, 2630, 2650, and 3370 nm with intrinsic efficiency as high as 2.5%. The major strengths of a reactor-pumped laser are continuous highpower operation, modular construction, self-contained power, compact size, and a variety of wavelengths (from visible to infrared). These characteristics suggest numerous applications not easily accessible to other laser types. A ground-based RPL could beam its power to space for such activities as illuminating geosynchronous communication satellites in the earth`s shadow to extend their lives, beaming power to orbital transfer vehicles, removing space debris, and providing power (from earth) to a lunar base during the long lunar night. The compact size and self-contained power also makes an RPL very suitable for ship basing so that power-beaming activities could be situated around the globe. The continuous high power of an RPL opens many potential manufacturing applications such as deep-penetration welding and cutting of thick structures, wide-area hardening of metal surfaces by heat treatment or cladding application, wide-area vapor deposition of ceramics onto metal surfaces, production of sub-micron sized particles for manufacturing of ceramics, wide-area deposition of diamond-like coatings, and 3-D ceramic lithography.

  20. DOE reactor-pumped laser program

    NASA Astrophysics Data System (ADS)

    Felty, James R.; Lipinski, Ronald J.; McArthur, David A.; Pickard, Paul S.

    1994-05-01

    FALCON is a high-power, steady-state, nuclear reactor-pumped laser (RPL) concept that is being developed by the Department of Energy. The FALCON program has experimentally demonstrated reactor-pumped lasing in various mixtures of xenon, argon, neon, and helium at wavelengths of 585, 703, 725, 1271, 1733, 1792, 2032, 2630, 2650, and 3370 nm with intrinsic efficiency as high as 2.5%. The major strengths of a reactor-pumped laser are continuous high-power operation, modular construction, self-contained power, compact size, and a variety of wavelengths (from visible to infrared). These characteristics suggest numerous applications not easily accessible to other laser types. A ground-based RPL could beam its power to space for such activities as illuminating geosynchronous communication satellites in the earth's shadow to extend their lives, beaming power to orbital transfer vehicles, removing space debris, and providing power (from earth) to a lunar base during the long lunar night. The compact size and self-contained power also makes an RPL very suitable for ship basing so that power-beaming activities could be situated around the globe. The continuous high power of an RPL opens many potential manufacturing applications such as deep-penetration welding and cutting of thick structures, wide-area hardening of metal surfaces by heat treatment or cladding application, wide-area vapor deposition of ceramics onto metal surfaces, production of sub-micron sized particles for manufacturing of ceramics, wide-area deposition of diamond- like coatings, and 3-D ceramic lithography.

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

    SciTech Connect

    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.

  2. Energy Programs at the Johns Hopkins University Applied Physics Laboratory, Quarterly Report, July-September 1980

    SciTech Connect

    1980-09-01

    The Johns Hopkins University Applied Physics Laboratory, under contracts with several agencies of the federal government, 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 September 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/RA), contains reports on small-scale hydroelectric investigations in the southeastern states. The third section, Seismotectonic Investigations, supported by the Reactor Safety Research Division of the Nuclear Regulatory Commission (NRC), reports on neotectonic investigations of the Manhattan Prong. The fourth section, Energy Conversion and Storage Techniques, contains three articles. The first is an evaluation of the Einstein refrigerator, supported by independent IR&D funds. The second concerns OTEC pilot plant performance calculations, supported by the Department of Energy/Division of Central Solar Technology (DOE/CST). The third, describing a study of landfill methane recovery, is supported by the National Park Service.

  3. Energy Programs at the Johns Hopkins University Applied Physics Laboratory, Quarterly Report, January-March 1980

    SciTech Connect

    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.

  4. Methane coupling by membrane reactor. Quarterly technical progress report, December 25, 1993--March 24, 1994

    SciTech Connect

    Not Available

    1994-06-15

    A comparison study was made between a quartz tube non-porous packed bed reactor and a 40 Angstrom pore size porous VYCOR membrane reactor using two different methane coupling catalysts. Comparisons of reactor performance of the two reactors were made on the basis of amount of methane converted, C{sub 2} selectivities and the total C{sub 2} yields. Identical flow and temperature conditions were maintained for the two reactor systems for this study. These studies appear to indicate that improved performance can be obtained in VYCOR membrane reactors. The product stream from the tube side effluent of the porous VYCOR membrane reactor was superior to that from the quartz tube non-porous reactor in terms of improved C{sub 2} selectivity. At the present stage of research, the total effluent from the membrane reactor compared slightly less favorably to the effluent from a non-porous reactor, but studies are continuing on devising a reactor configuration which increases methane throughput in the tube side of the membrane reactor which is expected to demonstrate the overall superiority of the membrane reactor. Simulation results obtained by doing a parameter study for different reactor systems showed that, for the methane coupling reaction, where the desired product formation had a lower kinetic order with respect to oxygen, improved C{sub 2} yields could be achieved in membrane reactors if the residence times were sufficiently high.

  5. Decontamination systems information and research program. Quarterly report, January 1996--March 1996

    SciTech Connect

    1996-04-01

    West Virginia University (WVU) and the US Department of Energy, Morgantown Energy Technology Center (DOE/METC) entered into a Cooperative Agreement in August 1992 titled {open_quotes}Decontamination Systems Information and Research Programs{close_quotes} (DOE Instrument No.: DE-FC21-92MC29467). Requirements stipulated by the Agreement require WVU to submit quarterly Technical Progress reports. This report contains the efforts of the research projects comprising the Agreement for the 1st calendar quarter of 1996. For the period January 1 through December 31, 1996 twelve projects have been selected for funding, and the Kanawha Valley will continue under a no-cost extension. Three new projects have also been added to the program. This document describes these projects involving decontamination, decommissioning and remedial action issues and technologies.

  6. DOE KSU EV Site Operator Program. Year 1, fourth quarter report, April 1--June 30, 1992

    SciTech Connect

    Hague, J.R.; Steinert, R.A.; Nissen-Pfrang, T.

    1992-08-01

    Kansas State University, with funding from federal, state, public, and private companies, is participating in the DOE Electric Vehicle Site Operator Program. Kansas State is demonstrating, testing, and evaluating electric of hybrid vehicle technology. This will provide organizations the opportunity to examine the latest EHV prototypes under actual operating conditions. KSU proposes to purchase one (1) electric or hybrid van and four(4) electric cars during the first two years of this five-year program. KSU has purchased one G-Van built by Conceptor Industries, Toronto, Canada and has initiated a procurement order to purchase two (2) Soleq 1992 Ford EVcort station wagons. This quarter`s report describes ongoing public relations activities and meetings as well as presenting performance data for the electric vehicles. (GHH)

  7. The Savannah River Plant`s Groundwater Monitoring Program, fourth quarter 1987

    SciTech Connect

    Not Available

    1987-12-31

    The Savannah River Plant`s Groundwater Monitoring Program is administered by the Environmental Monitoring Group of the Health Protection Department. During the fourth quarter of 1987 (October--December), routine monitoring was performed on monitoring wells and drinking water locations. This quarterly report includes the radioactive monitoring data from drinking water. These data were collected from SRP drinking water systems supplied by wells. Two sets of flagging criteria were established in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels but are intended to aid personnel in sample scheduling, interpretation of data, and trend identification. The first-level flagging criteria are based on detection limits or background levels in SRP groundwater. The second-level flagging criteria are based on various water standards or levels significantly above background. During the fourth quarter of 1987, Priority Pollutant analyses were conducted on LFW wells and Appendix IX analyses were conducted on FSB point-of-compliance wells. Also during this quarter, one drinking water sample exceeded the first-level flagging criteria.

  8. National NIF Diagnostic Program Fiscal Year 2002 Second Quarter Report

    SciTech Connect

    MacGowan, B

    2002-04-01

    Since October 2001 the development of the facility diagnostics for NIF has been funded by the NIF Director through the National NIF Diagnostic Program (NNDP). The current emphasis of the NNDP is on diagnostics for the early NIF quad scheduled to be available for experiment commissioning in FY03. During the past six months the NNDP has set in place processes for funding diagnostics, developing requirements for diagnostics, design reviews and monthly status reporting. Those processes are described in an interim management plan for diagnostics (''National NIF Diagnostic Program Interim Plan'', NIF-0081315, April 2002) and a draft Program Execution Plan (''Program Execution Plan for the National NlF Diagnostic Program'', NIF-0072083, October 2001) and documents cited therein. Work has been funded at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Naval Research Laboratory (NRL), Sandia National Laboratories (SNL), Bechtel Nevada at Los Alamos and Santa Barbara. There are no major technical risks with the early diagnostics. The main concerns relate to integration of the diagnostics into the facility, all such issues are being worked. This report is organized to show the schedule and budget status and a summary of Change Control Board actions for the past six months. The following sections then provide short descriptions of the status of each diagnostic. Where design reviews or requirements documents are cited, the documents are available on the Diagnostics file server or on request.

  9. [Enhancement of coal liquefaction efficiency with ceramic membrane reactors]. Second final quarterly report, July--September 1993

    SciTech Connect

    Not Available

    1993-12-31

    In this quarter, the gas chromatography GC calibrations of compound No. 9, No. 11 and toluene were established. The results were accurate and reproducible using wide bore capillary column. A three-component mixture -- toluene, tetraline and compound No. 9 --also could be analyzed with a modified injection procedure. The experimental procedures of modified membrane separation were finalized based on the literature review. The coal-liquid separation could be described as an ultrafiltration process. For microporous membrane separation, two transport phenomenons, molecular diffusion and convection, were the most important mechanisms. The hindrance factors of those mechanisms were necessary to evaluate the separation performance of the membrane and to design the catalytic membrane reactor. Experimentally, with the relation of rejection and permeate flux, the hindrance factors can be calculated based on the simplified Niemi-Palosaari method. In this quarter, we first tested the 40{Angstrom} pore membrane. The preliminary results indicated that the concentration polarization was observed due to the low Reynolds number, i.e. low feed flow rate. The experimental instrumentation and procedures will be improved in the future. These factors will be used to conduct the modification of the membrane and the catalytic membrane reactor. The model compound for catalytic membrane was compound No. 9, 1-[4-[2(Phenylethyl) benzyl

  10. Advanced Turbine Systems Program conceptual design and product development. Quarterly report, November 1993--January 1994

    SciTech Connect

    Karstensen, K.W.

    1994-06-01

    This Quarterly Technical Progress Report covers the period November 1, 1993, through January 31, 1994, for Phase 11 of the Advanced Turbine Systems (ATS) Program by Solar Turbines Incorporated under DOE Contract No. DE-AC421-93MC30246. The objective of this program is to provide the conceptual design and product development plan for an industrial gas turbine system to operate at a thermal efficiency of 50 percent ({open_quotes}ATS50{close_quotes}) with future improvement to 60 percent ({open_quotes}ATS60{close_quotes}). During the prior quarter Solar`s ATS Engine Design Team characterized the intercooled and recuperated (ICR) gas turbine cycle in 1-spool, 2-shaft, and 2-spool 3-shaft arrangements. Fixed and variable geometry free power turbines were compared in both arrangements and sensitivity of all combinations to component performance was determined. Full- and part-load performance were compared over a range of ambient air temperatures. During the quarter just completed, the Team defined four unique and different physical arrangements of the gas turbine components outlined above. These three arrangements were then examined in terms of their ability to support Program goals of thermal efficiency, low emissions, increased reliability, availability and maintainability (RAM), and reduced cost of electrical power production. This work, together with preliminary specification of component cooling needs, suggested that earlier studies of the pressure ratio/firing temperature/thermal efficiency relationship should be re-visited. This accomplished, the effect of total cooling air bleed requirements on thermal efficiency was determined. This will lead to the selection of hot section material capability/cooling air requirements which are able to meet Program goals. As noted in the first quarterly report, where there are apparently conflicting data, later results should take precedence due to the continuing refinement of analytical models.

  11. Short-rotation woody-crops program. Quarterly progress report for period ending May 31, 1981

    SciTech Connect

    Cushman, J.H.; Ranney, J.W.

    1982-04-01

    Progress of twenty projects in the Short Rotation Woody Crops Program is summarized for the period March 1 through May 31, 1981. Individual quarterly reports included from each of the projects discuss accomplishments within specific project objectives and identify recent papers and publications resulting from the research. The major project activities are species screening and genetic selection, stand establishment and cultural treatment, and harvest, collection, transportation, and storage.

  12. Environmental Hazards Assessment Program. Quarterly report, July--September 1993

    SciTech Connect

    Not Available

    1993-12-01

    The objectives of the EHAP program stated in the proposal to DOE are to: (1) develop a holistic, national basis for risk assessment, risk management, and risk communication which recognizes the direct impact of environmental hazards on the health and well-being of all, (2) develop a pool of talented scientists and experts in cleanup activities, especially in human health aspects, and (3) identify needs and develop programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health oriented aspects of environmental restoration and waste management.

  13. Fossil-Energy-Materials Program. Quarterly progress report for the period ending June 30, 1983

    SciTech Connect

    Not Available

    1983-08-01

    The objective of the AR and TD Fossil Energy Materials Program is to conduct 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. The management of the Program has been decentralized to DOE Oak Ridge Operations office (ORO) and the Oak Ridge National Laboratory (ORNL) as technical support contractor. The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FYs 1982-86 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.

  14. SP-100 Program: space reactor system and subsystem investigations

    SciTech Connect

    Harty, R.B.

    1983-09-30

    For a space reactor power system, a comprehensive safety program will be required to assure that no undue risk is present. This report summarizes the nuclear safety review/approval process that will be required for a space reactor system. The documentation requirements are presented along with a summary of the required contents of key documents. Finally, the aerospace safety program conducted for the SNAP-10A reactor system is summarized. The results of this program are presented to show the type of program that can be expected and to provide information that could be usable in future programs.

  15. Wind-energy program: FY 1982 second quarterly review

    SciTech Connect

    Mitchell, R.; Noun, R.J.; Flaim, T.; Deutsch, M.; Jacobs, E.; Hock, S.; Sklar, H.; Kelley, N.D.

    1982-05-01

    Progress on the following tasks is summarized: program management and planning; WECS applications in nongenerating utilities; technical feasibility of stand-alone SWECS; WECS/storage assessment and options; WECS performance/value analysis; wind energy industry analysis; wind systems coordination; wind workshops; noise and television interference studies; and advanced and innovative wind energy concepts. (MHR)

  16. Electric and hybrid vehicle program site operator program. Quarterly progress report, October 1994--December 1994 (First quarter of FY-95)

    SciTech Connect

    Kiser, D.M.; Brown, H.L.

    1995-07-01

    The DOE Site Operator Program was initially established to meet the requirements of the Electric and Hybrid Vehicle Research, Development, and Demonstration Act of 1976. The Program has since evolved in response to new legislation and interests. Its mission now includes three ma or activity categories: (1) Advancement of Electric Vehicle (EV) technologies, (2) Development of infrastructure elements needed to support significant EV use, and (3) Increasing public awareness and acceptance of EVs. The 13 Program participants, their geographic locations, and the principal thrusts of their efforts are identified in Table ES-1. The EV inventories of each participant are summarized in Table ES-2.

  17. Light Water Reactor Sustainability Program Integrated Program Plan

    SciTech Connect

    George Griffith; Robert Youngblood; Jeremy Busby; Bruce Hallbert; Cathy Barnard; Kathryn McCarthy

    2012-01-01

    Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline - even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy's Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration's energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program's plans.

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

    SciTech Connect

    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.

  19. Environmental Biosciences Program Quarterly Report for Year 3

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2006-04-30

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems. Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene and low-dose ionizing radiation. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making.

  20. Environmental Biosciences Program Third Quarter Report, Year 2

    SciTech Connect

    Lawrence C. Mohr, M.D.

    2005-03-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC09-02CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific research program, employing a range of research initiatives to identify, study and resolve environmental health risks. These initiatives are consistent with the MUSC role as a comprehensive state-supported health sciences institution and with the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable MUSC to be a national resource for the scientific investigation of environmental health issues. EBPs success as a nationally prominent research program is due, in part, to its ability to task-organize scientific expertise from multiple disciplines in addressing these complex problems Current research projects have focused EBP talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene (TCE), polychlorinated biphenyls (PCBs), and low-dose ionizing radiation. A project is also being conducted in the use of geographical information system technology to analyze population health risks related to environmental hazards as a tool for risk-based decision-making.

  1. Atmospheric Radiation Measurement program climate research facility operations quarterly report October 1 - December 31, 2008.

    SciTech Connect

    Sisterson, D. L.

    2009-01-15

    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, they 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 (FY) dating back to 1998. The US Department of Energy (DOE) 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 first quarter of FY 2009 for the Southern Great Plains (SGP) site is 2,097.60 hours (0.95 x 2,208 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,987.20 hours (0.90 x 2,208), and for the Tropical Western Pacific (TWP) locale is 1,876.80 hours (0.85 x 2,208). The OPSMAX time for the ARM Mobile Facility (AMF) is not reported this quarter because the data have not yet been released from China to the DMF for processing. 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

  2. Physics of reactor safety. Quarterly report, October-December 1980. Volume IV

    SciTech Connect

    Not Available

    1981-02-01

    The work in the Applied Physics Division includes reports on reactor safety modeling and assessment by members of the Reactor Safety Appraisals Section. Work on reactor core thermal-hydraulics is performed in ANL's Components Technology Division, emphasizing 3-dimensional code development for LMFBR accidents under natural convection conditions.

  3. Oil shale program. Eighteenth quarterly report, April 1980-June 1980

    SciTech Connect

    Stevens, A. L.

    1980-11-01

    Instrumentation and evaluation activities are in progress at two DOE-supported in situ oil shale field projects, namely, the Geokinetics Oil Shale Project near Vernal, Utah, and the Occidental Oil Shale Project near DeBeque, Colorado. In support of these projects, it is necessary to develop new and advanced instrumentation systems and associated deployment, recording and analysis techniques that are unique to the field project needs. A rock mechanics program provides material properties, material response models and computational methods for use in the design analysis, and evaluation functions. In addition, retorting studies are in progress on problems unique to the low void conditions encountered in field experiments.

  4. MUSC Environmental Biosciences Program First Quarter Report May - June, 2002

    SciTech Connect

    Lawrence C. Mohr

    2002-07-31

    In May 2002, the United States Department of Energy (DOE) signed Assistance Instrument Number DE-FC02-98CH11109 with the Medical University of South Carolina (MUSC) to support the Environmental Biosciences Program (EBP). This funding instrument replaces DOE Assistance Instrument Number DE-FC02-98CH10902. EBP is an integrated, multidisciplinary scientific program, employing a range of research initiatives to identify, study and resolve environmental health risk issues. These initiatives are consistent with the Medical University's role as a comprehensive state-supported health sciences institution and the nation's need for new and better approaches to the solution of a complex and expansive array of environment-related health problems. The intrinsic capabilities of a comprehensive health sciences institution enable the Medical University to be a national resource for the scientific investigation of environmental health issues. EBP's success in convening worldwide scientific expertise is due in part to the inherent credibility the Medical University brings to the process of addressing these complex issues.

  5. The Savannah River Site`s Groundwater Monitoring Program: Second quarter 1992

    SciTech Connect

    Rogers, C.D.

    1992-10-07

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1992, EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of criteria to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Since 1991, the flagging criteria have been based on the federal Environmental Protection Agency (EPA) drinking water standards and on method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1992 are listed in this report.

  6. The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter 1988

    SciTech Connect

    Not Available

    1989-12-31

    The Environmental Monitoring Group of the Health Protection Department administers the Savannah River Site`s Groundwater Monitoring Program. During fourth quarter 1988 (October--December), routine sampling of monitoring wells and drinking water locations was performed. The drinking water samples were collected from Savannah River Site (SRS) drinking water systems supplied by wells. Two sets of flagging criteria were established in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria section of this document. The drinking water samples were analyzed for radioactive constituents.

  7. The Savannah River Site`s Groundwater Monitoring Program: Fourth quarter 1991

    SciTech Connect

    Rogers, C.D.

    1992-06-02

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During fourth quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from fourth quarter 1991 are listed in this report.

  8. The Savannah River Site`s Groundwater Monitoring Program. Second quarter, 1991

    SciTech Connect

    Not Available

    1992-01-10

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1991 EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1991 are listed in this report.

  9. Advanced Turbine Systems Program -- Conceptual design and product development. Quarterly report, August 1--October 31, 1995

    SciTech Connect

    1995-12-31

    The objective of Phase 2 of the Advanced Turbine Systems (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. This quarterly report, addresses only Task 4, conversion of a gas turbine to a coal-fired gas turbine, which was completed during the quarter and the nine subtasks included in Task 8, design and test of critical components. These nine subtasks address six ATS technologies as follows: catalytic combustion; recuperator; autothermal fuel reformer; high temperature turbine disc; advanced control system (MMI); and ceramic materials.

  10. Decontamination systems information and research program. Quarterly report, October 1995--December 1995

    SciTech Connect

    1995-12-01

    West Virginia University (WVU) and the U.S. Department of Energy Morgantown Energy Technology Center (DOE/METC) entered into a Cooperative Agreement on August 29, 1992 titled {open_quotes}Decontamination Systems Information and Research programs{close_quotes} (DOE Instrument No. DE-FC21-92MC29467) This report contains the efforts of the research projects comprising the Agreement for the 4th calendar quarter of 1995, and is the final quarterly report deliverable required for the period ending 31 December 1995. The projects reported for the WVU Cooperative Agreement are categorized into the following three areas: 1.0 In Situ Remediation Process Development, 2.0 Advanced Product Applications Testing, and 3.0 Information Systems, Public Policy, Community Outreach, and Economics. Summaries of the significant accomplishments for the projects reported during the period 1 October 95 through 31 December 95 are presented in the following discussions.

  11. Unocal Parachute Creek Shale Oil Program. Environmental Monitoring Plan quarterly report. Fourth quarter, 1989. Rept. for 1 Oct-31 Dec 89

    SciTech Connect

    Not Available

    1990-02-28

    The Energy Security Act of 1980 established a program to provide financial assistance to private industry in the construction and operation of commerical-scale synthetic fuels plants. The Parachute Creek Shale Oil Program is one of four projects awarded financial assistance. The Program agreed to comply with existing environmental monitoring regulations and to develop an Environmental Monitoring Plan incorporating supplemental monitoring in the areas of water, air, solid waste, and worker health and safety during the period 1985-1992. These activities are described in a series of quarterly and annual reports. The report contains environmental compliance data reports, results of industrial hygiene compliance monitoring, and independent audits. Table 2-1 shows 14 of the 20 supplemental monitoring sites sampled during the quarter.

  12. Light Water Reactor Sustainability Program Integrated Program Plan

    SciTech Connect

    Kathryn McCarthy; Jeremy Busby; Bruce Hallbert; Shannon Bragg-Sitton; Curtis Smith; Cathy Barnard

    2013-04-01

    Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.

  13. Light Water Reactor Sustainability Program Integrated Program Plan

    SciTech Connect

    McCarthy, Kathryn A.; Busby, Jeremy; Hallbert, Bruce; Bragg-Sitton, Shannon; Smith, Curtis; Barnard, Cathy

    2014-04-01

    Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.

  14. The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter, 1990

    SciTech Connect

    Not Available

    1991-06-18

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted in the fourth quarter of 1990. It includes the analytical data, field data, well activity data, and other documentation for this program, provides a record of the program`s activities and rationale, and serves as an official document of the analytical results. The groundwater monitoring program includes the following activities: installation, maintenance, and abandonment of monitoring wells, environmental soil borings, development of the sampling and analytical schedule, collection and analyses of groundwater samples, review of analytical and other data, maintenance of the databases containing groundwater monitoring data, quality assurance (QA) evaluations of laboratory performance, and reports of results to waste-site facility custodians and to the Environmental Protection Section (EPS) of EPD.

  15. The Savannah River Site`s Groundwater Monitoring Program. First quarter, 1990

    SciTech Connect

    Not Available

    1990-10-18

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted in the first quarter of 1990. It includes the analytical data, field data, well activity data, and the other documentation for this program and provides a record of the program`s activities and rationale and an official document of the analytical results. The groundwater monitoring program includes the following activities: installation, maintenance, and abandonment of monitoring wells, environmental soil borings, development of the sampling and analytical schedule, collection and analyses of groundwater samples, review of the analytical data and other data, maintenance of the databases containing groundwater monitoring data and related data, quality assurance (QA) evaluations of laboratory performance, and reports of results to waste-site facility custodians and to the Environmental Protection Section (EPS) of EPD.

  16. Oak Ridge reservation federal facility agreement for the Environmental Restoration Program. Volume 1. Quarterly report, October--December 1993

    SciTech Connect

    Not Available

    1994-01-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that are specified in the Oak Ridge Reservation (ORR) 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 is October through December 1993 (first quarter of FY 1994). 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 1994 commitments.

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

    SciTech Connect

    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.

  18. Oak Ridge Reservation Federal Facility Agreement for the Environmental Restoration Program. Volume 4. Quarterly report, July--September 1993

    SciTech Connect

    Not Available

    1993-10-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that are specified in the Oak Ridge Reservation (ORR) 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 is July through September 1993 (fourth 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 approved as FY 1994 commitments.

  19. Methane coupling by membrane reactor. Quarterly technical progress report: June 25, 1993--September 24, 1993

    SciTech Connect

    Ma, Yi Hua

    1993-10-28

    Several membranes have been investigated for use in a membrane reactor. Porous VYCOR has been tested for permeability changes with temperature. Three-sectional VYCOR membranes, with a porous central section, have been fabricated and tested in the experimental setup. Catalysts for methane coupling have been reviewed in the literature and five catalysts have been selected. Modeling studies of the methane oxidative coupling reaction in different reactor configurations shows higher C{sub 2} selectivity and yield with membrane reactors as compared to conventional packed bed reactors.

  20. UNOCAL Parachute Creek Shale Oil Program. Environmental monitoring plan quarterly report. Second quarter 1988. Report for 1 April-30 June 1988

    SciTech Connect

    Not Available

    1988-08-31

    The Energy Security Act of 1980 established a program to provide financial assistance to private industry in the construction and operation of commercial-scale synthetic fuels plants. The Parachute Creek Shale Oil Program is one of four projects awarded financial assistance. The support agreement included development of an Environmental Monitoring Plan incorporating existing compliance monitoring and supplemental monitoring on water, air, solid waste, worker health and safety, and socio-economic impacts during the period 1986-1993. Twenty-two supplemental monitoring sites have been designated, to date. The report includes compliance operational monitoring data, ambient and source compliance data collected the previous quarter, and results of the industrial hygiene monitoring during the first quarter, 1988. Four pages of text precede over 718 pages of data sheets.

  1. Short Contact Time Direct Coal Liquefactionn Using a Novel Batch Reactor. Quarterly Report. May 16 - August 15, 1996

    SciTech Connect

    He Huang; Michael T. Klein; William H. Calkins

    1996-08-30

    The objective of this research is to optimize the design and operation of the bench scale batch reactor (SCTBR) for studying direct coal liquefaction at short contact times (.01 to 10 minutes or longer). Additional objectives are to study the kinetics of direct coal liquefaction particularly at short reaction times and to investigate the role of organic oxygen components of coal and their reaction pathways during coal liquefaction. Many of those objectives have already been achieved. This quarterly report discusses further kinetic studies of the liquefaction of Illinois #6 bituminous coal, Wyodak-Anderson subbituminous coal, and Pittsburgh #8 bituminous coal. The thermodynamic characteristics of the extraction stage at the start of the liquefaction process in the liquefaction of Illinois #6 coal is also discussed. Further work has also been done to attempt to clarify the role of the liquefaction solvent in the direct liquefaction process.

  2. Commercial waste and spent fuel packaging program. Quarterly report, October-December 1980

    SciTech Connect

    Hakl, A R

    1981-01-01

    This document is a report of activities performed by Westinghouse Advanced Energy Systems Division-Nevada Operations at the E-MAD Facility, Area 25, Nevada Test Site, in meeting subtask objectives during the first quarter of Fiscal Year 1981. These activities include the receipt and setup of the Plasma Welder for weld development; continuation of the Drywell Interaction Tests and the 2 kw Drywell Test; completion of the 2 kw Fuel Temperature Test and the 3 kw Soil Temperature Test; major overhaul of the Wall Mounted Handling System; installation of the major part of the Remote Air Monitor (RAM) System; and disassembly and packaging of the Reactor Maintenance, Assembly and Disassembly Building (R-MAD) windows.

  3. [Design of slurry reactor for indirect liquefaction applications: Quarterly technical status report, April--June 1991

    SciTech Connect

    Prakash, A.

    1991-07-11

    The objective of this project is to design a conceptual slurry reactor for two indirect liquefaction applications; production of methanol and production of hydrocarbon fuels via Fischer-Tropsch route. The work will be accomplished by the formulation of reactor models for both the processes and use computer simulation. Process data, kinetic and thermodynamic data, heat and mass transfer data and hydrodynamic data will be used in the mathematical models to describe the slurry reactor for each of the two processes. The cost of current vapor phase reactor systems will be compared with cost estimated for the slurry reactor systems. For the vapor phase systems, upstream and downstream processing equipments may have to be included during cost analysis for a meaningful cost comparison.

  4. [Design of slurry reactor for indirect liquefaction applications: Quarterly technical status report, July--September 1991

    SciTech Connect

    Prakash, A.

    1991-10-12

    The objective of this project is to design a conceptual slurry reactor for two indirect liquefaction applications; production of methanol and production of hydrocarbon fuels via Fischer-Tropsch route. The work will be accomplished by the formulation of reactor models for both the processes and use computer simulation. Process data, kinetic and thermodynamic data, heat and mass transfer data and hydrodynamic data will be used in the mathematical models to describe the slurry reactor for each of the two processes. The cost of current vapor phase reactor systems will be compared with cost estimated for the slurry reactor systems. For the vapor phase systems, upstream and downstream processing equipments may have to be included during cost analysis for a meaningful cost comparison.

  5. [Design of slurry reactor for indirect liquefaction applications: Quarterly technical status report, April--June 1990

    SciTech Connect

    Prakash, A.

    1990-07-10

    The objective of this project is to design a conceptual slurry reactor for two indirect liquefaction applications; production of methanol and production of hydrocarbon fuels via Fischer-Tropsch route. The work will be accomplished by the formulation of reactor models for both the processes and use computer simulation. Process data, kinetic and thermodynamic data, heat and mass transfer data and hydrodynamic data will be used in the mathematical models to describe the slurry reactor for each of the two processes. The cost of current vapor phase reactor systems will be compared with cost estimated for the slurry reactor systems. For the vapor phase systems, upstream and downstream processing equipments may have to be included during cost analysis for a meaningful cost comparison.

  6. Decontamination systems information and research program. Quarterly report, April--June 1995

    SciTech Connect

    1995-07-01

    West Virginia University (WVU) and the US Department of Energy Morgantown Energy Technology Center (DOE/METC) entered into a Cooperative Agreement on August 29, 1992 titled `Decontamination Systems Information and Research Programs`. Requirements stipulated by the Agreement require WVU to submit Technical Progress reports on a quarterly basis. This report contains the efforts of the fourteen research projects comprising the Agreement for the period April 1 to June 30, 1995. During this period three new projects have been funded by the Agreement. These projects are: (1) WERC National Design Contest, (2) Graduate Interns to the Interagency Environmental Technology Office under the National Science and Technology Council, and (3) WV High Tech Consortium.

  7. Atmospheric Radiation Measurement program climate research facility operations quarterly report April 1 - June 30, 2007.

    SciTech Connect

    Sisterson, D. L.

    2007-07-26

    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 (FY) 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 of FY 2007 for the Southern Great Plains (SGP) site is 2,074.8 hours (0.95 x 2,184 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,965.6 hours (0.90 x 2,184), and that for the Tropical Western Pacific (TWP) locale is 1,856.4 hours (0.85 x 2,184). The OPSMAX time for the ARM Mobile Facility (AMF) is 2,074.8 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

  8. Electric and hybrid vehicle program; Site Operator Program. Quarterly progress report, January--March 1992 (Second quarter of fiscal year 1992)

    SciTech Connect

    Warren, J.F.

    1992-05-01

    Activities during the second quarter included the second meeting of the Site Operators in Phoenix, AZ in late April. The meeting was held in conjunction with the Solar and Electric 500 Race activities. Delivery of vehicles ordered previously has begun, although two of the operators are experiencing some delays in receiving their vehicles. Public demonstration activities continue, with an apparent increasing level of awareness and interest being displayed by the public. Initial problems with the Site Operator Database have been corrected and revised copies of the program have been supplied to the Program participants. Operating and Maintenance data is being supplied and submitted to INEL on a monthly basis. Interest in the Site Operator Program is being reflected in requests for information from several organizations from across the country, representing a wide diversity of interests. These organizations have been referred to existing Site Operators with the explanation that the program will not be adding new participants, but that most of the existing organizations are willing to work with other groups. The exception to this was the addition of Potomac Electric Power Company (PEPCO) to the program. PEPCO has been awarded a subcontract to operate and maintain the DOE owned G-Van and Escort located in Washington, DC. They will provide data on these vehicles, as well as a Solectria Force which PEPCO has purchased. The Task Force intends to be actively involved in the infrastructure development in a wide range of areas. These include, among others, personnel development, safety, charging, and servicing. Work continues in these areas. York Technical College (YORK) has completed the draft outline for the EV Technician course. This is being circulated to organizations around the country for comments. Kansas State University (KSU) is working with a private sector company to develop a energy dispensing meter for opportunity charging in public areas.

  9. Catalyst and reactor development for a liquid phase Fischer-Tropsch process. Quarterly technical progress report, 1 October 1983-31 December 1983

    SciTech Connect

    Brian, B.W.; Carroll, W.E.; Cilen, N.; Pierantozzi, R.; Nordquist, A.F.

    1985-01-01

    Two major tasks continued in the thirteenth quarter: (1) Slurry Catalyst Development; and (2) Slurry Reactor Design Studies. In addition, work, as part of a three month contract modification, was begun to develop and improve the activity and center the selectivity for diesel fuel products of a proprietary catalyst A. This catalyst was found to produce yields in the diesel fuel region equal to or greater than the Schulz-Flory maximum with low rates of deactivation and good stability during previous extended periods of testing. A phase two extended slurry test of a proprietary catalyst B was completed this quarter. A considerable improvement in activity was observed, making this batch nearly four times as active as in the first phase of testing. The selectivity for total, gasoline and diesel, fuels was over 65 wt % in both phases of testing. The results of this test show the importance of metals loading and the need for further development work to optimize the activity and selectivity for diesel fuel of this catalyst. A short term (21 day) slurry test was conducted on another modified catalyst optimized by the gas phase screening program. Parametric gas phase screening tests were conducted on three additional catalysts. The optimum preparation and activation methods for diesel fuel selectivity will be chosen as these tests are completed. In the hydrodynamic studies, work in the 12 inch Cold-Flow Simulator was completed. A Box-Behnken experimental design was utilized to determine the statistical significance of the independent parameters studied (superficial gas velocity, solids weight fraction, solid size, etc.) on gas holdup, as well as, any synergistic effects. Correlations for gas holdup in the 12 inch and 5 inch columns were obtained. In each column, a strong linear dependence on superficial gas velocity was obtained. 6 references, 5 figures, 5 tables.

  10. Decentralization of operating reactor licensing reviews: NRR Pilot Program

    SciTech Connect

    Hannon, J.N.

    1984-07-01

    This report, which has incorporated comments received from the Commission and ACRS, describes the program for decentralization of selected operating reactor licensing technical review activities. The 2-year pilot program will be reviewed to verify that safety is enhanced as anticipated by the incorporation of prescribed management techniques and application of resources. If the program fails to operate as designed, it will be terminated.

  11. Results and recommendations from the reactor chemistry and corrosion tasks of the reactor materials program

    SciTech Connect

    Baumann, E.W.; Ondrejcin, R.S.

    1990-11-01

    Within the general context of extended service life, the Reactor Materials Program was initiated in 1984. This comprehensive program addressed material performance in SRS reactor tanks and the primary coolant or Process Water System (PWS) piping. Three of the eleven tasks concerned moderator quality and corrosion mitigation. Definition and control of the stainless steel aqueous environment is a key factor in corrosion mitigation. The Reactor Materials Program systematically investigated the SRS environment and its effect on crack initiation and propagation in stainless steel, with the objective of improving this environment. The purpose of this report is to summarize the contributions of Tasks 6, 7 and 10 of the Reactor Materials Program to the understanding and control of moderator quality and its relationship to mitigation of stress corrosion cracking.

  12. Great Lakes Regional Biomass Energy Program: Quarterly report, September 1, 1986-November 30, 1986

    SciTech Connect

    Bancroft, D.

    1987-05-01

    Stressing near-term biomass feedstock production techniques and conversion processes, the objective of the program is to increase the use of biomass energy by the public and private sectors in the Great Lakes region including Illinois, Indiana, Iowa, Michigan, Minnesota, Ohio and Wisconsin. The Great Lakes Regional Biomass Energy Program is divided into three separate operational programs. The first is the State Grant Program, which provides resources to the seven state energy offices in the region to increase their capabilities in biomass energy. State-specific activities and interagency programs are emphasized in the State Grant Program. The second, the Subcontractor Program, involves the letting of subcontracts to private organizations to address regional biomass issues and needs. The third is the In-House Technology Transfer Program in which Council staff develop biomass energy publications and reports. The primary activity this quarter has been information transfer. The program spearheaded an effort to reach the private sector and inform people about a wide range of biomass technologies. In one of the most successful events, 35 cheese manufacturers traveled to the South Alma Cheese Factory to see a woodburner supporting the process steam needs of the facility. In addition, 20 workshops were conducted throughout the region focusing on industrial wood combustion, municipal waste to energy incineration and short rotation forestry. 1 fig.

  13. Quarterly report on the Ferrocyanide Safety Program for the period ending, March 31, 1995

    SciTech Connect

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

    1995-04-01

    This quarterly report provides a status of the activities underway on the Ferrocyanide Safety Issue at the Hanford Site, including actions in response to Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 90-7 (FR 1990). In March 1991, a DNFSB implementation plan (Cash 1991) responding to the six parts of Recommendation 90-7 was prepared and sent to the DNFSB. A Ferrocyanide Safety Program Plan addressing the total Ferrocyanide Safety Program, including the six parts of DNFSB Recommendation 90-7, was released in October 1994 (DOE 1994b). Activities in the program plan are underway or have been completed, and the status of each is described in Sections 2.0 and 3.0 of this report.

  14. Quarterly report on the ferrocyanide safety program for the period ending June 30, 1996

    SciTech Connect

    Dukelow, G.T., Westinghouse Hanford

    1996-07-31

    This quarterly report provides a status of activities underway on the Ferrocyanide Safety Issue at the Hanford Site, including actions in response to Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 90-7 (FR 1990). In March 1991, a DNFSB implementation plan (Cash 1991) responding to the six parts of Recommendation 90-7 was prepared and sent to the DNFSB. A ferrocyanide safety program plan addressing the total Ferrocyanide Safety Program, including the six parts of DNFSB Recommendation 90-7, was released in October 1994 (DOE 1994b). Activities in the program plan are underway or are completed, and the status of each is described in Sections 2.0 and 3. 0 of this report.

  15. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report July 1 – September 30, 2008

    SciTech Connect

    Sisterson, DL

    2008-09-30

    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 (FY) dating back to 1998. The U.S. Department of Energy (DOE) 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 fourth quarter of FY 2008 for the Southern Great Plains (SGP) site is 2,097.60 hours (0.95 x 2,208 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,987.20 hours (0.90 x 2,208), and for the Tropical Western Pacific (TWP) locale is 1,876.80 hours (0.85 x 2,208). The OPSMAX time for the ARM Mobile Facility (AMF) is not reported this quarter because the data have not yet been released from China to the DMF for processing. 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

  16. NASA-EPA automotive thermal reactor technology program

    NASA Technical Reports Server (NTRS)

    Blankenship, C. P.; Hibbard, R. R.

    1972-01-01

    The status of the NASA-EPA automotive thermal reactor technology program is summarized. This program is concerned primarily with materials evaluation, reactor design, and combustion kinetics. From engine dynamometer tests of candidate metals and coatings, two ferritic iron alloys (GE 1541 and Armco 18-SR) and a nickel-base alloy (Inconel 601) offer promise for reactor use. None of the coatings evaluated warrant further consideration. Development studies on a ceramic thermal reactor appear promising based on initial vehicle road tests. A chemical kinetic study has shown that gas temperatures of at least 900 K to 1000 K are required for the effective cleanup of carbon monoxide and hydrocarbons, but that higher temperatures require shorter combustion times and thus may permit smaller reactors.

  17. OSU Reactor Sharing Program FY 1995 annual report

    SciTech Connect

    Higginbotham, J.F.

    1996-10-01

    This is the annual report of the activities supported under the Oregon State University Reactor Sharing Program, award number DE-FG06-NE38137. The beginning date for the award was September, 30, 1995 and the end date was September 29, 1996. Work conducted under this award is internally administered at the Radiation Center through a project tasking system. This allows for excellent quality control for the work which is performed from the point of initial contact, through the reactor application, project report generation and financial accounting. For the current fiscal year, FY95, the total cost of the reactor sharing program, including Radiation Center contributions, was $66,323.20 of which $40,000.00 was supplied by the DOE Reactor Sharing Program. The details of individual project costs is given in Table 1. The work performed for the individual projects are described in the brief work descriptions given in Table 2.

  18. Idaho National Engineering and Environmental Laboratory Offsite Environmental Surveillance Program Report: Second Quarter 1999

    SciTech Connect

    R. Evans

    1999-12-01

    The Environmental Science and Research Foundation conducts an Offsite Environmental Surveillance Program at the US Department of Energy's Idaho National Engineering and Environmental Laboratory (INEEL). The Foundation's environmental surveillance program monitors the effects, if any, of US Department of Energy (DOE) activities on the offsite environment, collects data to confirm compliance with applicable environmental laws and regulations, and observes any trends in the environmental levels of radioactivity. This report for the second quarter 1999 is based on 618 samples of air (including airborne radioactivity, fine particulates, and atmospheric moisture), precipitation, milk, drinking water, sheep, wild game tissues, and environmental radiation. All concentrations of radioactivity found in these samples were consistent with concentrations which have been found in sampling during recent quarters and which have been attributed in the past to natural background radiation, worldwide fallout from past nuclear weapons testing, and nuclear operations around the world. No measured concentrations could be directly attributed to operations at the INEEL. Concentrations in all samples were below the guidelines set by both the DOE and the US Environmental Protection Agency (EPA) for protection of the public.

  19. Idaho National Engineering and Environmental Laboratory Offsite Environmental Surveillance Program Report: Third Quarter 1999

    SciTech Connect

    R. Evans

    2000-03-01

    The Environmental Science and Research Foundation conducts an offsite environmental surveillance program for the Department of Energy's Idaho National Engineering and Environmental Laboratory (INEEL). The Foundation's environmental surveillance program monitors the effects, if any, of US Department of Energy (DOE) activities on the offsite environment, collects data to confirm compliance with applicable environmental laws and regulations, and observes any trends in the environmental levels of radioactivity. This report for the third quarter of 1999 is based on 704 samples of air, fine particulates, atmospheric moisture, precipitation, milk, and food. All concentrations of radioactivity found in these samples were consistent with concentrations which have been found in sampling during recent quarters and which have been attributed in the past to natural background radiation, worldwide fallout from past nuclear weapons testing, and nuclear operations around the world. No! measured concentrations could be directly attributed to operations at the INEEL. Concentrations in all samples were below the guidelines set by both the DOE and the US Environmental Protection Agency (EPA) for protection of the public.

  20. Idaho National Engineering and Environmental Laboratory Offsite Environmental Surveillance Program Report: First Quarter 1999

    SciTech Connect

    R. Evans

    1999-09-01

    The Environmental Science and Research Foundation conducts an Offsite Environmental Surveillance Program at the US Department of Energy's Idaho National Engineering and Environmental Laboratory (INEEL). The Foundation's environmental surveillance program monitors the effects, if any, of US Department of Energy (DOE) activities on the offsite environment, collects data to confirm compliance with applicable environmental laws and regulations, and observes any trends in the environmental levels of radioactivity. This report for the first quarter 1999 is based on 564 samples of air (including airborne radioactivity, fine particulates, and atmospheric moisture), precipitation, milk, and wild game tissues. All concentrations of radioactivity found in these samples were consistent with concentrations which have been found in sampling during recent quarters and which have been attributed in the past to natural background radiation, worldwide fallout from past nuclear weapons ! testing, an d nuclear operations around the world. No measured concentrations could be directly attributed to operations at the INEEL. Concentrations in all samples were below the guidelines set by both the DOE and the US Environmental Protection Agency (EPA) for protection of the public.

  1. Idaho National Engineering and Environmental Laboratory Offsite Environmental Surveillance Program Report: Fourth Quarter 1998

    SciTech Connect

    T. Saffle; R. Evans

    1999-08-01

    The Environmental Science and Research Foundation conducts the Offsite Environmental Surveillance Program at the US Department of Energy's Idaho National Engineering and Environmental Laboratory (INEEL). The Foundation's environmental surveillance program monitors the effects, if any, of US Department of Energy (DOE) activities on the offsite environment, collects data to confirm compliance with applicable environmental laws and regulations, and observes any trends in the environmental levels of radioactivity. This report for the fourth quarter 1998 is based on 622 samples collected of air, fine particulates, atmospheric moisture, precipitation, water, milk, potatoes, and game animals. All concentrations of radioactivity found in these samples were consistent with concentrations which have been found in sampling during recent quarters and which have been attributed in the past to natural background radioactivity, worldwide fallout from past nuclear weapons testing, an! d nuclear operations around the world. No measured concentrations could be directly attributed to operations at the INEEL, although statistical differences did exist between on-site and distant gross beta concentrations. No evidence could be found to link these differences with a specific INEEL source. Concentrations in all samples were below the guidelines set by both the DOE and the US Environmental Protection Agency (EPA) for protection of the public.

  2. Atmospheric Radiation Measurement program climate research facility operations quarterly report January 1 - March 31, 2009.

    SciTech Connect

    Sisterson, D. L.

    2009-04-23

    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 (FY) dating back to 1998. The U.S. Department of Energy (DOE) 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 second quarter of FY 2009 for the Southern Great Plains (SGP) site is 2,052.00 hours (0.95 x 2,160 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,944.00 hours (0.90 x 2,160), and for the Tropical Western Pacific (TWP) locale is 1,836.00 hours (0.85 x 2,160). The OPSMAX time for the ARM Mobile Facility (AMF) is not reported this quarter because not all of the metadata have been acquired that are used to generate this metric. 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

  3. Atmospheric Radiation Measurement program climate research facility operations quarterly report July 1 - Sep. 30, 2009.

    SciTech Connect

    Sisterson, D. L.

    2009-10-15

    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 approximately 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 (FY) dating back to 1998. The U.S. Department of Energy (DOE) 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 fourth quarter of FY 2009 for the Southern Great Plains (SGP) site is 2,097.60 hours (0.95 ? 2,208 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,987.20 hours (0.90 ? 2,208) and for the Tropical Western Pacific (TWP) locale is 1,876.8 hours (0.85 ? 2,208). The ARM Mobile Facility (AMF) was officially operational May 1 in Graciosa Island, the Azores, Portugal, so the OPSMAX time this quarter is 2,097.60 hours (0.95 x 2,208). 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 result from downtime (scheduled or unplanned) of the individual instruments. Therefore, data

  4. Atmospheric Radiation Measurement program climate research facilities quarterly report April 1 - June 30, 2009.

    SciTech Connect

    Sisterson, D. L.

    2009-07-14

    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 approximately 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 (FY) dating back to 1998. The U.S. Department of Energy (DOE) 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 of FY 2009 for the Southern Great Plains (SGP) site is 2,074.80 hours (0.95 x 2,184 hours this quarter); for the North Slope Alaska (NSA) locale it is 1,965.60 hours (0.90 x 2,184); and for the Tropical Western Pacific (TWP) locale it is 1,856.40 hours (0.85 x 2,184). The ARM Mobile Facility (AMF) was officially operational May 1 in Graciosa Island, the Azores, Portugal, so the OPSMAX time this quarter is 1390.80 hours (0.95 x 1464). 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

  5. Neutron irradiation experiments for fusion reactor materials through JUPITER program

    NASA Astrophysics Data System (ADS)

    Abe, K.; Kohyama, A.; Namba, C.; Wiffen, F. W.; Jones, R. H.

    1998-10-01

    A Japan-USA Program of irradiation experiments for fusion research, "JUPITER", has been established as a 6 year program from 1995 to 2000. The goal is to study "the dynamic behavior of fusion reactor materials and their response to variable and complex irradiation environment". This is phase-three of the collaborative program, which follows RTNS-II Program (Phase-1: 1982-1986) and FFTF/MOTA Program (Phase-2: 1987-1994). This program is to provide a scientific basis for application of materials performance data, generated by fission reactor experiments, to anticipated fusion environments. Following the systematic study on cumulative irradiation effects, done through FFTF/MOTA Program, JUPITER is emphasizing the importance of dynamic irradiation effects on materials performance in fusion systems. The irradiation experiments in this program include low activation structural materials, functional ceramics and other innovative materials. The experimental data are analyzed by theoretical modeling and computer simulation to integrate the above effects.

  6. AR and TD Fossil-Energy Materials Program. Quarterly progress report, March 31, 1982

    SciTech Connect

    Bradley, R.A.

    1982-07-01

    The objective of the AR and TD Fossil Energy Materials Program is to conduct 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. The management of the Program has been decentralized to DOE Oak Ridge Operations Office (ORO) and the Oak Ridge National Laboratory (ORNL) as technical support contractor. All subcontractor work is technically monitored by Program staff members at ORNL and Argonne National Laboratory (ANL). The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. Distribution is as shown on pages 397-403. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1982-86 (Ref. 1) in which projects are organized according to fossil energy technologies.

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

    SciTech Connect

    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.

  8. Reduced-Enrichment Research and Test Reactor Program: Environmental assessment

    SciTech Connect

    Not Available

    1980-05-01

    The principal program objective and principal part of the proposed action is to improve the proliferation resistance of nuclear fuels used in research and test reactors by providing the technical means (through technical development, design, and testing) for reducing the uranium enrichment requirements of these fuels to substantially less than the 90 to 93% enrichment currently used. Operator acceptance of the reduced-enrichment-uranium (REU) fuel alternative will require minimizing of reactor performance reduction, fuel cycle cost increases, the number of new safety and licensing issues raised, and reactor and facility modifications. The other part of the proposed action is to assure the capability for commercial production and supply of REU fuel for use both in the US and abroad. The RERTR Program scope is limited to generic design studies, technical support to reactor operating organizations in preparing for conversions to REU fuels, fuel development, fuel demonstrations, and technical support for commercialization of REU fuels. This environmental assessment addresses the environmental consequences of RERTR Program activities and of specific conversions of typical reactors (the Ford Nuclear Reactor and one or two other to-be-designated demonstrations) to REU-fuel cycles, including domestic and international shipments of enriched uranium pertinent to the conduct of RERTR Program activities.

  9. Calorimetry exchange program amendment to 3rd quarter CY92 report LLNL isotopic data

    SciTech Connect

    Barnett, T.M.

    1996-08-01

    This report is a series of ammendments to the Calorimetry Exchange Quarterly Data Report for third quarter CY1992. The ammendment is needed due to reporting errors encountered in the Lawrence Livermore National Laboratory isotopic data.

  10. Safety program considerations for space nuclear reactor systems

    SciTech Connect

    Cropp, L.O.

    1984-08-01

    This report discusses the necessity for in-depth safety program planning for space nuclear reactor systems. The objectives of the safety program and a proposed task structure is presented for meeting those objectives. A proposed working relationship between the design and independent safety groups is suggested. Examples of safety-related design philosophies are given.

  11. Reactor Material Program Fracture Toughness of Type 304 Stainless Steel

    SciTech Connect

    Awadalla, N.G.

    2001-03-28

    This report describes the experimental procedure for Type 304 Stainless Steel fracture toughness measurements and the application of results. Typical toughness values are given based on the completed test program for the Reactor Materials Program (RMP). Test specimen size effects and limitations of the applicability in the fracture mechanics methodology are outlined as well as a brief discussion on irradiation effects.

  12. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report January 1 - March 31, 2005

    SciTech Connect

    Sisterson, DL

    2005-03-31

    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 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 United States 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 this second quarter for the Southern Great Plains (SGP) site is 2052 hours (0.95 × 2,160 hours this quarter). The annual OPSMAX for the North Slope Alaska (NSA) site is 1944 hours (0.90 × 2,160), and that for the Tropical Western Pacific (TWP) site is 1836 hours (0.85 × 2,160). 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 ACRF 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 represents the average percent of the time (24 hours per day, 90

  13. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report October 1 - December 31, 2005

    SciTech Connect

    Sisterson, DL

    2005-12-31

    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. 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 2,097.6 hours (0.95 × 2,208 hours this quarter). The OPSMAX for the North Slope of Alaska (NSA) locale is 1,987.2 hours (0.90 × 2,208), and that for the Tropical Western Pacific (TWP) locale is 1,876.8 hours (0.85 × 2,208). The OPSMAX time for the ARM Mobile Facility (AMF) is 2,097.6 hours (0.95 × 2,208). 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 ACRF 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

  14. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report January-March 2006

    SciTech Connect

    Sisterson, DL

    2006-03-31

    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. 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 second quarter for the Southern Great Plains (SGP) site is 2,052 hours (0.95 × 2,160 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,944 hours (0.90 × 2,160), and that for the Tropical Western Pacific (TWP) locale is 1,836 hours (0.85 × 2,160). The OPSMAX time for the ARM Mobile Facility (AMF) is 2,052 hours (0.95 × 2,160). 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

  15. Oak Ridge Reservation Federal Facility agreement quarterly report for the Environmental Restoration Program, January--March 1994. Volume 2

    SciTech Connect

    Not Available

    1994-04-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that 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 herein is January through March 1994 (second quarter of FY 1994). 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 1994 commitments. Section 2 covers significant accomplishments. Section 3 discusses technical status at the Oak Ridge Y-12 Plant, Oak Ridge National Laboratory, Oak Ridge K-25 Site, and Clinch River. Technical oversight and technical programs are also covered. Section 4 covers responds action contractor assignments.

  16. The Savannah River Site`s groundwater monitoring program. Third quarter 1990

    SciTech Connect

    Not Available

    1991-05-06

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1990 (July through September) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. All analytical results from third quarter 1990 are listed in this report, which is distributed to all site custodians. One or more analytes exceeded Flag 2 in 87 monitoring well series. Analytes exceeded Flat 2 for the first since 1984 in 14 monitoring well series. In addition to groundwater monitoring, EPD/EMS collected drinking water samples from SRS drinking water systems supplied by wells. The drinking water samples were analyzed for radioactive constituents.

  17. Decontamination Systems Information and Research Program. Quarterly technical progress report, January 1--March 31, 1994

    SciTech Connect

    Not Available

    1994-05-01

    West Virginia University (WVU) and the US DOE Morgantown Energy Technology Center (METC) entered into a Cooperative Agreement on August 29, 1992 entitled ``Decontamination Systems Information and Research Programs.`` Stipulated within the Agreement is the requirement that WVU submit to METC a series of Technical Progress Reports on a quarterly basis. This report comprises the first Quarterly Technical Progress Report for Year 2 of the Agreement. This report reflects the progress and/or efforts performed on the sixteen (16) technical projects encompassed by the Year 2 Agreement for the period of January 1 through March 31, 1994. In situ bioremediation of chlorinated organic solvents; Microbial enrichment for enhancing in-situ biodegradation of hazardous organic wastes; Treatment of volatile organic compounds (VOCs) using biofilters; Drain-enhanced soil flushing (DESF) for organic contaminants removal; Chemical destruction of chlorinated organic compounds; Remediation of hazardous sites with steam reforming; Soil decontamination with a packed flotation column; Use of granular activated carbon columns for the simultaneous removal of organics, heavy metals, and radionuclides; Monolayer and multilayer self-assembled polyion films for gas-phase chemical sensors; Compact mercuric iodide detector technology development; Evaluation of IR and mass spectrometric techniques for on-site monitoring of volatile organic compounds; A systematic database of the state of hazardous waste clean-up technologies; Dust control methods for insitu nuclear and hazardous waste handling; Winfield Lock and Dam remediation; and Socio-economic assessment of alternative environmental restoration technologies.

  18. Quarterly technical progress report, July-September 1982 on Energy Conversion Research and Development Programs

    SciTech Connect

    Not Available

    1983-12-01

    Detail design work was resumed on the superheater. Satisfactory bids were received for the air heater and lowest price responsive bidder was chosen. The conduct of three tests in the LMF1C series is reported. The status of the environmental monitoring program is reviewed. Preliminary analyses of the test data from the three tests conducted during the quarter are included. The heat fluxes, combustor pressure and combustor efficiencies are reported. The performance of the nozzle, diagnostic (Hall) channel and diffuser is compared with an analytical model for each test run. The performance of the new diffuser which was installed during the quarter is discussed. The test results from the downstream components; i.e. slag screen, radiant furnace, secondary combustor and materials test module, are discussed. Slag removal from the radiant furnace, refractory performance and metals performance is covered. A summary report is included on the results of the cold flow modeling of the secondary combustor, which involved variations in relative velocity of the secondary air, the angle of injection and the flow constriction. Diagnostic support of testing activities is described, including the use of the laser doppler velocimeter (LDV) for the secondary combustor modeling. Luminosity and line reversal temperature measurements were made in support of the CFFF tests. A photodiode line reversal system has been designed which has the promise of being more reliable, easier to install on operational equipment and cheaper.

  19. Atmospheric Radiation Measurement program climate research facility operations quarterly report October 1 - December 31, 2007.

    SciTech Connect

    Sisterson, D. L.

    2008-01-24

    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 (FY) dating back to 1998. Table 1 shows the accumulated maximum operation time (planned uptime), actual hours of operation, and variance (unplanned downtime) for the period October 1 - December 31, 2007, for the fixed sites and the mobile site. The AMF has been deployed to Germany and this was the final operational quarter. The first quarter comprises a total of 2,208 hours. Although the average exceeded our goal this quarter, a series of severe weather events (i.e., widespread ice storms) disrupted utility services, which affected the SGP performance measures. Some instruments were covered in ice and power and data communication lines were down for more than 10 days in some areas of Oklahoma and Kansas, which resulted in lost data at the SGP site. The Site Access Request System is a web-based database used to track visitors to the fixed sites, all of which have facilities that can be visited. The NSA locale has the Barrow and Atqasuk sites. The SGP site has a central facility, 23 extended facilities, 4 boundary facilities, and 3 intermediate facilities. The TWP locale has the Manus, Nauru, and Darwin sites. The AMF completed its mission at the end of this quarter in Haselback, Germany (FKB designation). NIM represents the AMF statistics for the Niamey, Niger, Africa, past deployment in 2006. PYE

  20. AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending March 31, 1984

    SciTech Connect

    Not Available

    1984-05-01

    The objective of the AR and TD Fossil Energy Materials Program is to conduct 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 management of the Program has been decentralized to DOE Oak Ridge Operations Office (ORO) and the Oak Ridge National Laboratory (ORNL) as technical support contractor. A substantial portion of the work on the AR and TD Fossil Energy Materials Program is performed by participating subcontractor organizations (technically monitored by Program staff members at ORNL and Argonne National Laboratory (ANL)). The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. Distribution is as shown on pages 467-475. Future reports will be issued on a quarterly basis to a similar distribution. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FYs 1982-86 (Ref. 1) in which projects are organized according to fossil energy technologies. A schematic summary of this organization is provided in Fig. 2. 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.

  1. Assessment of light water reactor accident management programs and experience

    SciTech Connect

    Hammersley, R.J.

    1992-03-01

    The objective of this report is to provide an assessment of the current light water reactor experience regarding accident management programs and associated technology developments. This assessment for light water reactor (LWR) designs is provided as a resource and reference for the development of accident management capabilities for the production reactors at the Savannah River Site. The specific objectives of this assessment are as follows: 1. Perform a review of the NRC, utility, and industry (NUMARC, EPRI) accident management programs and implementation experience. 2. Provide an assessment of the problems and opportunities in developing an accident management program in conjunction or following the Individual Plant Examination process. 3. Review current NRC, utility, and industry technological developments in the areas of computational tools, severe accident predictive tools, diagnostic aids, and severe accident training and simulation.

  2. UNOCAL: Parachute Creek Shale Oil Program. Environmental Monitoring Plan quarterly report. Fourth quarter 1987. Report for 1 October-31 December 1987

    SciTech Connect

    Not Available

    1988-02-29

    The Energy Security Act of 1980 established a program to provide financial assistance to private industry in the construction and operation of commercial-scale synthetic-fuels plants. The Parachute Creek Shale Oil Program is one of four projects awarded financial assistance. The support agreement included development of an Environmental Monitoring Plan, incorporating existing compliance monitoring and supplemental monitoring on water, air, solid waste, worker health and safety, and socio-economic impacts during the period 1986-1993. Phase I of this project is to produce 10,000 barrels per day of syncrude from oil shale, using the Unishale B process. During the fourth quarter, detailed analytical procedures and computer-data-management software were developed, sampling analytical and data-management standards were completed, and supplemental quality assurance and control programs were finalized. All of these activities are summarized in the report.

  3. Reactor materials program: LBB assessment - heat exchangers

    SciTech Connect

    Sindelar, R.L.

    1988-04-15

    A credible Loss-of-Coolant Accident (LOCA) for the Savannah River Production Reactors is being defined through studies of the failure mechanisms in the components of the process water (PW) system. A component that can exhibit leakage or cracking that is readily detected prior to a large-break failure demonstrates a Leak-Before-Break (LBB) capability and would allow safe reactor shutdown well in advance of a large break. A related sequence which encompasses LBB is the Detect-Before-Break (DBB) assessment which considers inspection of the component and crack detection by leakage or visual methods to ensure integrity of the pressure boundary of the component. The LBB capability of the PW system is performed by assessing the pressure boundary integrity and determining the ability to exhibit leakage prior to an unacceptably large break for each component of the system. It has been demonstrated that pipe weldments will not fail causing a sudden double-ended-guillotine break (DEGB) in the PW system. The LBB and DBB ability of the flanges, valves and pumps has also been demonstrated. The subject of this report is the demonstration of the LBB/DBB capability of the heat exchangers in the SRP process water system. 10 figs.

  4. Startup of the FFTF sodium cooled reactor. [Acceptance Test Program

    SciTech Connect

    Redekopp, R.D.; Umek, A.M.

    1981-03-01

    The Fast Flux Test Facility (FFTF), located on the Department of Energy (DOE) Hanford Reservation near Richland, Washington, is a 3 Loop 400 MW(t) sodium cooled fast reactor with a primary mission to test fuels and materials for development of the Liquid Metal Fast Breeder Reactor (LMFBR). Bringing FFTF to a condition to accomplish this mission is the goal of the Acceptance Test Program (ATP). This program was the mechanism for achieving startup of the FFTF. Highlights of the ATP involving the system inerting, liquid metal and inerted cell testing and initial ascent to full power are discussed.

  5. Methane coupling by membrane reactor. Quarterly report, June 25--September 24, 1996

    SciTech Connect

    Ma, Y.H.

    1996-12-28

    To prevent the deep oxidation of methane catalyzed by the direct contact between methane and the dense membrane material (SrFeCo{sub 0.5}O{sub 3{minus}x}), BaCe{sub 0.6}Sm{sub 0.4}O{sub 3} perovskite was coated on the inner surface of the dense membrane tube by the sol-gel technique. Different pretreatment methods were tested to compare their effects on the coated film. The morphology of the coated membrane was studied by SEM. The BaCe{sub 0.6}Sm{sub 0.4}O{sub 3}-coated membrane which was pretreated with a basic solution before coating was more evenly covered by the coating material. The oxygen permanence through the modified membrane tube were measured at different temperatures. The oxygen permanence were found to be about 70% lower than those of the unmodified tubes. The catalytic runs were carried out with La/MgO catalyst packed inside the membrane tube. The C{sub 2} yields obtained using the dense membrane reactor were less than 4%. This may have resulted from the fact that the methane fed to the tube side was still exposed to the uncoated area of the dense membrane surface due to the incomplete coverage of the coating material (BaCe{sub 0.6}Sm{sub 0.4}O{sub 3}). A hybrid dense membrane reactor, in which the oxygen was supplied by co-feeding oxygen with methane to the tube side and feeding air to the shell side, was used for the oxidative coupling of methane. Again, the inner surface of the membrane tube was coated with BaCe{sub 0.6}Sm{sub 0.4}O{sub 3} by the sol-gel technique, and the La/MgO catalyst was packed inside the membrane tube. The oxygen permanence through the membrane tube was found to be about ten times higher than that under non-reaction conditions. C{sub 2} yields up to 12% were obtained using the coated dense membrane reactor. These yields are higher than those obtained in an uncoated dense membrane reactor setup with methane and oxygen co-fed into the tube side, where the same catalyst was packed.

  6. Fischer-Tropsch synthesis in slurry reactor systems. Quarterly report, May 1, 1984-July 31, 1984

    SciTech Connect

    Satterfield, C.N.; Bartos, T.; Hanlon, R.; Huff, G.A. Jr.; Matsumoto, D.

    1984-01-01

    We suspect that a number of reports in the published literature of catalyst preparations that supposedly minimize wax formation are erroneous in that wax may actually have accumulated in catalyst pores and that insufficient time may have been allowed for the effluent to represent true intrinsic kinetics. Mathematical simulations show the effect of pressure, temperature, rate constant, feed composition, space velocity and Flory parameter ..cap alpha.., on time required for pores to fill, upon liquid product distribution and vapor composition leaving the reactor. The pore filling rate and condensed product composition vary with position through the reactor but not with time. The maximum filling rate does not occur at the same position in the bed as the maximum synthesis rate. For reaction conditions of industrial interest, the greatest effect is caused by the assumed carbon number distribution of the products. A rigorous parameter to generalize the results is not immediately evident. We reported studies of the effect of the nature of the liquid on the activity and selectivity of a reduced fused magnetite catalyst. For interpretation of such studies it is necessary to have data on solubilities of hydrogen and carbon monoxide in the liquids of interest. New data at elevated temperatures and pressure are reported for octacosane, phenanthreene and Fomblin, a perfluorinated polyether, and compared to previous literature on a variety of liquids. When hydrogen solubilities are reported on a volumetric basis, substances of a similar chemical nature have very similar solubilities.

  7. AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending December 31, 1981

    SciTech Connect

    Not Available

    1982-04-01

    The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1982-1986 in which projects are organized according to fossil energy technologies. This report is divided into parts and chapters with each part describing projects related to a particular fossil energy technology. Chapters within a part provide details of the various projects associated with that technology. 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. Plans for the program will be issued annually. A draft of the program plan for FY 1982 to 1986 has been prepared and is in the review process. The implementation of these plans will be reflected by these quarterly progress reports, and this dissemination of information will bw augmented by topical or final reports as appropriate.

  8. Oak Ridge Reservation Federal Facility Agreement quarterly report for the environmental restoration program. Volume 2: January--March 1995

    SciTech Connect

    1995-04-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that 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). 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. The report describes the technical status of the following: Y-12 Plant; Oak Ridge National Lab; K-25 Plant; and Oak Ridge Reservation boundary areas. The report also describes technical programs, namely: the Oak Ridge environmental information system, remote sensing and special survey program, and the risk assessment program.

  9. Oak Ridge Reservation Federal Facility Agreement quarterly report for the environmental restoration program. Volume 3: April--June 1995

    SciTech Connect

    1995-07-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that 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). 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. The report describes the technical status of the following: Y-12 Plant; Oak Ridge National Lab; K-25 Plant; and Oak Ridge Reservation boundary areas. The report also describes technical programs, namely: the Oak Ridge environmental information system, remote sensing and special survey program, and the risk assessment program.

  10. Heavy-Section Steel Technology Program quarterly progress report, January-March 1980

    SciTech Connect

    Whitman, G.D.; Bryan, R.H.

    1980-07-01

    The program comprises studies related to all areas of the technology of materials fabricated into thick-section primary-coolant containment systems of light-water-cooled nuclear power reactors. The principal area of investigation is the behavior and structural integrity of steel pressure vessels containing cracklike flaws. Current work is organized into the following tasks: (1) program administration and procurement, (2) fracture mechanics analyses and investigations, (3) investigations of irradiated materials, (4) thermal shock investigations, and (5) pressure vessel investigations. Work performed under the existing research and development subcontracts is included in this report.